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Note: This page contains sample records for the topic "research vessel mirai" from the National Library of EnergyBeta (NLEBeta).
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1

ARM - Campaign Instrument - mirai  

NLE Websites -- All DOE Office Websites (Extended Search)

govInstrumentsmirai govInstrumentsmirai Comments? We would love to hear from you! Send us a note below or call us at 1-888-ARM-DATA. Send Campaign Instrument : JAMSTEC Research Vessel Mirai (MIRAI) Instrument Categories Radiometric, Cloud Properties, Ocean Observations, Surface Meteorology, Atmospheric Profiling Campaigns Nauru99 Campaign [ Download Data ] Tropical Western Pacific, 1999.06.16 - 1999.07.15 Primary Measurements Taken The following measurements are those considered scientifically relevant. Refer to the datastream (netcdf) file headers for the list of all available measurements, including those recorded for diagnostic or quality assurance purposes. Sea surface temperature Liquid water content Cloud fraction CO2 concentration Backscatter depolarization ratio Hydrometeor size

2

NETL: News Release - Ocean Research Vessel Returns with Undersea 'Treasure'  

NLE Websites -- All DOE Office Websites (Extended Search)

23, 2002 23, 2002 Ocean Research Vessel Returns with Undersea 'Treasure' of Methane Hydrates Largest Amount of Marine Hydrate Core Ever Recovered - The R/V JOIDES Resolution - The R/V JOIDES Resolution VICTORIA, BRITISH COLUMBIA - An internationally funded ocean research vessel has returned to port after a two-month expedition off the Oregon coast, bringing with it the largest amount of marine methane hydrate core samples ever recovered for scientific study. The R/V JOIDES Resolution, the world's largest scientific drillship, docked at Victoria, British Columbia earlier this month and began offloading pressure vessels containing methane hydrates recovered 50 miles offshore of Oregon from an area known as Hydrate Ridge. The pressure vessels, each six feet long and four inches in diameter, will

3

Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Research  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Research and Development by the Light Water Reactor Sustainability Program Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Research and Development by the Light Water Reactor Sustainability Program The Department of Energy's (DOE's) Light Water Reactor Sustainability (LWRS) Program is a five year effort that 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 operation of existing commercial nuclear power reactors. This year, the Materials Aging and Degradation (MAaD) Pathway of this program has placed emphasis on emerging

4

Experimental and Numerical Study of the Turbulence Characteristics of Airflow around a Research Vessel  

Science Conference Proceedings (OSTI)

Airflow distortion by research vessels has been shown to significantly affect micrometeorological measurements. This study uses an efficient time-dependent large-eddy simulation numerical technique to investigate the effect of the R/V Tangaroa on ...

Stphane Popinet; Murray Smith; Craig Stevens

2004-10-01T23:59:59.000Z

5

Why Web GIS May Not be Enough: A Case Study with the Virtual Research Vessel  

E-Print Network (OSTI)

Why Web GIS May Not be Enough: A Case Study with the Virtual Research Vessel DAWN J. WRIGHT1 infrastructure is desired and needed for ready access to data and the resulting maps via web GIS, in order, and the quantitative evaluation of scientific hypotheses. For widespread data access, web GIS is therefore only

Wright, Dawn Jeannine

6

Use of Polycarbonate Vacuum Vessels in High-Temperature Fusion-Plasma Research  

Science Conference Proceedings (OSTI)

Magnetic fusion energy (MFE) research requires ultrahigh-vacuum (UHV) conditions, primarily to reduce plasma contamination by impurities. For radiofrequency (RF)-heated plasmas, a great benefit may accrue from a non-conducting vacuum vessel, allowing external RF antennas which avoids the complications and cost of internal antennas and high-voltage high-current feedthroughs. In this paper we describe these and other criteria, e.g., safety, availability, design flexibility, structural integrity, access, outgassing, transparency, and fabrication techniques that led to the selection and use of 25.4-cm OD, 1.6-cm wall polycarbonate pipe as the main vacuum vessel for an MFE research device whose plasmas are expected to reach keV energies for durations exceeding 0.1 s

B. Berlinger, A. Brooks, H. Feder, J. Gumbas, T. Franckowiak and S.A. Cohen

2012-09-27T23:59:59.000Z

7

A Multisensor Comparison of Ocean Wave Frequency Spectra from a Research Vessel during the Southern Ocean Gas Exchange Experiment  

Science Conference Proceedings (OSTI)

Obtaining accurate measurements of wave statistics from research vessels remains a challenge due to platform motion. One principal correction is the removal of ship heave and Doppler effects from point measurements. Here, open ocean wave ...

Alejandro Cifuentes-Lorenzen; James. B. Edson; Christopher J. Zappa; Ludovic Bariteau

8

ORNL/TM-2012/380 Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Research  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

2/380 2/380 Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Research and Development by the Light Water Reactor Sustainability Program September 2012 Prepared by Cyrus Smith Randy Nanstad Robert Odette Dwight Clayton Katie Matlack Pradeep Ramuhalli Glenn Light DOCUMENT AVAILABILITY Reports produced after January 1, 1996, are generally available free via the U.S. Department of Energy (DOE) Information Bridge. Web site http://www.osti.gov/bridge Reports produced before January 1, 1996, may be purchased by members of the public from the following source. National Technical Information Service 5285 Port Royal Road Springfield, VA 22161 Telephone 703-605-6000 (1-800-553-6847) TDD 703-487-4639 Fax 703-605-6900

9

Reactor pressure vessel integrity research at the Oak Ridge National Laboratory  

Science Conference Proceedings (OSTI)

Maintaining the integrity of the reactor pressure vessel (RPV) in a light-water-cooled nuclear power plant is crucial in preventing and controlling severe accidents that have the potential for major contamination release. The RPV is the only key safety-related component of the plant for which a duplicate or redundant backup system does not exist. It is therefore imperative to understand and be able to predict the integrity inherent in the RPV. For this reason, the U.S. Nuclear Regulatory Commission has established the related research programs at ORNL described herein to provide for the development and confirmation of the methods used for: (1) establishing the irradiation exposure conditions within the RPV in the Embrittlement Data Base and Dosimetry Evaluation Program, (2) assessing the effects of irradiation on the RPV materials in the Heavy-Section Steel Irradiation Program, and (3) developing overall structural and fracture analyses of RPVs in the Heavy-Section Steel Technology Program.

Corwin, W.R.; Pennell, W.E.; Pace, J.V.

1995-12-31T23:59:59.000Z

10

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

Science Conference Proceedings (OSTI)

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 750C, 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.

J. K. Wright; R. N. Wright

2010-07-01T23:59:59.000Z

11

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

Science Conference Proceedings (OSTI)

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 900C 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, 2Cr-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.

J. K. Wright; R. N. Wright

2008-04-01T23:59:59.000Z

12

Underwater radiated noise measurements of a noise?reduced research vessel: Comparison between a U.S. Navy noise range and a simple hydrophone mooring.  

Science Conference Proceedings (OSTI)

[A feasibility study was undertaken to characterize underwater radiated noise for a new class of noise?reduced fisheries research vessels using a field?deployable hydrophone system. Recent studies have demonstrated that vessel?radiated noise can impact the behavior of fish

Alex De Robertis; Christopher D. Wilson; Peter H. Dahl

2011-01-01T23:59:59.000Z

13

Underwater radiated noise measurements of a noise-reduced research vessel: comparison between a US Navy noise range and a simple hydrophone mooring.  

Science Conference Proceedings (OSTI)

A feasibility study was undertaken to characterize underwater radiated noise for a new class of noise-reduced fisheries research vessels using a field-deployable hydrophone system. Recent studies have demonstrated that vessel-radiated noise can impact the behavior of fish

Alex De Robertis; Christopher Wilson

2014-01-01T23:59:59.000Z

14

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

SciTech Connect

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.

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

2012-09-01T23:59:59.000Z

15

Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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

16

Cloud response to the meandering Kuroshio Extension front  

Science Conference Proceedings (OSTI)

A unique set of observations onboard research vessel (R/V) Mirai in April 2010 captured a striking cloud hole over a cold meander of the Kuroshio Extension (KE) east of Japan as corroborated by atmospheric soundings, ceilometer, ship-board ...

Hiroyuki Tomita; Shang-Ping Xie; Hiroki Tokinaga; Yoshimi Kawai

17

Floating vessel  

SciTech Connect

The invention relates to a floating vessel which may be used in oil recovery. The assembly consists of a vertical column having a relatively small diameter. The column has a buoyancy capacity and is supplied with a ballast section having a larger diameter at its end. An upper structure is movably connected to the column. The column and the ballast chamber determine the limits of a shaft. The shaft is open at its lower end and is supplied with means to let fluid into the shaft over a relatively large area. (8 claims)

1974-05-14T23:59:59.000Z

18

CHF Enhancement by Vessel Coating for External Reactor Vessel Cooling  

SciTech Connect

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.

Fan-Bill Cheung; Joy L. Rempe

2004-06-01T23:59:59.000Z

19

Argonne Liquid-Metal Advanced Burner Reactor : components and in-vessel system thermal-hydraulic research and testing experience - pathway forward.  

Science Conference Proceedings (OSTI)

This white paper provides an overview and status report of the thermal-hydraulic nuclear research and development, both experimental and computational, conducted predominantly at Argonne National Laboratory. Argonne from the early 1970s through the early 1990s was the Department of Energy's (DOE's) lead lab for thermal-hydraulic development of Liquid Metal Reactors (LMRs). During the 1970s and into the mid-1980s, Argonne conducted thermal-hydraulic studies and experiments on individual reactor components supporting the Experimental Breeder Reactor-II (EBR-II), Fast Flux Test Facility (FFTF), and the Clinch River Breeder Reactor (CRBR). From the mid-1980s and into the early 1990s, Argonne conducted studies on phenomena related to forced- and natural-convection thermal buoyancy in complete in-vessel models of the General Electric (GE) Prototype Reactor Inherently Safe Module (PRISM) and Rockwell International (RI) Sodium Advanced Fast Reactor (SAFR). These two reactor initiatives involved Argonne working closely with U.S. industry and DOE. This paper describes the very important impact of thermal hydraulics dominated by thermal buoyancy forces on reactor global operation and on the behavior/performance of individual components during postulated off-normal accident events with low flow. Utilizing Argonne's LMR expertise and design knowledge is vital to the further development of safe, reliable, and high-performance LMRs. Argonne believes there remains an important need for continued research and development on thermal-hydraulic design in support of DOE's and the international community's renewed thrust for developing and demonstrating the Global Nuclear Energy Partnership (GNEP) reactor(s) and the associated Argonne Liquid Metal-Advanced Burner Reactor (LM-ABR). This white paper highlights that further understanding is needed regarding reactor design under coolant low-flow events. These safety-related events are associated with the transition from normal high-flow operation to natural circulation. Low-flow coolant events are the most difficult to design for because they involve the most complex thermal-hydraulic behavior induced by the dominance of thermal-buoyancy forces acting on the coolants. Such behavior can cause multiple-component flow interaction phenomena, which are not adequately understood or appreciated by reactor designers as to their impact on reactor performance and safety. Since the early 1990s, when DOE canceled the U.S. Liquid Metal Fast Breeder Reactor (LMFBR) program, little has been done experimentally to further understand the importance of the complex thermal-buoyancy phenomena and their impact on reactor design or to improve the ability of three-dimensional (3-D) transient computational fluid dynamics (CFD) and structures codes to model the phenomena. An improved experimental data base and the associated improved validated codes would provide needed design tools to the reactor community. The improved codes would also facilitate scale-up from small-scale testing to prototype size and would facilitate comparing performance of one reactor/component design with another. The codes would also have relevance to the design and safety of water-cooled reactors. To accomplish the preceding, it is proposed to establish a national GNEP-LMR research and development center at Argonne having as its foundation state-of-art science-based infrastructure consisting of: (a) thermal-hydraulic experimental capabilities for conducting both water and sodium testing of individual reactor components and complete reactor in-vessel models and (b) a computational modeling development and validation capability that is strongly interfaced with the experimental facilities. The proposed center would greatly advance capabilities for reactor development by establishing the validity of high-fidelity (i.e., close to first principles) models and tools. Such tools could be used directly for reactor design or for qualifying/tuning of lower-fidelity models, which now require costly experimental qualification for each different type of design

Kasza, K.; Grandy, C.; Chang, Y.; Khalil, H.; Nuclear Engineering Division

2007-06-30T23:59:59.000Z

20

MMA Tugboat/ Barge/ Vessel | Open Energy Information  

Open Energy Info (EERE)

MMA Tugboat/ Barge/ Vessel MMA Tugboat/ Barge/ Vessel Jump to: navigation, search Basic Specifications Facility Name MMA Tugboat/ Barge/ Vessel Overseeing Organization Maine Maritime Academy Hydrodynamic Testing Facility Type Tow Vessel Depth(m) 15.2 Water Type Saltwater Cost(per day) Contact POC Special Physical Features Tug: 73 ft (2)16V-92 Detroits Barge: 43 ft by 230ft Research Vessel Friendship: 40 foot vessel w/ 6 cylinder Cummins diesel engine and A-Frame crane Towing Capabilities Towing Capabilities Yes Maximum Velocity(m/s) 5.1 Wavemaking Capabilities Wavemaking Capabilities None Channel/Tunnel/Flume Channel/Tunnel/Flume None Wind Capabilities Wind Capabilities None Control and Data Acquisition Description Full onbard Navigation, GPS, marine radar and depth plotter; standard PC onboard can be configured as needed for data acquisition needs

Note: This page contains sample records for the topic "research vessel mirai" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

Prediction of Vessel Icing  

Science Conference Proceedings (OSTI)

Vessel icing from wave-generated spray is a severe hazard to expanded marine operations in high latitudes. Hardships in making observations during operations, combined with differences in vessel type and heading, have resulted in great ...

J. E. Overland; C. H. Pease; R. W. Preisendorfer; A. L. Comiskey

1986-12-01T23:59:59.000Z

22

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 · Remote Handling - Maintenance Approach & Component Classification - In-Vessel Transporter - Component

23

Materials Reliability Program: Reactor Pressure Vessel Integrity Primer (MRP-278)  

Science Conference Proceedings (OSTI)

This primer is based on two earlier Electric Power Research Institute (EPRI) reports: Reactor Vessel Embrittlement Management Handbook: A Handbook for Managing Reactor Vessel Embrittlement and Vessel Integrity (TR-101975-T2) and Primer: Fracture Mechanics in the Nuclear Power Industry (NP-5792-SR, Rev. 1). The information in those earlier reports has been updated extensively and focuses on todays reactor pressure vessel (RPV) embrittlement, integrity, and plant license renewal issues. This RPV integrity ...

2010-06-09T23:59:59.000Z

24

Reactor vessel support system  

DOE Patents (OSTI)

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.

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

1982-01-01T23:59:59.000Z

25

Cover Heated, Open Vessels  

SciTech Connect

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

2006-01-01T23:59:59.000Z

26

TMI-2 Vessel Investigation Project integration report  

Science Conference Proceedings (OSTI)

The Three Mile Island Unit 2 (TMI-2) Vessel Investigation Project (VIP) was an international effort that was sponsored by the Nuclear Energy Agency of the Organization for Economic Cooperation and Development. The primary objectives of the VIP were to extract and examine samples from the lower head and to evaluate the potential modes of failure and the margin of structural integrity that remained in the TMI-2 reactor vessel during the accident. This report presents a summary of the major findings and conclusions that were developed from research during the VIP. Results from the various elements of the project are integrated to form a cohesive understanding of the vessel`s condition after the accident.

Wolf, J. R.; Rempe, J. L.; Stickler, L. A.; Korth, G. E.; Diercks, D. R.; Neimark, L. A.; Akers, D W; Schuetz, B. K.; Shearer, T L; Chavez, S. A.; Thinnes, G. L.; Witt, R. J.; Corradini, M L; Kos, J. A. [EG and G Idaho, Inc., Idaho Falls, ID (United States)

1994-03-01T23:59:59.000Z

27

Reconnecting broken blood vessels  

NLE Websites -- All DOE Office Websites (Extended Search)

Reconnecting broken blood vessels Reconnecting broken blood vessels Name: Catherine A Kraft Status: N/A Age: N/A Location: N/A Country: N/A Date: N/A Question: While watching the television program "Chicago Hope" the other day, I watched a doctor sew someone's ear back on using an elaborate microscope. I was wondering if a surgeon is required to reconnect all the broken blood vessels, and how you would accomplish this? Thanks for your time! Replies: I'm not a surgeon, but I think the answer to your question is "no." The blood will flow across the wound (out the end of one blood vessel and into the end of another), although not efficiently. I believe they sometimes use leeches sucking on the end of the reconnected part to help induce flow of blood in the right direction through the area. You probably do need to put the ends of the major vessels near each other, so the distribution of blood flow is reasonably like it was before the injury, and so the vessels can eventually reconnect. But probably the microscope is used mostly to be sure the various layers of muscle, connective tissue, and fat are connected together correctly.

28

Reactor vessel annealing system  

DOE Patents (OSTI)

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).

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)

1991-01-01T23:59:59.000Z

29

ARM - Measurement - Sea surface temperature  

NLE Websites -- All DOE Office Websites (Extended Search)

govMeasurementsSea surface temperature govMeasurementsSea surface temperature ARM Data Discovery Browse Data Comments? We would love to hear from you! Send us a note below or call us at 1-888-ARM-DATA. Send Measurement : Sea surface temperature The temperature of sea water near the surface. Categories Surface Properties Instruments The above measurement is considered scientifically relevant for the following instruments. Refer to the datastream (netcdf) file headers of each instrument for a list of all available measurements, including those recorded for diagnostic or quality assurance purposes. External Instruments ECMWF : European Centre for Medium Range Weather Forecasts Model Data Field Campaign Instruments ECMWF : European Centre for Medium Range Weather Forecasts Model Data MIRAI : JAMSTEC Research Vessel Mirai

30

ARM - Measurement - Cloud droplet size  

NLE Websites -- All DOE Office Websites (Extended Search)

droplet size droplet size ARM Data Discovery Browse Data Comments? We would love to hear from you! Send us a note below or call us at 1-888-ARM-DATA. Send Measurement : Cloud droplet size Linear size (e.g. radius or diameter) of a cloud particle Categories Cloud Properties Instruments The above measurement is considered scientifically relevant for the following instruments. Refer to the datastream (netcdf) file headers of each instrument for a list of all available measurements, including those recorded for diagnostic or quality assurance purposes. Field Campaign Instruments CPI : Cloud Particle Imager CVI-AIR : Counterflow Virtual Impactor MIRAI : JAMSTEC Research Vessel Mirai PDI : Phase Doppler Interferometer UAV-PROTEUS-MICRO : Proteus Cloud Microphysics Instruments SPEC-CPI : Stratton Park Engineering Company - Cloud particle imager

31

ARM - Measurement - Backscatter depolarization ratio  

NLE Websites -- All DOE Office Websites (Extended Search)

govMeasurementsBackscatter depolarization ratio govMeasurementsBackscatter depolarization ratio ARM Data Discovery Browse Data Comments? We would love to hear from you! Send us a note below or call us at 1-888-ARM-DATA. Send Measurement : Backscatter depolarization ratio The ratio of cross polarized to co-polarized elastic backscatter. Categories Aerosols Instruments The above measurement is considered scientifically relevant for the following instruments. Refer to the datastream (netcdf) file headers of each instrument for a list of all available measurements, including those recorded for diagnostic or quality assurance purposes. ARM Instruments HSRL : High Spectral Resolution Lidar RL : Raman Lidar Field Campaign Instruments HSRL : High Spectral Resolution Lidar MIRAI : JAMSTEC Research Vessel Mirai MPL-AIR : Micropulse Lidar- Airborne

32

Decisions decisions plant vessels  

Science Conference Proceedings (OSTI)

This paper describes concepts for a family of plant vessels that help users make decisions or reach goals. The concepts use plants to mark time or answer questions for the user, creating a connection between the user and the individual plant. These concepts ...

Jenny Liang

2007-08-01T23:59:59.000Z

33

A Xenon Condenser with a Remote Liquid Storage Vessel  

E-Print Network (OSTI)

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.

Slutsky, S; Breuer, H; Dobi, A; Hall, C; Langford, T; Leonard, D; Kaufman, L J; Strickland, V; Voskanian, N

2009-01-01T23:59:59.000Z

34

A Xenon Condenser with a Remote Liquid Storage Vessel  

E-Print Network (OSTI)

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.

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

2009-07-13T23:59:59.000Z

35

Application of Computational Physics: Blood Vessel Constrictions and Medical Infuses  

E-Print Network (OSTI)

Application of computation in many fields are growing fast in last two decades. Increasing on computation performance helps researchers to understand natural phenomena in many fields of science and technology including in life sciences. Computational fluid dynamic is one of numerical methods which is very popular used to describe those phenomena. In this paper we propose moving particle semi-implicit (MPS) and molecular dynamics (MD) to describe different phenomena in blood vessel. The effect of increasing the blood pressure on vessel wall will be calculate using MD methods, while the two fluid blending dynamics will be discussed using MPS. Result from the first phenomenon shows that around 80% of constriction on blood vessel make blood vessel increase and will start to leak on vessel wall, while from the second phenomenon the result shows the visualization of two fluids mixture (drugs and blood) influenced by ratio of drugs debit to blood debit. Keywords: molecular dynamic, blood vessel, fluid dynamic, moving particle semi implicit.

Suprijadi; Mohamad Rendi; Petrus Subekti; Sparisoma Viridi

2013-12-14T23:59:59.000Z

36

Radiant vessel auxiliary cooling system  

DOE Patents (OSTI)

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.

Germer, John H. (San Jose, CA)

1987-01-01T23:59:59.000Z

37

High pressure storage vessel  

DOE Patents (OSTI)

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.

Liu, Qiang

2013-08-27T23:59:59.000Z

38

Reactor pressure vessel nozzle  

DOE Patents (OSTI)

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.

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

1994-10-04T23:59:59.000Z

39

Reactor Vessel Embrittlement Management Handbook: A Handbook for Managing Reactor Vessel Embrittlement and Vessel Integrity  

Science Conference Proceedings (OSTI)

For many reactor pressure vessels, embrittlement is the primary concern for continued safe operation. The shutdown of the Yankee Rowe plant because of uncertainties related to embrittlement of the vessel demonstrates the importance of adequately addressing embrittlement issues. Managing embrittlement requires integration, management, and implementation of diverse technical, regulatory, planning, and economic activities. An effective embrittlement management program will ensure vessel safety and reliabili...

1994-01-22T23:59:59.000Z

40

Vessel structural support system  

SciTech Connect

Vessel structural support system for laterally and vertically supporting a vessel, such as a nuclear steam generator having an exterior bottom surface and a side surface thereon. The system includes a bracket connected to the bottom surface. A support column is pivotally connected to the bracket for vertically supporting the steam generator. The system also includes a base pad assembly connected pivotally to the support column for supporting the support column and the steam generator. The base pad assembly, which is capable of being brought to a level position by turning leveling nuts, is anchored to a floor. The system further includes a male key member attached to the side surface of the steam generator and a female stop member attached to an adjacent wall. The male key member and the female stop member coact to laterally support the steam generator. Moreover, the system includes a snubber assembly connected to the side surface of the steam generator and also attached to the adjacent wall for dampening lateral movement of the steam generator. In addition, the system includes a restraining member of "flat" attached to the side surface of the steam generator and a bumper attached to the adjacent wall. The flat and the bumper coact to further laterally support the steam generator.

Jenko, James X. (N. Versailles, PA); Ott, Howard L. (Kiski Twp., Allegheny County, PA); Wilson, Robert M. (Plum Boro, PA); Wepfer, Robert M. (Murrysville, PA)

1992-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "research vessel mirai" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

Core Vessel Insert Handling Robot for the Spallation Neutron Source  

Science Conference Proceedings (OSTI)

The Spallation Neutron Source provides the world's most intense pulsed neutron beams for scientific research and industrial development. Its eighteen neutron beam lines will eventually support up to twenty-four simultaneous experiments. Each beam line consists of various optical components which guide the neutrons to a particular instrument. The optical components nearest the neutron moderators are the core vessel inserts. Located approximately 9 m below the high bay floor, these inserts are bolted to the core vessel chamber and are part of the vacuum boundary. They are in a highly radioactive environment and must periodically be replaced. During initial SNS construction, four of the beam lines received Core Vessel Insert plugs rather than functional inserts. Remote replacement of the first Core Vessel Insert plug was recently completed using several pieces of custom-designed tooling, including a highly complicated Core Vessel Insert Robot. The design of this tool are discussed.

Graves, Van B [ORNL; Dayton, Michael J [ORNL

2011-01-01T23:59:59.000Z

42

Coal gasification vessel  

DOE Patents (OSTI)

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).

Loo, Billy W. (Oakland, CA)

1982-01-01T23:59:59.000Z

43

Reactor vessel support system. [LMFBR  

DOE Patents (OSTI)

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.

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

1980-05-09T23:59:59.000Z

44

LPG storage vessel cracking experience  

SciTech Connect

In order to evaluate liquefied petroleum gas (LPG) handling and storage hazards, Caltex Petroleum Corp. (Dallas) surveyed several installations for storage vessel cracking problems. Cracking was found in approximately one-third of the storage vessels. In most cases, the cracking appeared to be due to original fabrication problems and could be removed without compromising the pressure containment. Several in-service cracking problems found were due to exposure to wet hydrogen sulfide. Various procedures were tried in order to minimize the in-service cracking potential. One sphere was condemned because of extensive subsurface cracking. This article's recommendations concern minimizing cracking on new and existing LPG storage vessels.

Cantwell, J.E. (Caltex Petroleum Corp., P.O. Box 619500, Dallas, TX (US))

1988-10-01T23:59:59.000Z

45

LPG storage vessel cracking experience  

SciTech Connect

As part of an overall company program to evaluate LPG handling and storage hazards the authors surveyed several installations for storage vessel cracking problems. Cracking was found in approximately one third of the storage vessels. In most cases the cracking appeared due to original fabrication problems and could be removed without compromising the pressure containment. Several in-service cracking problems due to exposure to wet hydrogen sulfide were found. Various procedures were tried in order to minimize the in-service cracking potential. One sphere was condemned because of extensive subsurface cracking. Recommendations are made to minimize cracking on new and existing LPG storage vessels.

Cantwell, J.E.

1988-01-01T23:59:59.000Z

46

Cryogenic Pressure Vessels: Progress and Plans  

NLE Websites -- All DOE Office Websites (Extended Search)

Pressure Vessel workshop, LLNL, February 15, 2011, p. 1 Cryogenic Pressure Vessels: Progress and Plans Salvador Aceves, Gene Berry, Francisco Espinosa, Ibo Matthews, Guillaume...

47

Reactor vessel seal service fixture  

DOE Patents (OSTI)

An apparatus for the preparation of exposed sealing surfaces along the open rim of a nuclear reactor vessel comprised of a motorized mechanism for traveling along the rim and simultaneously brushing the exposed surfaces is described.

Ritz, W.C.

1975-12-01T23:59:59.000Z

48

Recent United States and International Experiences in Reactor Vessel and Internals Segmentation  

Science Conference Proceedings (OSTI)

The segmentation of reactor vessels and internals is one of the most challenging tasks in nuclear power plant decommissioning. Many experiences, lessons learned, and best practices have been gained through the execution of the first few reactor vessel and internals segmentation projects. The Electric Power Research Institute (EPRI) previously documented the experiences, lessons learned, best practices, and technologies used in decommissioning reactor vessel and internals segmentation projects in the Unit...

2011-11-29T23:59:59.000Z

49

PRESSURE VESSEL FABRICATION USING T-1 STEEL  

SciTech Connect

The fabrication of pressure vessels using C-l steel is described. The welding, welding electrodes, explosionbulge test, and impact and fatigue properties for the pressure vessel are given. (W.L.H.)

Franco-Ferreira, E.A.

1957-11-14T23:59:59.000Z

50

Mechanical behavior analysis of CDIO production-blood vessel robot in curved blood vessel  

Science Conference Proceedings (OSTI)

In order to analyze mechanical behavior of blood vessel robot (student's CDIO production) in curved blood, and provide the data for outline design of robot, the flow field out side of robot is numerical simulated. The results show that the vessel shape ... Keywords: blood vessel robot, curved blood vessel, mechanical behavior analysis, numerical simulation

Fan Jiang; Chunliang Zhang; Yijun Wang

2010-10-01T23:59:59.000Z

51

Reactor pressure vessel vented head  

DOE Patents (OSTI)

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.

Sawabe, James K. (San Jose, CA)

1994-01-11T23:59:59.000Z

52

Coal gasification vessel. [Patent application  

DOE Patents (OSTI)

A vessel system comprises an outer shell of carbon fibers held in a binder, a coolant circulation mechanism and control mechanism and an inner shell 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 can be computer controlled and can be used to monitor and modulate the coolant which is provided through the circulation mechanism for cooling and protecting the carbon fiber and outer shell. The control mechanism is also used to locate any isolated hot spots which may occur through the local disintegration of the inner refractory shell.

Loo, B.W.

1981-03-17T23:59:59.000Z

53

IWTU Construction Workers Set Largest Process Vessel  

NLE Websites -- All DOE Office Websites (Extended Search)

IWTU Construction Workers Set Largest Process Vessel IWTU Construction Workers Set Largest Process Vessel Click on image to enlarge Construction of the Integrated Waste Treatment Unit (IWTU) took a major step forward on Sept. 2, 2009 as crews lifted into place the largest of the six process vessels that will be used to treat radioactive liquid waste stored at the site. The IWTU will use a steam reforming process to solidify the waste for eventual shipment out of Idaho. The vessel and its skid, or framework, were constructed at Premier Technologies in Blackfoot. (Premier is the main small business partner for CH2M-WG Idaho (CWI), the contractor for DOE's Idaho Cleanup Project.) The Carbon Reduction Reformer vessel and skid weigh approximately 60 tons (120,000 lbs.). Because of the weight of the vessel and the location of the

54

Neutron Assay System for Confinement Vessel Disposition  

Science Conference Proceedings (OSTI)

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.

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

2012-07-13T23:59:59.000Z

55

Blood Vessel Normalization in the Hamster Oral Cancer Model for Experimental Cancer Therapy Studies  

Science Conference Proceedings (OSTI)

Normalization of tumor blood vessels improves drug and oxygen delivery to cancer cells. The aim of this study was to develop a technique to normalize blood vessels in the hamster cheek pouch model of oral cancer. Materials and Methods: Tumor-bearing hamsters were treated with thalidomide and were compared with controls. Results: Twenty eight hours after treatment with thalidomide, the blood vessels of premalignant tissue observable in vivo became narrower and less tortuous than those of controls; Evans Blue Dye extravasation in tumor was significantly reduced (indicating a reduction in aberrant tumor vascular hyperpermeability that compromises blood flow), and tumor blood vessel morphology in histological sections, labeled for Factor VIII, revealed a significant reduction in compressive forces. These findings indicated blood vessel normalization with a window of 48 h. Conclusion: The technique developed herein has rendered the hamster oral cancer model amenable to research, with the potential benefit of vascular normalization in head and neck cancer therapy.

Ana J. Molinari; Romina F. Aromando; Maria E. Itoiz; Marcela A. Garabalino; Andrea Monti Hughes; Elisa M. Heber; Emiliano C. C. Pozzi; David W. Nigg; Veronica A. Trivillin; Amanda E. Schwint

2012-07-01T23:59:59.000Z

56

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

SciTech Connect

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.

Joy L. Rempe

2005-11-01T23:59:59.000Z

57

Rancho Seco Reactor Vessel Segmentation Experience Report  

Science Conference Proceedings (OSTI)

This report documents the approach taken by Sacramento Municipal Utility District (SMUD) in the segmentation and disposal of the Reactor Vessel from the Rancho Seco Nuclear Generating Station (RSNGS). The location of the Rancho Seco plant placed major constraints on the shipping options available for large plant components (Steam Generators and Reactor Vessel). This report details the engineering evaluations leading to the segmentation and disposal of the Reactor Vessel (RV). It describes the key element...

2008-03-18T23:59:59.000Z

58

Embrittlement of Nuclear Reactor Pressure Vessels  

Science Conference Proceedings (OSTI)

Boiler and Pressure Vessel Code Section III App. G Protection Against Nonductile Fracture (New York: American Society of Mechanical Engineers, 1986 ). 3.

59

Lightweight bladder lined pressure vessels - Energy Innovation ...  

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 ...

60

Reactor pressure vessel vented head  

DOE Patents (OSTI)

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.

Sawabe, J.K.

1994-01-11T23:59:59.000Z

Note: This page contains sample records for the topic "research vessel mirai" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

Pressure vessel and piping codes  

SciTech Connect

Section III of the ASME Boiler and Pressure Vessel Code contains simplified design formulas for placing bounds on the plastic deformations in nuclear power plant piping systems. For Class 1 piping a simple equation is given in terms of primary load stress indices (B/sub 1/ and B/sub 2/) and nominal pressure and bending stresses. The B/sub 1/ and B/sub 2/ stress indices reflect the capacities of various piping products to carry load without gross plastic deformation. In this paper, the significance of the indices, nominal stresses, and limits given in the Code for Class 1 piping and corresponding requirements for Class 2 and Class 3 piping are discussed. Motivation behind recent (1978-1981) changes in the indices and in the associated stress limits is presented.

Moore, S.E.; Rodabaugh, E.C.

1982-11-01T23:59:59.000Z

62

Device for inspecting vessel surfaces  

DOE Patents (OSTI)

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.

Appel, D. Keith (Aiken, SC)

1995-01-01T23:59:59.000Z

63

Nuclear reactor vessel fuel thermal insulating barrier  

DOE Patents (OSTI)

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.

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

2013-03-19T23:59:59.000Z

64

A review of vessel extraction techniques and algorithms  

Science Conference Proceedings (OSTI)

Vessel segmentation algorithms are the critical components of circulatory blood vessel analysis systems. We present a survey of vessel extraction techniques and algorithms. We put the various vessel extraction approaches and techniques in perspective ... Keywords: Magnetic resonance angiography, X-ray angiography, medical imaging, neurovascular, vessel extraction

Cemil Kirbas; Francis Quek

2004-06-01T23:59:59.000Z

65

BWRVIP-267: BWR Vessel and Internals Project, BWRVIP Inspection Trends, 2012 Update  

Science Conference Proceedings (OSTI)

The BWR Vessel and Internals Project (BWRVIP) is an association of utilities focused exclusively on boiling water reactor (BWR) vessel and internals issues. As a group, the utilities have developed a set of guidelines that recommend inspecting specific BWR internal components. Results of these inspections are reported to the Electric Power Research Institute (EPRI) where they are compiled and made available to all member utilities. This report documents results of inspections performed between ...

2012-10-10T23:59:59.000Z

66

BWRVIP-167NP, Revision 2: BWR Vessel and Internals Project, Boiling Water Reactor Issue Management Tables  

Science Conference Proceedings (OSTI)

Nuclear utilities face numerous ongoing issues related to degradation of boiling water reactor (BWR) pressure vessels, reactor internals, and American Society of Mechanical Engineers (ASME) Class 1 piping components. These issues have resulted in the need for a summary tool to assist in prioritizing and addressing research and development (R&D) issues and BWR Vessel and Internals Project (BWRVIP) requirements. The BWR Issue Management Tables (IMTs) in the report are living documents that summarize the st...

2010-08-24T23:59:59.000Z

67

BWRVIP-167: BWR Vessel and Internals Project, Boiling Water Reactor Issue Management Tables  

Science Conference Proceedings (OSTI)

Ongoing issues related to degradation of boiling water reactor (BWR) pressure vessels, reactor internals, and American Society of Mechanical Engineers (ASME) Class 1 piping components have resulted in the need for a summary tool to assist in prioritizing and addressing research and development (R&D) issues. This BWR Vessel and Internals Project (BWRVIP) report provides BWR Issue Management Tables that identify, rank, and describe R&D gaps.

2007-03-20T23:59:59.000Z

68

Welding and Repair Technology Center: Repair Technology for Degraded Pressure Vessel and Heat Exchanger Shells  

Science Conference Proceedings (OSTI)

BackgroundPressure vessels and heat exchangers are subject to a number of degradation mechanisms that can cause thinning of component walls and deterioration of internal components. With many repair options available, the Electric Power Research Institute (EPRI) Welding and Repair Technology Center (WRTC) has developed this report to assist operations and engineering personnel who are faced with defective or failed vessel components. Many available repair options allow ...

2013-10-30T23:59:59.000Z

69

DEMO Hot Cell and Ex-Vessel Remote Handling  

E-Print Network (OSTI)

In Europe the work on the specification and design of a Demonstration Power Plant (DEMO) is being carried out by EFDA in the Power Plant Physics and Technology (PPP&T) programme. DEMO will take fusion from experimental research into showing the potential for commercial power generation. This paper describes the first steps being taken towards the design of the DEMO Hot Cell. It will show a comparison of the current DEMO in-vessel maintenance concepts from a Hot Cell perspective, describe a proposed ex-vessel transport system, and summarize the facilities that have been identified as required within the Hot Cell, examine current RH technology and discuss the identified critical development issues.

Thomas, Justin; Bachmann, Christian; Harman, Jon

2013-01-01T23:59:59.000Z

70

Lightweight bladder lined pressure vessels  

DOE Patents (OSTI)

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.

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

1998-08-25T23:59:59.000Z

71

Lightweight bladder lined pressure vessels  

DOE Patents (OSTI)

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.

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

1998-01-01T23:59:59.000Z

72

Reactor vessel using metal oxide ceramic membranes  

DOE Patents (OSTI)

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.

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

1992-08-11T23:59:59.000Z

73

HFIR In-Vessel Irradiation Facilities | ORNL Neutron Sciences  

NLE Websites -- All DOE Office Websites (Extended Search)

Home Facilities HFIR In-Vessel Irradiation In-Vessel Irradiation Experiment Facilities The HFIR provides a variety of in-core irradiation facilities, allowing for a...

74

Analysis of Crack Development Involving a Pressure Vessel in a ...  

Science Conference Proceedings (OSTI)

The vessel is part of a by-product refining system comprising a synthetic natural gas production plant. The vessel processes a mixture of chemical species,...

75

Future characteristics of Offshore Support Vessels  

E-Print Network (OSTI)

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 ...

Rose, Robin Sebastian Koske

2011-01-01T23:59:59.000Z

76

Resistance upset welding for vessel fabrication  

SciTech Connect

Solid-state resistance upset welding has been successfully applied to fabrication of small vessels. The process has advantages compared with the fusion welding processes currently used to join the two halves of such vessels. These advantages result from the improved metallurgical properties of the weld zone and the simplicity of the welding process. Spherical and cylindrical shapes have been fabricated using the upset welding process. Nondestructive and destructive tests have shown excellent weld strength. Storage tests have demonstrated long term compatibility of the welds for cylindrical parts made from 304L stainless steel that have been in storage for eight years. Spherical vessels and reinforced desip vessels made from forged 21-6-9 stainless steel have been prepared for storage.

Kanne, W.R. Jr.

1992-01-01T23:59:59.000Z

77

Resistance upset welding for vessel fabrication  

SciTech Connect

Solid-state resistance upset welding has been successfully applied to fabrication of small vessels. The process has advantages compared with the fusion welding processes currently used to join the two halves of such vessels. These advantages result from the improved metallurgical properties of the weld zone and the simplicity of the welding process. Spherical and cylindrical shapes have been fabricated using the upset welding process. Nondestructive and destructive tests have shown excellent weld strength. Storage tests have demonstrated long term compatibility of the welds for cylindrical parts made from 304L stainless steel that have been in storage for eight years. Spherical vessels and reinforced desip vessels made from forged 21-6-9 stainless steel have been prepared for storage.

Kanne, W.R. Jr.

1992-10-01T23:59:59.000Z

78

Final Vitrification Melter And Vessels Evaluation Documentation  

Energy.gov (U.S. Department of Energy (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...

79

Vessel Sanitation Program 2011 Operations Manual  

E-Print Network (OSTI)

and Prevention (CDC) established the Vessel Sanitation Program (VSP) in the 1970s as a cooperative activity............................................................................................ 1 1.1.1 Cooperative Activity.......................................................................................................... 1 1.2 Activities

80

Ion transport membrane module and vessel system  

DOE Patents (OSTI)

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.

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)

2012-02-14T23:59:59.000Z

Note: This page contains sample records for the topic "research vessel mirai" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

Ion transport membrane module and vessel system  

DOE Patents (OSTI)

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.

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)

2008-02-26T23:59:59.000Z

82

Decommissioning: Reactor Pressure Vessel Internals Segmentation  

Science Conference Proceedings (OSTI)

Decommissioning a nuclear plant covers a wide variety of challenging projects. One of the most challenging areas is the removal and disposal of the reactor pressure vessel (RPV) and the RPV internals. This report describes commercial reactor pressure vessel segmentation projects that have been completed and discusses several projects that are still in the planning stages. The report also covers lessons learned from each project.

2001-10-11T23:59:59.000Z

83

Draft report: application of organic Rankine cycle heat recovery systems to diesel powered marine vessels  

DOE Green Energy (OSTI)

The analysis and results of an investigation of the application of organic Rankine cycle heat recovery systems to diesel-powered marine vessels are described. The program under which this study was conducted was sponsored jointly by the US Energy Research and Development Administration, the US Navy, and the US Maritime Administration. The overall objective of this study was to investigate diesel bottoming energy recovery systems, currently under development by three US concerns, to determine the potential for application to marine diesel propulsion and auxiliary systems. The study primarily focused on identifying the most promising vessel applications (considering vessel type, size, population density, operational duty cycle, etc.) so the relative economic and fuel conservation merits of energy recovery systems could be determined and assessed. Vessels in the current fleet and the projected 1985 fleet rated at 1000 BHP class and above were investigated.

Not Available

1977-07-15T23:59:59.000Z

84

Test of 6-inch-thick pressure vessels. Series 1: intermediate test vessels V-1 and V-2  

SciTech Connect

The intermediate vessel tests have been subdivided into four seriesi flaws in cylindrical vessels, A508, class 2 forging steel-two vessels; flaws in cylindrical vessels with longitudinal weld seams, A508, class 2 forging steel, submerged-arc welds-three vessels; flaws in cylindrical vessels wlth longitudinal weld seams, A533, grade B, class l plate steel, submerged-arc weld-two vessels; and cylindrical vessels with radially attached nozzles, vessels of A508, chass 2 forging steel and A533, grade B, class 1 plate steel; nozzle of A508 class 2 forging steel-three vessels. A comprehensive description of the pertinent factors considered in the design of the vessels is presented. Construction of the test facility and documentation of test results and fracture predictions are included. Emphasis is placed on providing the test results in such a manner that they form a resource for amy investigators interested in the problem of fracture. (auth)

Derby, R.W.; Merkle, J.G.; Robinson, G.C.; Whitman, G.D.; Witt, F.J.

1974-02-01T23:59:59.000Z

85

EDS V25 containment vessel explosive qualification test report.  

SciTech Connect

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.

Rudolphi, John Joseph

2012-04-01T23:59:59.000Z

86

Reactor pressure vessel with forged nozzles  

DOE Patents (OSTI)

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.

Desai, Dilip R. (Fremont, CA)

1993-01-01T23:59:59.000Z

87

MAAP5 BWR Vessel Penetration and Ex-Vessel Equipment Model Enhancement Description  

Science Conference Proceedings (OSTI)

This report describes proposed enhancements to the Modular Accident Analysis Program (MAAP) vessel penetration and ex-vessel equipment model for BWR designs. MAAP is anEPRI-owned and -licensed computer program that simulates the operation of light water and heavy water moderated nuclear power plants for both current and advanced light water reactor (ALWR) designs.The report explores the manner in which the in-core instrument tubes would respond during severe core damage events that ...

2013-02-25T23:59:59.000Z

88

Melting Layer Cloud Observed during R/V Mirai Cruise MR01-K05  

Science Conference Proceedings (OSTI)

In this study, cloud profiling radar and lidar were used to determine the frequency distribution of the base heights of cloudy layers with little (or no) falling condensate particles. The data were obtained from stationary observations conducted ...

Kazuaki Yasunaga; Kunio Yoneyama; Hisayuki Kubota; Hajime Okamoto; Atsushi Shimizu; Hiroshi Kumagai; Masaki Katsumata; Nobuo Sugimoto; Ichiro Matsui

2006-11-01T23:59:59.000Z

89

On the interactive 3D reconstruction of Iberian vessels  

Science Conference Proceedings (OSTI)

Reconstructing vessels from sherds is a complex task, specially for hand made pottery. That is the case of the Iberian vessels. The reconstruction process can be done in three steps: orientation of the sherd, computing the symmetry axis and detecting ...

F. J. Melero; J. C. Torres; A. Len

2003-11-01T23:59:59.000Z

90

Operating an Acoustic Doppler Current Profiler aboard a Container Vessel  

Science Conference Proceedings (OSTI)

Since October 1992 an acoustic Doppler current profiler (ADCP) has been in near-continuous operation on board a 118-m-long container vessel, the container motor vessel Oleander, which operates on a weekly schedule between Port Elizabeth, New ...

C. N. Flagg; G. Schwartze; E. Gottlieb; T. Rossby

1998-02-01T23:59:59.000Z

91

Responses of wintering humpback whales to vessel traffic  

Science Conference Proceedings (OSTI)

Responses of humpback whales to vessel traffic were monitored over two winter seasons during 19831984 in Maui

Gordon B. Bauer; Joseph R. Mobley; Louis M. Herman

1993-01-01T23:59:59.000Z

92

Conceptual design of an in-vessel core catcher  

Science Conference Proceedings (OSTI)

An enhanced in-vessel core catcher is being designed and evaluated as part of a joint United States (US)Korean International Nuclear Energy Research Initiative (INERI) investigating methods to insure retention of materials that may relocate to the lower head of a reactor vessel under severe accident conditions in advanced reactors. This enhanced core catcher design consists of several interlocking sections that are machined to fit together when inserted into the lower head. Each section of the core catcher consists of two material layers with an option to add a third layer (if deemed necessary): a base material, which has the capability to support and contain the mass of core materials that may relocate during a severe accident; an insulator coating material on top of the base material, which resists interactions with high-temperature core materials; and an optional coating on the bottom side of the base material to prevent any potential oxidation of the base material during the lifetime of the reactor. This paper summarizes results from thermal, flow, and structural analyses as well as initial scoping materials interaction tests that were completed to support the conceptual design of the core catcher.

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

2004-05-01T23:59:59.000Z

93

Progress in understanding the mechanical behavior of pressure-vessel materials at elevated temperatures  

SciTech Connect

Progress during the 1970's on the production of high-temperature mechanical properties data for pressure vessel materials was reviewed. The direction of the research was toward satisfying new data requirements to implement advances in high-temperature inelastic design methods. To meet these needs, servo-controlled testing machines and high-resolution extensometry were developed to gain more information on the essential behavioral features of high-temperature alloys. The similarities and differences in the mechanical response of various pressure vessel materials were identified. High-temperature pressure vessel materials that have received the most attention included Type 304 stainless steel, Type 316 stainless steel, 2 1/4 Cr-1 Mo steel, alloy 800H, and Hastelloy X.

Swindeman, R.W.; Brinkman, C.R.

1981-01-01T23:59:59.000Z

94

In-Vessel Coil Material Failure Rate Estimates for ITER Design Use  

SciTech Connect

The ITER international project design teams are working to produce an engineering design for construction of this large tokamak fusion experiment. One of the design issues is ensuring proper control of the fusion plasma. In-vessel magnet coils may be needed for plasma control, especially the control of edge localized modes (ELMs) and plasma vertical stabilization (VS). These coils will be lifetime components that reside inside the ITER vacuum vessel behind the blanket modules. As such, their reliability is an important design issue since access will be time consuming if any type of repair were necessary. The following chapters give the research results and estimates of failure rates for the coil conductor and jacket materials to be used for the in-vessel coils. Copper and CuCrZr conductors, and stainless steel and Inconel jackets are examined.

L. C. Cadwallader

2013-01-01T23:59:59.000Z

95

Blood vessel segmentation methodologies in retinal images - A survey  

Science Conference Proceedings (OSTI)

Retinal vessel segmentation algorithms are a fundamental component of automatic retinal disease screening systems. This work examines the blood vessel segmentation methodologies in two dimensional retinal images acquired from a fundus camera and a survey ... Keywords: Blood vessel segmentation, Image segmentation, Medical imaging, Retinal images, Retinopathy, Survey

M. M. Fraz; P. Remagnino; A. Hoppe; B. Uyyanonvara; A. R. Rudnicka; C. G. Owen; S. A. Barman

2012-10-01T23:59:59.000Z

96

Photoacoustic removal of occlusions from blood vessels  

DOE Patents (OSTI)

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.

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)

2002-01-01T23:59:59.000Z

97

Investigation of impulsively loaded pressure vessels  

SciTech Connect

Explosion containment vessels for containing from 2,000 to 3,000 five ton nuclear explosions are considered. Analysis methods appear adequate and lowest weights using the most advanced materials available in the next five years are projected.None of these materials can be fabricated today and all require extensive development. Present material technology limits the choice of materials and defines the weight. The addition of safety factors and fixtures (nozzles, etc.) will add to this weight considerably, and may well radically alter the vessel response. Improvements in the strength weight ratios of metals and glasses over those considered in this report do not appear reasonable at this time. Winding schemes to utilize the high strength of steel wires and somehow maintain a reasonable thickness appear to offer the most promise. A `ductile` beryllium would of course offer vast improvement, but no indications that this is being developed have appeared and all presently known beryllium is much too brittle.

Brown, N.; Cornwell, R.; Hanner, D.; Leichter, H.; Mohr, P.

1963-10-15T23:59:59.000Z

98

Nuclear reactor pressure vessel support system  

DOE Patents (OSTI)

A support system for nuclear reactor pressure vessels which can withstand all possible combinations of stresses caused by a postulated core disrupting accident during reactor operation. The nuclear reactor pressure vessel is provided with a flange around the upper periphery thereof, and the flange includes an annular vertical extension formed integral therewith. A support ring is positioned atop of the support ledge and the flange vertical extension, and is bolted to both members. The plug riser is secured to the flange vertical extension and to the top of a radially outwardly extension of the rotatable plug. This system eliminates one joint through which fluids contained in the vessel could escape by making the fluid flow path through the joint between the flange and the support ring follow the same path through which fluid could escape through the plug risers. In this manner, the sealing means to prohibit the escape of contained fluids through the plug risers can also prohibit the escape of contained fluid through the securing joint.

Sepelak, George R. (McMurray, PA)

1978-01-01T23:59:59.000Z

99

Reactor Vessel Internals Inspection and Reactor Pressure Vessel Surveillance Program Summaries for R.E. Ginna and Nine Mile Point Unit 1  

Science Conference Proceedings (OSTI)

This report provides a summary of project activities involving the reactor pressure vessel and internals for the nuclear power plants included in the joint Electric Power Research Institute (EPRI), Department of Energy (DOE), and Constellation Energy Nuclear Group (CENG) Nuclear Plant Life Extension demonstration project.BackgroundThe project focused on continuing operations at two CENG nuclear units that are currently operating in their extended license ...

2013-12-18T23:59:59.000Z

100

Vehicular Storage of Hydrogen in Insulated Pressure Vessels  

DOE Green Energy (OSTI)

This paper describes the development of an alternative technology for storing hydrogen fuel onboard automobiles. Insulated pressure vessels are cryogenic-capable pressure vessels that can accept cryogenic liquid fuel, cryogenic compressed gas or compressed gas at ambient temperature. Insulated pressure vessels offer advantages over conventional H{sub 2} storage approaches. Insulated pressure vessels are more compact and require less carbon fiber than GH{sub 2} vessels. They have lower evaporative losses than LH{sub 2} tanks, and are much lighter than metal hydrides. After outlining the advantages of hydrogen fuel and insulated pressure vessels, the paper describes the experimental and analytical work conducted to verify that insulated pressure vessels can be used safely for vehicular H{sub 2} storage. The paper describes tests that have been conducted to evaluate the safety of insulated pressure vessels. Insulated pressure vessels have successfully completed a series of DOT, ISO and SAE certification tests. A draft procedure for insulated pressure vessel certification has been generated to assist in a future commercialization of this technology. An insulated pressure vessel has been installed in a hydrogen fueled truck and it is currently being subjected to extensive testing.

Aceves, S M; Berry, G D; Martinez-Frias, J; Espinosa-Loza, F

2005-01-03T23:59:59.000Z

Note: This page contains sample records for the topic "research vessel mirai" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

Confinement Vessel Assay System: Calibration and Certification Report  

SciTech Connect

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.

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

2012-07-17T23:59:59.000Z

102

20080310arm2008_norfolk_pos.ppt  

NLE Websites -- All DOE Office Websites (Extended Search)

Introduction: Introduction: An active remote-sensing using radar and/or lidar can provide the vertical structure of cloud properties. Okamoto et al. [2007] showed the vertical cloud structure over the Pacific Ocean near Japan using radar and lidar on the Research Vessel Mirai during MR01/K02 cruise (May 2001). This study reports the substitute result by a nest-grid simulation using a three dimensional non-hydrostatic model with a spectral bin microphysics for clouds. Model Description: A numerical model for atmospheric dynamics used in this study is based on a multi-purpose non-hydrostatic atmospheric model developed by the Japan Meteorological Agency (JMA-NHM) [Saito et al., 2006]. We replaced the original bulk-type cloud microphysical scheme with a bin-type

103

NEWASH AND TECUMSETH: ANALYSIS OF TWO POST-WAR OF 1812 VESSELS ON THE GREAT LAKES  

E-Print Network (OSTI)

In 1953 the tangled, skeletal remains of a ship were pulled from the small harbor of Penetanguishene, Ontario. Local historians had hoped to raise the hull of a War of 1812 veteran, but the vessel pulled from the depths did not meet the criteria. Identified as H.M. Schooner Tecumseth, the vessel was built just after the War of 1812 had ended. Historical research of Tecumseth and her sister ship Newash, which remained in Penetanguishene harbor, illuminated the ships? shadowy past. Conceived and built after the war, the vessels sailed for only two years before being rendered obsolete by the terms of the Rush-Bagot disarmament agreement. Nevertheless, the two vessels offer a unique perspective from which to view the post-war period on the Great Lakes. The schooners? hulls were interpreted and analyzed using archaeological evidence. A theoretical rigging reconstruction was created, using contemporary texts and documentary evidence of the ships themselves. Architectural hull analysis was carried out to explore the nature of these vessels. From these varied approaches, a conception of Newash and Tecumseth has emerged, revealing ways in which the hulls were designed to fulfill their specific duties. The hulls were sharp, yet had capacious cargo areas. The rigs combined square-rigged and fore-and-aft sails for maximum flexibility. The designs of the hulls and rigging also reflect predominant attitudes of the period, in which naval vessels on the lakes gave way to merchant craft. Taken as a whole, Tecumseth and Newash illustrate how ships, while fluid in the nature of their work, are also singular entities that truly encapsulate a specific point in time and place.

Gordon, Leeanne E.

2009-05-01T23:59:59.000Z

104

Annabella: a North American coasting vessel  

E-Print Network (OSTI)

The coasting schooner Annabella was built at Port Elizabeth, New Jersey, in 1834. Originally constructed as a sloop, the vessel was built specifically for transporting raw materials such as cordwood, brick, coal, and perishables to markets and industries along the northeast United States coast. During its lengthy 50-year career, ownership of Annabella was transferred among numerous merchants in Philadelphia, Plymouth, Boston, and, finally, Cape Neddick, Maine. The vessel was finally abandoned on October 17, 1885, in the Cape Neddick River, in Cape Neddick, Maine, beyond repair and no longer fit for service. This study covers the following topics: the 1994 and 1995 archaeological field seasons, including hull and artifact descriptions and analyses; the history of the coasting trade and the cordwood industry during the 19th century in the vicinity of southern Maine; and an analysis of historical documents that detail the history ofannabella. Toward these ends, this thesis will present a description and analysis of a type of craft that once was common to the eastern seaboard, including discussions about how the craft was designed and built for transporting specific cargoes, and how this ship may be representative of maritime activities and shipbuilding technologies of the 19th century

Claesson, Stefan Hans

1998-01-01T23:59:59.000Z

105

Engineering Test Reactor (ETR) Vessel Relocated after 50 years.  

NLE Websites -- All DOE Office Websites (Extended Search)

Printer Friendly Printer Friendly Engineering Test Reactor (ETR) Vessel Relocated Engineering Test Reactor Vessel Pre-startup 1957 Click on image to enlarge. Image 1 of 5 Gantry jacks attached to ETR vessel. Initial lift starts. - Click on image to enlarge. Image 2 of 5 ETR vessel removed from substructure. Vessel lifted approximately 40 ft. - Click on image to enlarge. On Monday, September 24, 2007 the Engineering Test Reactor (ETR) vessel was removed from its location and delivered to the Idaho CERCLA Disposal Facility (ICDF). The long history of the ETR began for this water-cooled reactor with its start up in 1957, after taking only 2 years to build. According to "Proving the Principles," by Susan M. Stacy: When the Engineering Test Reactor started up at the Test Reactor Area in

106

International Hydrogen Fuel and Pressure Vessel Forum 2010 Proceedings  

NLE Websites -- All DOE Office Websites (Extended Search)

challenges in harmonizing test protocols and requirements for compressed natural gas (CNG), hydrogen, and CNG-hydrogen (HCNG) blend pressure vessels and to define next steps for...

107

Damage analysis of composite pressure vessels using acoustic emission monitoring.  

E-Print Network (OSTI)

??Composite pressure vessels (CPVs) fabricated using a metal or plastic liner under a composite structural skin are commonly used for natural gas storage on road (more)

Chou, H

2012-01-01T23:59:59.000Z

108

Reactor Pressure Vessel Task of Light Water Reactor Sustainability...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Milestone Report on Materials and Machining of Specimens for the ATR-2 Experiment Reactor Pressure...

109

Retinal vessel segmentation using multiwavelet kernels and multiscale hierarchical decomposition  

Science Conference Proceedings (OSTI)

We propose a comprehensive method for segmenting the retinal vasculature in fundus camera images. Our method does not require preprocessing and training and can therefore be used directly on different images sets. We enhance the vessels using matched ... Keywords: Matched filter, Multiscale hierarchical decomposition, Multiwavelet, Retinal images, Segmentation, Vessel detection

Yangfan Wang; Guangrong Ji; Ping Lin; Emanuele Trucco

2013-08-01T23:59:59.000Z

110

Nuclear reactor construction with bottom supported reactor vessel  

DOE Patents (OSTI)

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.

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

1987-01-01T23:59:59.000Z

111

A re-assembly and reconstruction of the 9th-century AD vessel wrecked off the coast of Bozburun, Turkey  

E-Print Network (OSTI)

In 1973, researchers from the Institute of Nautical Archaeology (INA) were led to the site of a wrecked ship by sponge diver Mehmet A??k??n, near his hometown of Bozburun, Turkey. During further monitoring over the following 21 years by INA, the site was identified as a merchant vessel dating from the 9th century AD. The excavation of the site by INA researchers and students from Texas A&M University occurred over four summer seasons, from 1995 to 1998, and yielded approximately 900 whole or nearly-whole amphorae, personal items, palynological material, and approximately 35 percent of the vessel??s wooden hull. This dissertation is a record of the curation, cataloging, analysis and re-assembly of the preserved elements of the Bozburun vessel??s hull, as well as a theoretical reconstruction of the entire vessel. The Bozburun vessel is unique as it is the only fully-excavated shipwreck from the 9th century AD, and is, indeed, a valuable source of examples of ship construction in the Mediterranean between the 7th and the 11th centuries AD. This dissertation, after discussing the methods of excavation and cataloging methods, posits the hypothesis that the techniques used to build this vessel represent a transitional stage in shipbuilding technology, combining distinctly old and new techniques. While the builders used embedded edge joinery in the ship??s planking, a very old method, they also appear to have used a conceptual framework and standards to design the vessel as well; methods evident in modified forms in Italian shipbuilding treatises from the Renaissance.

Harpster, Matthew Benjamin

2005-08-01T23:59:59.000Z

112

Interim Report: Coiled Tubing Drilling and Intervention System Using Cost Effective Vessel  

NLE Websites -- All DOE Office Websites (Extended Search)

DOCUMENT TITLE: DOCUMENT TITLE: Self Supporting Riser Technology to Enable Coiled Tubing Intervention for Deepwater Wells Document No.: 08121-1502-12 RPSEA PROJECT TITLE: Coil Tubing Drilling and Intervention System Using a Cost Effective Vessel RPSEA Project No.: 08121-1502 01 April 2011 Charles R. Yemington, PE Project Manager Nautilus International 400 North Sam Houston Parkway East, Suite 105 Houston, Texas 77060 RPSEA Project No.: 08121-1502 Coiled Tubing Drilling and Intervention System Using a Cost Effective Vessel RPSEA Project 08121-1502 01 April 2011 Page 2 of 91 LEGAL NOTICE This report was prepared by Nautilus International, LLC. as an account of work sponsored by the Research Partnership to Secure Energy for America (RPSEA). RPSEA members, the

113

Welding the AT-400A Containment Vessel  

SciTech Connect

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.

Brandon, E.

1998-11-01T23:59:59.000Z

114

Welding the AT-400A Containment Vessel  

SciTech Connect

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.

Brandon, E.

1998-11-01T23:59:59.000Z

115

Confinement Vessel Assay System: Design and Implementation Report  

SciTech Connect

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.

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

2012-07-18T23:59:59.000Z

116

Thermal Expansion Coefficient of Steels Used in LWR Vessels  

Science Conference Proceedings (OSTI)

Because of the impact that melt relocation and vessel failure have on subsequent progression and associated consequences of a Light Water Reactor (LWR) accident, it is important to accurately predict the heat-up and relocation of materials within the reactor vessel and heat transfer to and from the reactor vessel. Accurate predictions of such heat transfer phenomena require high temperature thermal properties. However, a review of vessel and structural steel material properties in severe accident analysis codes reveals that the required high temperature material properties are extrapolated with little, if any, data above 700C. To reduce uncertainties in predictions relying upon this extrapolated high temperature data, new thermal expansion data were obtained using pushrod dilatometry techniques for two metals used in LWR vessels: SA 533 Grade B, Class 1 (SA533B1) low alloy steel, which is used to fabricate most US LWR reactor vessels; and Type 304 Stainless Steel (SS304), which is used in LWR vessel piping, penetration tubes, and internal structures. This paper summarizes the new data and compares it to existing, lower temperature data in the literature.

Joshua E. Daw; Joy L. Rempe; Darrell L. Knudson; John C. Crepeau

2008-05-01T23:59:59.000Z

117

High temperature thermal properties for metals used in LWR vessels  

Science Conference Proceedings (OSTI)

Because of the impact that melt relocation and vessel failure has on subsequent progression and associated consequences of an Light Water Reactor (LWR) accident, it is important to accurately predict the heatup and relocation of materials within the reactor vessel and heat transfer to and from the reactor vessel. Accurate predictions of such heat transfer phenomena require high temperature thermal properties. However, a review of vessel and structural steel material properties in severe accident analysis codes reveals that the required high temperature material properties are extrapolated, with little if any, data above 700 C. To reduce uncertainties in predictions relying upon this extrapolated high temperature data, INL obtained data using laser-flash thermal diffusivity techniques for two metals used in LWR vessels: SA533B1 carbon steel, which is used to fabricate most US LWR reactor vessels; and SS304, which is used in LWR vessel piping, penetration tubes, and internal structures. This paper summarizes the new data, compares it to existing data in the literature, and provides recommended correlations for thermal properties based on this data.

Joy L. Rempe

2008-01-01T23:59:59.000Z

118

Start-up control system and vessel for LMFBR  

DOE Patents (OSTI)

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.

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

1987-01-01T23:59:59.000Z

119

Start-up control system and vessel for LMFBR  

DOE Patents (OSTI)

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.

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

1987-01-01T23:59:59.000Z

120

Pressure vessel reliability as a function of allowable stress  

SciTech Connect

From Winter meeting of American Society of Mechanical Engineers; Detroit, Michigan, USA (11 Nov 1973). The probability of failure corresponding to specified levels of allowable design stress was calculated for pressure vessels designed in accordance with the ASME Boiler and Pressure Vessel Code. The analysis was performed for maximum shear stress failure and for cyclic stress failure. The significance of such failure prediction is ddscussed and a rationale for selecting an allowable stress is presented. Examples are presented that demonstrate the estimation of vessel failure probability as a function of load variation, strength variation, and design safety factor. (auth)

Arnold, H.G.

1972-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "research vessel mirai" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

Float level switch for a nuclear power plant containment vessel  

DOE Patents (OSTI)

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.

Powell, J.G.

1993-11-16T23:59:59.000Z

122

Float level switch for a nuclear power plant containment vessel  

DOE Patents (OSTI)

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.

Powell, James G. (Clifton Park, NY)

1993-01-01T23:59:59.000Z

123

Experiment Hazard Class 5.3 High Pressure Vessels  

NLE Websites -- All DOE Office Websites (Extended Search)

3 High Pressure Vessels 3 High Pressure Vessels Applicability This hazard classification applies to working with pressure vessels and systems. Other hazard classifications and associated controls may apply to experiments in this hazard class. Experiment Category Experiments involving previously reviewed hazard controls are catergorized as medium risk experiments. Experiments involving new equipment, processes or materials, or modified hazard control schemes are categorized as high risk experiments. Hazard Control Plan Verification Statements Engineered Controls - The establishment of applicable controls in accordance with the (American Society of Mechanical Engineers) ASME Boiler and Pressure Code, ASME B.31 Piping Code and applicable federal, state, and local codes. Verify vessel is stampled with ASME Code Symbol or allowable

124

Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program:  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Reactor Pressure Vessel Task of Light Water Reactor Sustainability Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Initial Assessment of Thermal Annealing Needs and Challenges Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Initial Assessment of Thermal Annealing Needs and Challenges The most life-limiting structural component in light-water reactors (LWR) is the reactor pressure vessel (RPV) because replacement of the RPV is not considered a viable option at this time. LWR licenses are now being extended from 40y to 60y by the U.S. Nuclear Regulatory Commission (NRC) with intentions to extend licenses to 80y and beyond. The RPV materials exhibit varying degrees of sensitivity to irradiation-induced embrittlement (decreased toughness) , as shown in Fig. 1.1, and extending operation from

125

Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program:  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Reactor Pressure Vessel Task of Light Water Reactor Sustainability Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Milestone Report on Materials and Machining of Specimens for the ATR-2 Experiment Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Milestone Report on Materials and Machining of Specimens for the ATR-2 Experiment The reactor pressure vessel (RPV) in a light-water reactor (LWR) represents the first line of defense against a release of radiation in case of an accident. Thus, regulations, which govern the operation of commercial nuclear power plants, require conservative margins of fracture toughness, both during normal operation and under accident scenarios. In the unirradiated condition, the RPV has sufficient fracture toughness such that failure is implausible under any postulated condition, including

126

Analysis of the Catastrophic Rupture of a Pressure Vessel  

E-Print Network (OSTI)

occurred at a petroleum refinery in Chicago, killing 17 people and causing extensive property damage [1]. NBS was requested by the Occupational Safety and Health Administration (OSHA) to conduct an investigation into the failure of the pressure vessel that eyewitnesses identified as the initial source of the explosion and fire. This vessel was an amine absorber tower used to strip hydrogen sulfide from a process stream of propane and butane. The vessel was 18.8 m tall, 2.6 m in diameter, and constructed from 25 mm thick plates of type ASTM A516 Grade 70 steel. The investigation was complicated by the damage caused by the explosion and fire. The explosive force had been sufficient to propel the upper 14 m of the vessel a distance of 1 km from its original location,

unknown authors

1984-01-01T23:59:59.000Z

127

Experimental investigation of creep behavior of reactor vessel lower head  

SciTech Connect

The objective of the USNRC supported Lower Head Failure (LHF) Experiment Program at Sandia National Laboratories is to experimentally investigate and characterize the failure of the reactor pressure vessel (RPV) lower head due to the thermal and pressure loads of a severe accident. The experimental program is complemented by a modeling program focused on the development of a constitutive formulation for use in standard finite element structure mechanics codes. The problem is of importance because: lower head failure defines the initial conditions of all ex-vessel events; the inability of state-of-the-art models to simulate the result of the TMI-II accident (Stickler, et al. 1993); and TMI-II results suggest the possibility of in-vessel cooling, and creep deformation may be a precursor to water ingression leading to in-vessel cooling.

Chu, T.Y.; Pilch, M.; Bentz, J.H. [Sandia National Labs., Albuquerque, NM (United States); Behbahani, A. [NRC, Washington, DC (United States)

1998-03-01T23:59:59.000Z

128

Prediction of Vessel Icing for Near-Freezing Sea Temperatures  

Science Conference Proceedings (OSTI)

The operational NOAA categorical vessel icing algorithm is evaluated with regard to advances in understanding of the icing process and forecasting experience. When sea temperatures are <23C above the saltwater freezing point there is the ...

James E. Overland

1990-03-01T23:59:59.000Z

129

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

Science Conference Proceedings (OSTI)

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

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

2006-06-06T23:59:59.000Z

130

Using SA508/533 for the HTGR Vessel Material  

SciTech Connect

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.

Larry Demick

2012-06-01T23:59:59.000Z

131

Feasibility of underwater welding of highly irradiated in-vessel components of boiling-water reactors: A literature review  

SciTech Connect

In February 1997, the U.S. Nuclear Regulatory Commission (NRC), Office of Nuclear Regulatory Research (RES), initiated a literature review to assess the state of underwater welding technology. In particular, the objective of this literature review was to evaluate the viability of underwater welding in-vessel components of boiling water reactor (BWR) in-vessel components, especially those components fabricated from stainless steels that are subjected to high neutron fluences. This assessment was requested because of the recent increased level of activity in the commercial nuclear industry to address generic issues concerning the reactor vessel and internals, especially those issues related to repair options. This literature review revealed a preponderance of general information about underwater welding technology, as a result of the active research in this field sponsored by the U.S. Navy and offshore oil and gas industry concerns. However, the literature search yielded only a limited amount of information about underwater welding of components in low-fluence areas of BWR in-vessel environments, and no information at all concerning underwater welding experiences in high-fluence environments. Research reported by the staff of the U.S. Department of Energy (DOE) Savannah River Site and researchers from the DOE fusion reactor program proved more fruitful. This research documented relevant experience concerning welding of stainless steel materials in air environments exposed to high neutron fluences. It also addressed problems with welding highly irradiated materials, and primarily attributed those problems to helium-induced cracking in the material. (Helium is produced from the neutron irradiation of boron, an impurity, and nickel.) The researchers found that the amount of helium-induced cracking could be controlled, or even eliminated, by reducing the heat input into the weld and applying a compressive stress perpendicular to the weld path.

Lund, A.L.

1997-11-01T23:59:59.000Z

132

Simulant Melt Experiments on Performance of the In-Vessel Core Catcher  

SciTech Connect

In order to enhance the feasibility of in-vessel retention (IVR) of molten core material during a severe accident for high-power reactors, an in-vessel core catcher (IVCC) was designed and evaluated as part of a joint United States-Korean International Nuclear Energy Research Initiative (INERI). The proposed IVCC is expected to increase the thermal margin for success of IVR by providing an engineered gap for heat transfer from materials that relocate during a severe accident and potentially serving as a sacrificial material under a severe accident. In this study, LAVA-GAP experiments were performed to investigate the thermal and mechanical performance of the IVCC using the alumina melt as simulant. The LAVAGAP experiments aim to examine the feasibility and sustainability of the IVCC under the various test conditions using 1/8th scale hemispherical test sections. As a feasibility test of the proposed IVCC in this INERI project, the effects of IVCC base steel materials, internal coating materials, and gap size between the IVCC and the vessel lower head were examined. The test results indicated that the internally coated IVCC has high thermal performance compared with the uncoated IVCC. In terms of integrity of the base steel, carbon steel is superior to stainless steel and the effect of bond coat is found to be trivial for the tests performed in this study. The thermal load is mitigated via boiling heat removal in the gap between the IVCC and the vessel lower head. The current test results imply that gaps less than 10mm are not enough to guarantee effective cooling induced by water ingression and steam venting there through. Selection of endurable material and pertinent gap size is needed to implement the proposed IVCC concept into advanced reactor designs.

Kyoung-Ho Kang; Rae-Joon Park; Sang-Baik Kim; K. Y. Suh; F. B. Cheung; J. L. Rempe

2007-09-01T23:59:59.000Z

133

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

Science Conference Proceedings (OSTI)

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

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

2005-11-15T23:59:59.000Z

134

LNG Imports by Vessel into the U.S. Form | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Vessel into the U.S. Form LNG Imports by Vessel into the U.S. Form Excel Version of LNG Imports by Vessel into the U.S. Form.xlsx PDF Version of LNG Imports by Vessel into the U.S....

135

Elliptical Local Vessel Density: a Fast and Robust Quality Metric for Fundus Images  

SciTech Connect

A great effort of the research community is geared towards the creation of an automatic screening system able to promptly detect diabetic retinopathy with the use of fundus cameras. In addition, there are some documented approaches to the problem of automatically judging the image quality. We propose a new set of features independent of Field of View or resolution to describe the morphology of the patient's vessels. Our initial results suggest that they can be used to estimate the image quality in a time one order of magnitude shorter respect to previous techniques.

Giancardo, Luca [ORNL; Chaum, Edward [ORNL; Karnowski, Thomas Paul [ORNL; Meriaudeau, Fabrice [ORNL; Tobin Jr, Kenneth William [ORNL; Abramoff, M.D. [University of Iowa

2008-01-01T23:59:59.000Z

136

Forum Agenda: International Hydrogen Fuel and Pressure Vessel Forum  

NLE Websites -- All DOE Office Websites (Extended Search)

FORUM AGENDA FORUM AGENDA U.S. Department of Energy and Tsinghua University International Hydrogen Fuel and Pressure Vessel Forum Tsinghua University Beijing, PRC September 27 - 29, 2010 The U.S. Department of Energy (DOE) and Tsinghua University in Beijing co-hosted the International Hydrogen Fuel and Pressure Vessel Forum on September 27 - 29, 2010 in Beijing, China. High pressure vessel experts gathered to share lessons learned from CNG and hydrogen vehicle deployments, and to identify R&D needs to aid the global harmonization of regulations, codes and standards to enable the successful deployment of hydrogen and fuel cell technologies. Forum Objectives: * Address and share data and information on specific technical topics discussed at the workshop in

137

Tritium permeation and wall loading in the TFTR vacuum vessel  

SciTech Connect

The problems of tritium permeation through and loading of the TFTR vacuum vessel wall structural components are considered. A general analytical solution to the time dependent diffusion equation which takes into account the boundary conditions arising from the tritium filling gas as well as the source function associated with implanted energetic charge exchange tritium is presented. Expressions are derived for two quantities of interest: (1) the total amount of tritium leaving the outer surface of a particular vessel component as a function of time, and (2) the amount retained as a function of time. These quantities are evaluated for specific TFTR operating scenarios and outgassing modes. The results are that permeation through the vessel is important only for the bellows during discharge cleaning if the wall temperature rises above approximately 150/sup 0/C. At 250/sup 0/C, after 72 hours of discharge cleaning 195 Ci would be lost.

Cecchi, J.L.

1978-05-01T23:59:59.000Z

138

Sterilization of fermentation vessels by ethanol/water mixtures  

DOE Patents (OSTI)

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

Wyman, C.E.

1991-03-20T23:59:59.000Z

139

The Westinghouse Electric Corporation Reactor Vessel Radiation Surveillance Program  

Science Conference Proceedings (OSTI)

Westinghouse recognized that the disruption of the atomic lattice of metals by collision from energetic neutrons could alter the properties of the metals to such an extent that the changes could be of engineering significance. Furthermore, it was recognized that a physical-metallurgical phenomenon such as aging, both thermal and mechanical, also could alter the properties of a metal over its service life. Because of the potential changes in properties, reactor vessel radiation surveillance programs to monitor the effect of neutron radiation and other environmental factors on the reactor vessel materials during operational conditions over the life of the plant were initiated for Westinghouse plants with the insertion of reactor vessel material radiation surveillance capsules into the Yankee Atomic Company's Yankee Rowe plant in 1961.

Mayer, T.R.; Anderson, S.L.; Yanichko, S.E.

1983-01-01T23:59:59.000Z

140

Sterilization of fermentation vessels by ethanol/water mixtures  

DOE Patents (OSTI)

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

Wyman, C.E.

1999-02-09T23:59:59.000Z

Note: This page contains sample records for the topic "research vessel mirai" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

Sterilization of fermentation vessels by ethanol/water mixtures  

DOE Patents (OSTI)

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

Wyman, Charles E. (Lakewood, CO)

1999-02-09T23:59:59.000Z

142

The Louisiana State Museum Vessel: a historical and archaeological analysis of an American Civil War-era submersible boat  

E-Print Network (OSTI)

During the spring of 1992, and again in the winter of 1993, seven graduate students from Texas A&M University's Nautical Archaeology Program participated in a project to document the Louisiana State Museum Vessel, an American Civil War-era submersible boat presently residing in the collections of the Louisiana State Museum in New Orleans. The project initially focused on providing archaeological documentation of the boat's design and construction characteristics, and on compiling some basic historical documentation regarding its known past. Since the turn of the century, this vessel has been presumed by many to be the New Orleans-built Confederate privateer Pioneer, which was scuttled at the time of the evacuation of New Orleans by Federal forces, and last reported in very close proximity to where the Louisiana State Museum Vessel was found in 1878. This was the assumption made at the time the documentation project was conducted, and based upon the information available at that time, an argument in support of this identification was published in a subsequent article summarizing the project's findings. Additional research has clearly determined that this vessel is not the Pioneer. Recent research also indicates that efforts to design, fabricate, and employ submersible vessels within the Confederate States were more widespread than conventionally believed. Furthermore, it now appears that the level of Confederate government support enjoyed by these efforts was more substantial than has traditionally been presumed. The Louisiana State Museum Vessel constitutes the oldest extant example of an important American watercraft tradition. The goals of this thesis are to historically and archaeologically document the Louisiana State Museum Vessel, and, as it cannot presently be identified, to establish likely historical candidates for potential association with it. In this process, the boat is used as a lens through which to view the larger picture of submersible watercraft development efforts undertaken within the Confederacy, and to discuss the collective body of antebellum American experiences and technical knowledge available to the Confederate submersible boat builders. It is also used as a vantage point from which to explore the relationship between Confederate and contemporaneous Federal submersible development efforts, and to acknowledge the common postwar legacy that emerged as a result of these parallel programs.

Wills, Richard Keith

2000-01-01T23:59:59.000Z

143

Initial Evaluation of the Heat-Affected Zone, Local Embrittlement Phenomenon as it Applies to Nuclear Reactor Vessels  

Science Conference Proceedings (OSTI)

The objective of this project was to determine if the local brittle zone (LBZ) problem, encountered in the testing of the heat-affected zone (HAZ) part of welds in offshore platform construction, can also be found in reactor pressure vessel (RPV) welds. Both structures have multipass welds and grain coarsening along the fusion line. Literature was obtained that described the metallurgical evidence and the type of research work performed on offshore structure welds.

McCabe, D.E.

1999-09-01T23:59:59.000Z

144

Fabrication of toroidal composite pressure vessels. Final report  

DOE Green Energy (OSTI)

A method for fabricating composite pressure vessels having toroidal geometry was evaluated. Eight units were fabricated using fibrous graphite material wrapped over a thin-walled aluminum liner. The material was wrapped using a machine designed for wrapping, the graphite material was impregnated with an epoxy resin that was subsequently thermally cured. The units were fabricated using various winding patterns. They were hydrostatically tested to determine their performance. The method of fabrication was demonstrated. However, the improvement in performance to weight ratio over that obtainable by an all metal vessel probably does not justify the extra cost of fabrication.

Dodge, W.G.; Escalona, A.

1996-11-24T23:59:59.000Z

145

DHCVIM: A direct heating containment vessel interactions module  

SciTech Connect

Models for prediction of direct containment heating phenomena as implemented in the DHCVIM computer module are described. The models were designed to treat thermal, chemical and hydrodynamic processes in the three regions of the Sandia National Laboratory Surtsey DCH test facility: the melt generator, cavity and vessel. The fundamental balance equations, along with constitutive relations are described. A combination of Eulerian treatment for the gas phase and Lagrangian treatment for the droplet phase is used in the modeling. Comparisons of calculations and DCH-1 test results are presented. Reasonable agreement is demonstrated for the vessel pressure rise, melt generator pressure decay and particle size distribution.

Ginsberg, T.; Tutu, N.K.

1987-01-01T23:59:59.000Z

146

Simulation of Diffusive Lithium Evaporation Onto the NSTX Vessel Walls  

Science Conference Proceedings (OSTI)

A model for simulating the diffusive evaporation of lithium into a helium filled NSTX vacuum vessel is described and validated against an initial set of deposition experiments. The DEGAS 2 based model consists of a three-dimensional representation of the vacuum vessel, the elastic scattering process, and a kinetic description of the evaporated atoms. Additional assumptions are required to account for deuterium out-gassing during the validation experiments. The model agrees with the data over a range of pressures to within the estimated uncertainties. Suggestions are made for more discriminating experiments that will lead to an improved model.

D.P. Stotler, C.H. Skinner, W.R. Blanchard, P.S. Krstic, H.W. Kugel, H. Schneider, and L.E. Zakharov

2010-12-09T23:59:59.000Z

147

BWRVIP-44-A: BWR Vessel and Internals Project: Underwater Weld Repair of Nickel Alloy Reactor Vessel Internals  

Science Conference Proceedings (OSTI)

The Boiling Water Reactor Vessel and Internals Project (BWRVIP), formed in June 1994, is an association of utilities focused exclusively on BWR vessel and internals issues. This report describes work performed to qualify a flux-core welding process for use in repairing reactor internals at a water depth of up to 50 feet. A previous version of this report was published as BWRVIP-44 (EPRI report TR-108708). The current report, BWRVIP-44-A, incorporates changes proposed by the BWRVIP in response to U.S. Nuc...

2006-08-16T23:59:59.000Z

148

Angiotensin II receptors in rabbit renal preglomerular vessels  

SciTech Connect

Controversy exists regarding the specific sites within the renal microcirculation affected by angiotensin II (ANG II). Under some conditions, ANG II can elicit direct vasoconstrictor responses in the preglomerular vessels and efferent arterioles. These experiments were designed to evaluate the binding of {sup 125}I-ANG II in preglomerular vessels. Arcuate and interlobular arteries, with attached proximal segments of afferent arterioles, were microdissected from rabbit renal cortexes. A membrane preparation was obtained from the pooled freshly dissected vessels and utilized in an ANG II radioreceptor assay on the same day. The dissociation of bound ANG II was enhanced in the presence of a nonhydrolyzable analogue of GTP. Linear Scatchard plots were obtained, indicating the presence of a single class of high-affinity binding sites. In conclusion, there is a single class of specific ANG II receptors in preglomerular vessels. The K{sub D} and N are similar, but the binding inhibition potencies of selected ANG analogues differ in renal and extrarenal vascular tissues. Intrarenal vascular receptors also appear to differ from glomerular receptors. Furthermore, these data support the concept that ANG II may affect renal vascular resistance at sites proximal to the distal afferent arterioles.

Brown, G.P.; Venuto, R.C. (State Univ. of New York, Buffalo (USA))

1988-07-01T23:59:59.000Z

149

Fillables: everyday vessels as tangible controllers with adjustable haptics  

Science Conference Proceedings (OSTI)

We introduce Fillables: low-cost and ubiquitous everyday vessels that are appropriated as tangible controllers whose haptics are tuned ad-hoc by filling, e.g., with water. We show how Fillables can assist users in video navigation and drawing tasks with ... Keywords: appropriation, everyday objects, tangible user interfaces, ubiquitous computing, up-and-down transformed response (udtr), weber's law

Christian Corsten; Chat Wacharamanotham; Jan Borchers

2013-04-01T23:59:59.000Z

150

FIRE Vacuum Vessel Cost estimate and R&D needs  

E-Print Network (OSTI)

for remote handling mockup to be used for demonstration of : - Transfer cask docking - Divertor handling - FW and will serve as mockup for remote handling facility #12; tile handling / alignment - Recovery operations - Etc. #12;6 June 2001 FIRE Review: Vacuum Vessel

151

AN IBM 7090 FORTRAN PROGRAM FOR ASME UNFIRED PRESSURE VESSEL DESIGN AND PRELIMINARY COST ESTIMATION  

SciTech Connect

An IBM 7090 FORTRAN program was written for the preliminary design and cost estimation of unfired pressure vessels with or without a jacket. Both vessel and jacket designs conform to the 1959 ASME Boiler and Pressure Vessel Code, Section VIII, Unfired Pressure Vessels. Vessels and jackets from 5 in. pipe through 84 in. o.d. and 1/4 in. through 1 1/2 in. in metal thickness may be designed by this program as written. Total vessel cost is the sum of metal and fabrication costs, each on a weight basis. (auth)

Prince, C.E.; Milford, R.P.

1962-10-17T23:59:59.000Z

152

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

DOE Patents (OSTI)

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.

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

2010-02-09T23:59:59.000Z

153

Application of small specimens to fracture mechanics characterization of irradiated pressure vessel steels  

SciTech Connect

In this study, precracked Charpy V-notch (PCVN) specimens were used to characterize the fracture toughness of unirradiated and irradiated reactor pressure vessel steels in the transition region by means of three-point static bending. Fracture toughness at cleavage instability was calculated in terms of elastic-plastic K{sub Jc} values. A statistical size correction based upon weakest-link theory was performed. The concept of a master curve was applied to analyze fracture toughness properties. Initially, size-corrected PCVN data from A 533 grade B steel, designated HSST Plate O2, were used to position the master curve and a 5% tolerance bound for K{sub Jc} data. By converting PCVN data to IT compact specimen equivalent K{sub Jc} data, the same master curve and 5% tolerance bound curve were plotted against the Electric Power Research Institute valid linear-elastic K{sub Jc} database and the ASME lower bound K{sub Ic} curve. Comparison shows that the master curve positioned by testing several PCVN specimens describes very well the massive fracture toughness database of large specimens. These results give strong support to the validity of K{sub Jc} with respect to K{sub Ic} in general and to the applicability of PCVN specimens to measure fracture toughness of reactor vessel steels in particular. Finally, irradiated PCVN specimens of other materials were tested, and the results are compared to compact specimen data. The current results show that PCVNs demonstrate very good capacity for fracture toughness characterization of reactor pressure vessel steels. It provides an opportunity for direct measurement of fracture toughness of irradiated materials by means of precracking and testing Charpy specimens from surveillance capsules. However, size limits based on constraint theory restrict the operational test temperature range for K{sub Jc} data from PCVN specimens. 13 refs., 8 figs., 1 tab.

Sokolov, M.A.; Wallin, K.; McCabe, D.E.

1996-12-31T23:59:59.000Z

154

TR-105696-R16 (BWRVIP-03) Revision 16: BWR Vessel and Internals Project, Reactor Pressure Vessel and Internals Examination Guidelines  

Science Conference Proceedings (OSTI)

This report provides the boiling water reactor (BWR) fleet with inspection options for all of the safety-related vessel internal components, and provides a stable mechanism for documenting the capability of the evolving inspection technology. It is the sole resource for internals inspection information for BWR ...

2013-12-14T23:59:59.000Z

155

LNG Exports by Vessel in ISO Containers out of the U.S. Form...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

in ISO Containers out of the U.S. Form LNG Exports by Vessel in ISO Containers out of the U.S. Form Excel Version of LNG Exports by Vessel in ISO Container out of the U.S....

156

Mechanical safety subcommittee guideline for design of thin windows for vacuum vessels  

SciTech Connect

This guideline specifies the usage of thin windows for vacuum vessels in terms of their design and application a Fermilab.

Western, J.L.

1993-03-01T23:59:59.000Z

157

Mechanical Safety Subcommittee guideline for design of thin windows for vacuum vessels  

SciTech Connect

This guideline specifies the usage of thin windows for vacuum vessels in terms of their design and application at Fermilab.

Western, J.L.

1991-03-06T23:59:59.000Z

158

Mechanical safety subcommittee guideline for design of thin windows for vacuum vessels. Revised  

SciTech Connect

This guideline specifies the usage of thin windows for vacuum vessels in terms of their design and application a Fermilab.

Western, J.L.

1993-03-01T23:59:59.000Z

159

Design and Evaluation of an Enhanced In-Vessel Core Catcher  

SciTech Connect

An enhanced in-vessel core catcher is being designed and evaluated as part of a joint United States (U.S.) - Korean International Nuclear Engineering Research Initiative (INERI) investigating methods to insure In-Vessel Retention (IVR) of core materials that may relocate under severe accident conditions in advanced reactors. 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): a base material, which has the capability to support and contain the mass of core materials that may relocate during a severe accident; an oxide coating material on top of the base material, which resists interactions with high-temperature core materials; and an optional coating on the bottom side of the base material to prevent any potential oxidation of the base material during the lifetime of the reactor. This paper summarizes the status of core catcher design and evaluation efforts, including analyses, materials interaction tests, and prototypic testing efforts.

Joy L. Rempe

2004-06-01T23:59:59.000Z

160

Helium leak testing of a radioactive contaminated vessel under high pressure in a contaminated environment  

Science Conference Proceedings (OSTI)

At ANL-W, with the shutdown of EBR-II, R&D has evolved from advanced reactor design to the safe handling, processing, packaging, and transporting spent nuclear fuel and nuclear waste. New methods of processing spent fuel rods and transforming contaminated material into acceptable waste forms are now in development. Storage of nuclear waste is a high interest item. ANL-W is participating in research of safe storage of nuclear waste, with the WIPP (Waste Isolation Pilot Plant) site in New Mexico the repository. The vessel under test simulates gas generated by contaminated materials stored underground at the WIPP site. The test vessel is 90% filled with a mixture of contaminated material and salt brine (from WIPP site) and pressurized with N2-1% He at 2500 psia. Test acceptance criteria is leakage jar method is used to determine leakage rate using a mass spectrometer leak detector (MSLD). The efficient MSLD and an Al bell jar replaced a costly, time consuming pressure decay test setup. Misinterpretation of test criterion data caused lengthy delays, resulting in the development of a unique procedure. Reevaluation of the initial intent of the test criteria resulted in leak tolerances being corrected and test efficiency improved.

Winter, M.E.

1996-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "research vessel mirai" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

Helium leak testing of a radioactive contaminated vessel under high pressure in a contaminated environment  

SciTech Connect

At ANL-W, with the shutdown of EBR-II, R&D has evolved from advanced reactor design to the safe handling, processing, packaging, and transporting spent nuclear fuel and nuclear waste. New methods of processing spent fuel rods and transforming contaminated material into acceptable waste forms are now in development. Storage of nuclear waste is a high interest item. ANL-W is participating in research of safe storage of nuclear waste, with the WIPP (Waste Isolation Pilot Plant) site in New Mexico the repository. The vessel under test simulates gas generated by contaminated materials stored underground at the WIPP site. The test vessel is 90% filled with a mixture of contaminated material and salt brine (from WIPP site) and pressurized with N2-1% He at 2500 psia. Test acceptance criteria is leakage < 10{sup -7} cc/seconds at 2500 psia. The bell jar method is used to determine leakage rate using a mass spectrometer leak detector (MSLD). The efficient MSLD and an Al bell jar replaced a costly, time consuming pressure decay test setup. Misinterpretation of test criterion data caused lengthy delays, resulting in the development of a unique procedure. Reevaluation of the initial intent of the test criteria resulted in leak tolerances being corrected and test efficiency improved.

Winter, M.E.

1996-10-01T23:59:59.000Z

162

BWRVIP-244: BWR Vessel and Internals Project, Nondestructive Evaluation Development 2010  

Science Conference Proceedings (OSTI)

This report provides 2010 results of the nondestructive evaluation NDE development task of the Boiling Water Reactor Vessel and Internals Project BWRVIP Inspection Focus Group. The scope of activity includes applications of various NDE techniques to boiling water reactor vessels and vessel internals components.

2010-12-23T23:59:59.000Z

163

An approach to localize the retinal blood vessels using bit planes and centerline detection  

Science Conference Proceedings (OSTI)

The change in morphology, diameter, branching pattern or tortuosity of retinal blood vessels is an important indicator of various clinical disorders of the eye and the body. This paper reports an automated method for segmentation of blood vessels in ... Keywords: Bit plane slicing, Blood vessel segmentation, First order derivative of Gaussian, Image segmentation, Mathematical morphology, Medical imaging, Retinal image, Ocular fundus

M. M. Fraz; S. A. Barman; P. Remagnino; A. Hoppe; A. Basit; B. Uyyanonvara; A. R. Rudnicka; C. G. Owen

2012-11-01T23:59:59.000Z

164

Materials Reliability Program: Reactor Pressure Vessel Integrity Training Module (MRP-286)  

Science Conference Proceedings (OSTI)

For many reactor pressure vessels, embrittlement is the primary concern in ensuring continued safe operation. The shutdown of the Yankee Rowe plant, which occurred because of uncertainties related to embrittlement of the vessel, demonstrated the importance of adequately addressing embrittlement issues. Managing embrittlement involves the integration, management, and implementation of diverse technical, regulatory, planning, and economic activities. Reactor vessel embrittlement management is an essential ...

2010-11-22T23:59:59.000Z

165

LNG Exports by Vessel out of the U.S. Form | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

out of the U.S. Form LNG Exports by Vessel out of the U.S. Form Excel Version of LNG Exports by Vessel out of the U.S. Form.xlsx PDF Version of LNG Exports by Vessel out of the...

166

Inexpensive Delivery of Compressed Hydrogen with Advanced Vessel Technology  

NLE Websites -- All DOE Office Websites (Extended Search)

delivery of compressed hydrogen delivery of compressed hydrogen with advanced vessel technology Gene Berry Andrew Weisberg Salvador M. Aceves Lawrence Livermore National Laboratory (925) 422-0864 saceves@LLNL.GOV DOE and FreedomCar & Fuel Partnership Hydrogen Delivery and On-Board Storage Analysis Workshop Washington, DC January 25, 2006 LLNL is developing innovative concepts for efficient containment of hydrogen in light duty vehicles concepts may offer advantages for hydrogen delivery Conformable containers efficiently use available space in the vehicle. We are pursuing multiple approaches to conformability High Strength insulated pressure vessels extend LH 2 dormancy 10x, eliminate boiloff, and enable efficiencies of flexible refueling (compressed/cryogenic H 2 /(L)H 2 ) The PVT properties of H

167

Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program:  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Assessment of High Value Surveillance Materials Assessment of High Value Surveillance Materials Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Assessment of High Value Surveillance Materials The reactor pressure vessel (RPV) in a light-water reactor (LWR) represents the first line of defense against a release of radiation in case of an accident. Thus, regulations that govern the operation of commercial nuclear power plants require conservative margins of fracture toughness, both during normal operation and under accident scenarios. In the unirradiated condition, the RPV has sufficient fracture toughness such that failure is implausible under any postulated condition, including pressurized thermal shock (PTS) in pressurized water reactors (PWR). In the irradiated condition, however, the fracture toughness of the RPV may be severely

168

Lightweight pressure vessels and unitized regenerative fuel cells  

DOE Green Energy (OSTI)

Energy storage systems have been designed using lightweight pressure vessels with unitized regenerative fuel cells (URFCs). The vessels provide a means of storing reactant gases required for URFCs; they use lightweight bladder liners that act as inflatable mandrels for composite overwrap and provide a permeation barrier. URFC systems have been designed for zero emission vehicles (ZEVs); they are cost competitive with primary FC powered vehicles that operate on H/air with capacitors or batteries for power peaking and regenerative braking. URFCs are capable of regenerative braking via electrolysis and power peaking using low volume/low pressure accumulated oxygen for supercharging the power stack. URFC ZEVs can be safely and rapidly (<5 min.) refueled using home electrolysis units. Reversible operation of cell membrane catalyst is feasible without significant degradation. Such systems would have a rechargeable specific energy > 400 Wh/kg.

Mitlitsky, F.; Myers, B.; Weisberg, A.H.

1996-09-06T23:59:59.000Z

169

PRESSURIZATION OF CONTAINMENT VESSELS FROM PLUTONIUM OXIDE CONTENTS  

Science Conference Proceedings (OSTI)

Transportation and storage of plutonium oxide is typically done using a convenience container to hold the oxide powder which is then placed inside a containment vessel. Intermediate containers which act as uncredited confinement barriers may also be used. The containment vessel is subject to an internal pressure due to several sources including; (1) plutonium oxide provides a heat source which raises the temperature of the gas space, (2) helium generation due to alpha decay of the plutonium, (3) hydrogen generation due to radiolysis of the water which has been adsorbed onto the plutonium oxide, and (4) degradation of plastic bags which may be used to bag out the convenience can from a glove box. The contributions of these sources are evaluated in a reasonably conservative manner.

Hensel, S.

2012-03-27T23:59:59.000Z

170

Lessons Learned From Developing Reactor Pressure Vessel Steel Embrittlement Database  

SciTech Connect

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.

Wang, Jy-An John [ORNL

2010-08-01T23:59:59.000Z

171

Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program:  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Initial Assessment of Thermal Annealing Needs and Challenges Initial Assessment of Thermal Annealing Needs and Challenges Reactor Pressure Vessel Task of Light Water Reactor Sustainability Program: Initial Assessment of Thermal Annealing Needs and Challenges The most life-limiting structural component in light-water reactors (LWR) is the reactor pressure vessel (RPV) because replacement of the RPV is not considered a viable option at this time. LWR licenses are now being extended from 40y to 60y by the U.S. Nuclear Regulatory Commission (NRC) with intentions to extend licenses to 80y and beyond. The RPV materials exhibit varying degrees of sensitivity to irradiation-induced embrittlement (decreased toughness) , as shown in Fig. 1.1, and extending operation from 40y to 80y implies a doubling of the neutron exposure for the RPV. Thus,

172

BWRVIP-60-A: BWR Vessel and Internals Project, Evaluation of Stress Corrosion Crack Growth in Low Alloy Steel Vessel Materials in th e BWR Environment  

Science Conference Proceedings (OSTI)

The Boiling Water Reactor Vessel and Internals Project (BWRVIP), formed in June 1994, is an association of utilities focused exclusively on boiling water reactor (BWR) vessel and internals materials issues. This report provides a methodology for assessing crack growth in BWR low alloy steel pressure vessels and nozzles. A previous version of this report was published as BWRVIP-60 (TR-108709). This report (BWRVIP-60-A) incorporates the U.S. Nuclear Regulatory Commission (NRC) Safety Evaluation (SE) and ot...

2003-06-09T23:59:59.000Z

173

IMPACT OF NUCLEAR MATERIAL DISSOLUTION ON VESSEL CORROSION  

Science Conference Proceedings (OSTI)

Different nuclear materials require different processing conditions. In order to maximize the dissolver vessel lifetime, corrosion testing was conducted for a range of chemistries and temperature used in fuel dissolution. Compositional ranges of elements regularly in the dissolver were evaluated for corrosion of 304L, the material of construction. Corrosion rates of AISI Type 304 stainless steel coupons, both welded and non-welded coupons, were calculated from measured weight losses and post-test concentrations of soluble Fe, Cr and Ni.

Mickalonis, J.; Dunn, K.; Clifton, B.

2012-10-01T23:59:59.000Z

174

Welding stainless and 9% nickel steel cryogenic vessels  

SciTech Connect

Gases are often more efficiently stored and shipped as liquids at cryogenic temperatures. Pure gases commonly stored below liquefaction temperatures include oxygen {minus}297 F ({minus}183 C), argon {minus}302 f ({minus}186 C), nitrogen {minus}320 F ({minus}196 C), hydrogen {minus}423 F ({minus}253 C) and helium {minus}452 F ({minus}269 C). Natural gas is also transported and frequently stored as liquefied natural gas (LNG) at temperatures below {minus}261 F ({minus}163 C). Storage tanks for the pure gases are generally shop fabricated in sizes that can be shipped by conventional carriers. Smaller LNG vessels for over-the-road and railroad fuel applications are also shop-fabricated. Shown in a figure is a rail-mounted tank designed to supply liquefied natural gas to locomotives. Another example of a tank installation is also shown. LNG terminal storage tanks are generally field-erected vessels fabricated from 9% nickel steel in sizes of 50,000 to 100,000 m{sup 3} (315,000 to 630,000 bbls). This article focuses on welding practices for shop-fabricated vessels and equipment.

Avery, R.E. [Nickel Development Inst., Londonderry, NH (United States); Parsons, D. [Parsons (David), Hampstead, NH (United States)

1995-11-01T23:59:59.000Z

175

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

E-Print Network (OSTI)

Distribution patterns of Classic Mimbres Black-on-white (Style III) bowls and jars were determined by instrumental neutron activation analysis (INAA) to identify vessel movement between geographically defined regions and between villages within individual regions of southwestern New Mexico. Ceramic and clay samples (n=288) from 15 sites in the Gila, Mimbres, and Rio Grande valleys composed the data set. Vessel movement was identified at the regional and site level to determine the degree of regional and site-specific interactions. Fifteen sites composed the regional level data set whereas only five sites contributed large enough sample sizes to determine vessel movement between sites at the site level of analysis. The operating hypotheses 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, (4) elites did not control ceramic vessel distribution. Discriminant function analysis was used to identify vessel movement based on INAA data. The statistical results indicated that bowls were more frequently exchanged than jars, a higher number of vessels were moved between sites within the same region than between regions, vessels were manufactured at the village level, and an elite that controlled vessel distribution most likely did not exist in the Mimbres culture. The absence of a controlling elite was inferred from the overall low levels of exchange and the identification of site-specific production locations.

Dahlin, Eleanor Sherlock

2003-01-01T23:59:59.000Z

176

GRR/Section 6-HI-e - Boiler Pressure Vessel Permit | Open Energy  

Open Energy Info (EERE)

GRR/Section 6-HI-e - Boiler Pressure Vessel Permit GRR/Section 6-HI-e - Boiler Pressure Vessel Permit < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 6-HI-e - Boiler Pressure Vessel Permit 06HIGBoilerPressureVesselPermit.pdf Click to View Fullscreen Contact Agencies Hawaii Department of Labor and Industrial Relations Occupational Safety and Health Division Regulations & Policies Boiler and Pressure Vessel Regulations Triggers None specified Click "Edit With Form" above to add content 06HIGBoilerPressureVesselPermit.pdf Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Flowchart Narrative Boiler/Pressure Vessel Permit

177

Method and apparatus for detecting irregularities on or in the wall of a vessel  

DOE Patents (OSTI)

A method of detecting irregularities on or in the wall of a vessel by detecting localized spatial temperature differentials on the wall surface, comprising scanning the vessel surface with a thermal imaging camera and recording the position of the or each region for which the thermal image from the camera is indicative of such a temperature differential across the region. The spatial temperature differential may be formed by bacterial growth on the vessel surface; alternatively, it may be the result of defects in the vessel wall such as thin regions or pin holes or cracks. The detection of leaks through the vessel wall may be enhanced by applying a pressure differential or a temperature differential across the vessel wall; the testing for leaks may be performed with the vessel full or empty, and from the inside or the outside.

Bowling, Michael Keith (Blackborough Cullompton, GB)

2000-09-12T23:59:59.000Z

178

An experimental study of assessment of weld quality on fatigue reliability analysis of a nuclear pressure vessel  

SciTech Connect

The steam generator in a PWR primary coolant system is one of the pieces of equipment made in China for the Qinshan nuclear power plant, Zhejiang. It is a crucial unit belonging to the category of nuclear pressure vessel. The purpose of this research work is to carry out an examination of the weld quality of the steam generator under fatigue loading and to assess its reliability by using experimental results of a fatigue test of the nuclear pressure vessel steel S-271 (Chinese Standard) and of qualified tests of welded seams of a simulated prototype of the bottom closure head of the steam generator. A guarantee of weld quality is proposed as the quality assurance of safety for the China National Nuclear Safety Supervision Bureau. The results of the reliability analysis reported in this work can be taken as supplementary material for a Probabilistic Risk Assessment (PRA) of the Qinshan nuclear power plant. According to the requirement of Provision 2-1500 CYCLIC TESTING, ASME Boiler and Pressure Vessel Code, Section 3, Rules for Construction of Nuclear Power Plant Components, a simulated prototype of the bottom closure head of the steam generator was made in this work for the qualified tests. Qualified tests with small sample size present a problem which is difficult to solve in reliability analysis, and are therefore of interest. Here, the authors offer proposals attempting to solve this problem.

Dai, Shuho (Nanjing Inst. of Chemical Technology, Jiangsu (China). Dept. of Mechanical Engineering)

1993-11-01T23:59:59.000Z

179

Upgrade of the DIII-D vacuum vessel protection system  

SciTech Connect

An upgrade of the General Atomics DIII-D tokamak armor protection system has been completed. The upgrade consisted of armoring the outer wall and the divertor gas baffle with monolithic graphite tiles and cleaning the existing floor, ceiling, and inner wall tiles to remove any deposited impurity layer from the tile surfaces. The new tiles replace the graphite tiles used as local armor for neutral beam shine through, three graphite poloidal back-up limiter bands, and miscellaneous Inconel protection tiles. The total number of tiles increased from 1636 to 3200 and corresponding vessel coverage from 40% to 90%. A new, graphite armored, toroidally continuous, gas baffle between the outer wall and the biased divertor ring was installed in order to accommodate the cryocondensation pump that was installed in parallel with the outer wall tiles. To eliminate a source of copper in the plasma, GRAFOIL gaskets replaced the copper felt metal gaskets previously used as a compliant heat transfer interface between the inertially cooled tiles and the vessel wall. GRAFOIL, an exfoliated, flexible graphite material from Union Carbide, Inc., was used between each tile and the vessel wall and also between each tile and its hold-down hardware. Testing was performed to determine the mechanical compliance, thermal conductance, and vacuum characteristics of the GRAFOIL material. To further decrease the quantity of high Z materials exposed to the plasma, the 1636 existing graphite tiles were identified, removed, and grit blasted to eliminate a thin layer of deposited metals which included nickel, chromium, and molybdenum. Prior to any processing, a selected set of tiles was tested for radioactivity, including tritium contamination. The tiles were grit blasted in a negative-pressure blasting cabinet using 37 {mu}m boron carbide powder as the blast media and dry nitrogen as the propellant.

Hollerbach, M.A.; Lee, R.L.; Smith, J.P.; Taylor, P.L.

1993-10-01T23:59:59.000Z

180

Use of Polycarbonate Vacuum Vessels in High-Temperature Fusion-Plasma Research  

Science Conference Proceedings (OSTI)

Divertor and High-Heat-Flux Components / Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 1), Nashville, Tennessee, August 27-31, 2012

B. Berlinger; A. Brooks; H. Feder; J. Gumbas; T. Franckowiak; S. A. Cohen

Note: This page contains sample records for the topic "research vessel mirai" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

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

SciTech Connect

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.

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

2013-04-16T23:59:59.000Z

182

Certification Testing and Demonstration of Insulated Pressure Vessels for Vehicular Hydrogen and Natural Gas Storage  

Science Conference Proceedings (OSTI)

We are working on developing an alternative technology for storage of hydrogen or natural gas on light-duty vehicles. This technology has been titled insulated pressure vessels. Insulated pressure vessels are cryogenic-capable pressure vessels that can accept either liquid fuel or ambient-temperature compressed fuel. Insulated pressure vessels offer the advantages of cryogenic liquid fuel tanks (low weight and volume), with reduced disadvantages (fuel flexibility, lower energy requirement for fuel liquefaction and reduced evaporative losses). The work described in this paper is directed at verifying that commercially available pressure vessels can be safely used to store liquid hydrogen or LNG. The use of commercially available pressure vessels significantly reduces the cost and complexity of the insulated pressure vessel development effort. This paper describes a series of tests that have been done with aluminum-lined, fiber-wrapped vessels to evaluate the damage caused by low temperature operation. All analysis and experiments to date indicate that no significant damage has resulted. Future activities include a demonstration project in which the insulated pressure vessels will be installed and tested on two vehicles. A draft standard will also be generated for obtaining insulated pressure vessel certification.

Aceves, S M; Martinez-Frias, J; Espinosa-Loza, F; Schaffer, R; Clapper, W

2002-05-22T23:59:59.000Z

183

Remotely Operated Equipment for Post Irradiation Examination of the SNS Target Vessel  

Science Conference Proceedings (OSTI)

The Spallation Neutron Source produces neutrons by accelerating protons into flowing mercury contained inside a stainless steel target vessel. During facility operation the target vessel is degraded by a combination of high-energy neutrons, the proton beam, and cavitation-induced corrosion. The degradation is primarily concentrated at the nose of the target vessel, where the proton beam passes through. Currently, the Spallation Neutron Source has replaced three target vessels and is operating the fourth. To minimize the operational costs of manufacturing and disposing of target vessels, efforts are underway to increase the operational lifetimes of the target vessels by conducting post irradiation examinations of spent vessels. This examination involves remotely removing multiple coupons from the nose of the target vessel using a single piece of equipment, called the Nose Sampling Cutter, installed inside the Spallation Neutron Source s hot cell. The Cutter produces circular coupons approximately 2 inches in diameter using a carbide-tipped hole saw. The nose of the target vessel consists of four layers of material, and the Nose Sampling Cutter is capable of cutting through the layers in a single stroke. This remote operation has been successfully completed twice. In addition to the Nose Sampling Cutter, a large reciprocation saw capable of removing a sizable section of the nose of the target vessel has been constructed and tested, but never implemented. To support this large reciprocation saw other equipment has also been designed. The details of the Nose Sampling Cutter, reciprocation saw, and associated equipment are discussed.

Carroll, Adam J [ORNL; Graves, Van B [ORNL; Dayton, Michael J [ORNL; Riemer, Bernie [ORNL

2011-01-01T23:59:59.000Z

184

Research Opportunities  

Science Conference Proceedings (OSTI)

*. Bookmark and Share. Research Opportunities. ... NRC Postdoctoral Research Associateships Program; NIST NRC Program Description. ...

2013-04-22T23:59:59.000Z

185

Blowdown of hydrocarbons pressure vessel with partial phase separation  

E-Print Network (OSTI)

We propose a model for the simulation of the blowdown of vessels containing two-phase (gas-liquid) hydrocarbon fluids, considering non equilibrium between phases. Two phases may be present either already at the beginning of the blowdown process (for instance in gas-liquid separators) or as the liquid is formed from flashing of the vapor due to the cooling induced by pressure decrease. There is experimental evidence that the assumption of thermodynamic equilibrium is not appropriate, since the two phases show an independent temperature evolution. Thus, due to the greater heat transfer between the liquid phase with the wall, the wall in contact with the liquid experiences a stronger cooling than the wall in contact with the gas, during the blowdown. As a consequence, the vessel should be designed for a lower temperature than if it was supposed to contain vapor only. Our model is based on a compositional approach, and it takes into account internal heat and mass transfer processes, as well as heat transfer with ...

Speranza, Alessandro; 10.1142/9789812701817_0046

2011-01-01T23:59:59.000Z

186

Calculations to estimate the margin to failure in the TMI-2 vessel  

SciTech Connect

As part of the OECD-sponsored Three Mile Island Unit 2 (TMI-2) Vessel Investigation Project (VIP), margin-to-failure calculations for mechanisms having the potential to threaten the integrity of the vessel were performed to improve understanding of events that occurred during the TMI-2 accident. Analyses considered four failure mechanisms: tube rupture, tube ejection, global vessel failure, and localized vessel failure. Calculational input was based on data from the TMI-2 VIP examinations of the vessel steel samples, the instrument tube nozzles, and samples of the hard layer of debris found on the TMI-2 vessel lower head. Sensitivity studies were performed to investigate the uncertainties in key parameters for these analyses.

Stickler, L.A.; Rempe, J.L.; Chavez, S.A.; Thinnes, G.L.; Snow, S.D. [EG& G Idaho, Inc., Idaho Falls, ID (United States); Witt, R.J.; Corradini, M.L.; Kos, J.A. [Univ. of Wisconsin, Madison, WI (United States)

1994-03-01T23:59:59.000Z

187

PRESTRESSING A TWO-LAYER PRESSURE VESSEL BY CONTROLLED YIELDING OF THE INNER LAYER  

SciTech Connect

A method of designing a two-layer pressure vessel is presented wherein contact between the layers is produced by controlled yielding of the inner vessel by internal pressure. The amount of prestress depends upon the dimensions of the vessel, the properties of the material of construction, and the prestressing pressure. The method takes into account the actual stress-strain curve of the material and satisfies the rales of plastic flow with work hardening. (auth)

Schneider, R.W.

1964-04-01T23:59:59.000Z

188

PRESTRESSING A TWO-LAYER PRESSURE VESSEL BY CONTROLLED YIELDING OF THE INNER LAYER  

SciTech Connect

A method is presented for designing a two-layer pressure vessel wherein contact between the layers is produced by controlled yielding of the inner vessel by internal pressure. The amount of prestress depends upon the dimensions of the vessel, the properties of the material of construction, and the prestressing pressure. The method takes into account the actual stress-strain curve of the material and satisfies the rules of plastic flow with work hardening. (auth)

Schneider, R.W.

1964-01-29T23:59:59.000Z

189

BWRVIP-189: BWR Vessel and Internals Project, Evaluation of RAMA Fluence Methodology Calculational Uncertainty  

Science Conference Proceedings (OSTI)

This report documents the overall calculational uncertainty associated with the application of the Radiation Application Modeling Application (RAMA) Fluence Methodology to BWR reactor pressure vessel fluence evaluations.

2008-07-07T23:59:59.000Z

190

Nuclear reactor having a polyhedral primary shield and removable vessel insulation  

DOE Patents (OSTI)

A nuclear reactor is provided having a generally cylindrical reactor vessel disposed within an opening in a primary shield. The opening in the primary shield is defined by a plurality of generally planar side walls forming a generally polyhedral-shaped opening. The reactor vessel is supported within the opening in the primary shield by reactor vessel supports which are in communication and aligned with central portions of some of the side walls. The reactor vessel is connected to the central portions of the reactor vessel supports. A thermal insulation polyhedron formed from a plurality of slidably insertable and removable generally planar insulation panels substantially surrounds at least a portion of the reactor vessel and is disposed between the reactor vessel and the side walls of the primary shield. The shape of the insulation polyhedron generally corresponds to the shape of the opening in the primary shield. Reactor monitoring instrumentation may be mounted in the corners of the opening in the primary shield between the side walls and the reactor vessel such that insulation is not disposed between the instrumentation and the reactor vessel. 5 figures.

Ekeroth, D.E.; Orr, R.

1993-12-07T23:59:59.000Z

191

Nuclear reactor having a polyhedral primary shield and removable vessel insulation  

DOE Patents (OSTI)

A nuclear reactor is provided having a generally cylindrical reactor vessel disposed within an opening in a primary shield. The opening in the primary shield is defined by a plurality of generally planar side walls forming a generally polyhedral-shaped opening. The reactor vessel is supported within the opening in the primary shield by reactor vessel supports which are in communication and aligned with central portions of some of the side walls. The reactor vessel is connected to the central portions of the reactor vessel supports. A thermal insulation polyhedron formed from a plurality of slidably insertable and removable generally planar insulation panels substantially surrounds at least a portion of the reactor vessel and is disposed between the reactor vessel and the side walls of the primary shield. The shape of the insulation polyhedron generally corresponds to the shape of the opening in the primary shield. Reactor monitoring instrumentation may be mounted in the corners of the opening in the primary shield between the side walls and the reactor vessel such that insulation is not disposed between the instrumentation and the reactor vessel.

Ekeroth, Douglas E. (Delmont, PA); Orr, Richard (Pittsburgh, PA)

1993-01-01T23:59:59.000Z

192

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

E-Print Network (OSTI)

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 ...

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

2010-01-01T23:59:59.000Z

193

Research - CECM  

E-Print Network (OSTI)

Our research is outlined our research proposals below. Samples of completed research may be found under "Sample Papers" and under "Project Highlights" on ...

194

Experiment DTA report for semiscale transparent vessel countercurrent flow tests  

SciTech Connect

Steady state air-water tests were performed as part of the Semiscale Blowdown and Emergency Core Cooling (ECC) Project to investigate downcomer countercurrent flow and downcomer bypass flow phenomena. These tests were performed in a plexiglass representation of the Semiscale pressure vessel which allowed changes to be madein the geometry of the upper annulus and downcomer for the purpose of investigating the sensitivity of downcomer and bypass flow to changes in system geometry. Tests were also performed to investigate the effects of two-phase inlet flows and different initial system pressures on countercurrent and bypass flow. Results for each test are presented in the form of computer printout of the measurements and of a summary of the pertinent calculated flow rates, pressures, and dimensionless volumetric fluxes. Descriptions of the test facility, instrumentation, operating procedures, and test conditions are also presented. An error analysis is presented for selected volumetric flux calculations. 10 references. (auth)

Hanson, D.J.

1975-10-01T23:59:59.000Z

195

Reactor Vessel Head Disposal Campaign for Nuclear Management Company  

SciTech Connect

After establishing a goal to replace as many reactor vessel heads as possible - in the shortest time and at the lowest cost as possible - Nuclear Management Company (NMC) initiated an ambitious program to replace the heads on all six of its pressurized water reactors. Currently, four heads have been replaced; and four old heads have been disposed of. In 2002, NMC began fabricating the first of its replacement reactor vessel heads for the Kewaunee Nuclear Plant. During its fall 2004 refueling outage, Kewaunee's head was replaced and the old head was prepared for disposal. Kewaunee's disposal project included: - Down-ending, - Draining, - Decontamination, - Packaging, - Removal from containment, - On-Site handling, - Temporary storage, - Transportation, - Disposal. The next two replacements took place in the spring of 2005. Point Beach Nuclear Plant (PBNP) Unit 2 and Prairie Island Nuclear Generating Plant (PINGP) Unit 2 completed their head replacements during their scheduled refueling outages. Since these two outages were scheduled so close to each other, their removal and disposal posed some unique challenges. In addition, changes to the handling and disposal programs were made as a result of lessons learned from Kewaunee. A fourth head replacement took place during PBNP Unit 1's refueling outage during the fall of 2005. A number of additional changes took place. All of these changes and challenges are discussed in the paper. NMC's future schedule includes PINGP Unit 1's installation in Spring 2006 and Palisades' installation during 2007. NMC plans to dispose of these two remaining heads in a similar manner. This paper presents a summary of these activities, plus a discussion of lessons learned. (authors)

Hoelscher, H.L.; Closs, J.W. [Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016 (United States); Johnson, S.A. [Duratek, Inc., 140 Stoneridge Drive, Columbia, SC 29210 (United States)

2006-07-01T23:59:59.000Z

196

Instrumentation of a prestressed concrete containment vessel model  

Science Conference Proceedings (OSTI)

A series of static overpressurization tests of scale models of nuclear containment structures is being conducted by Sandia National Laboratories for the Nuclear Power Engineering Corporation of Japan and the U.S. Nuclear Regulatory Commission. At present, two tests are being planned: a test of a model of a steel containment vessel (SCV) that is representative of an improved, boiling water reactor (BWR) Mark II design; and a test of a model of a prestressed concrete containment vessel (PCCV). This paper discusses plans and the results of a preliminary investigation of the instrumentation of the PCCV model. The instrumentation suite for this model will consist of approximately 2000 channels of data to record displacements, strains in the reinforcing steel, prestressing tendons, concrete, steel liner and liner anchors, as well as pressure and temperature. The instrumentation is being designed to monitor the response of the model during prestressing operations, during Structural Integrity and Integrated Leak Rate testing, and during test to failure of the model. Particular emphasis has been placed on instrumentation of the prestressing system in order to understand the behavior of the prestressing strands at design and beyond design pressure levels. Current plans are to place load cells at both ends of one third of the tendons in addition to placing strain measurement devices along the length of selected tendons. Strain measurements will be made using conventional bonded foil resistance gages and a wire resistance gage, known as a {open_quotes}Tensmeg{close_quotes}{reg_sign} gage, specifically designed for use with seven-wire strand. The results of preliminary tests of both types of gages, in the laboratory and in a simulated model configuration, are reported and plans for instrumentation of the model are discussed.

Hessheimer, M.F.; Rightley, M.J. [Sandia National Labs., Albuquerque, NM (United States); Matsumoto, T. [Nuclear Power Engineering Corp., Tokyo (Japan)] [and others

1995-09-01T23:59:59.000Z

197

The Disruption of Vessel-Spanning Bubbles with Sloped Fins in Flat-Bottom and 2:1 Elliptical-Bottom Vessels  

DOE Green Energy (OSTI)

Radioactive sludge was generated in the K-East Basin and K-West Basin fuel storage pools at the Hanford Site while irradiated uranium metal fuel elements from the N Reactor were being stored and packaged. The fuel has been removed from the K Basins, and currently, the sludge resides in the KW Basin in large underwater Engineered Containers. The first phase to the Sludge Treatment Project being led by CH2MHILL Plateau Remediation Company (CHPRC) is to retrieve and load the sludge into sludge transport and storage containers (STSCs) and transport the sludge to T Plant for interim storage. The STSCs will be stored inside T Plant cells that are equipped with secondary containment and leak-detection systems. The sludge is composed of a variety of particulate materials and water, including a fraction of reactive uranium metal particles that are a source of hydrogen gas. If a situation occurs where the reactive uranium metal particles settle out at the bottom of a container, previous studies have shown that a vessel-spanning gas layer above the uranium metal particles can develop and can push the overlying layer of sludge upward. The major concern, in addition to the general concern associated with the retention and release of a flammable gas such as hydrogen, is that if a vessel-spanning bubble (VSB) forms in an STSC, it may drive the overlying sludge material to the vents at the top of the container. Then it may be released from the container into the cells secondary containment system at T Plant. A previous study demonstrated that sloped walls on vessels, both cylindrical coned-shaped vessels and rectangular vessels with rounded ends, provided an effective approach for disrupting a VSB by creating a release path for gas as a VSB began to rise. Based on the success of sloped-wall vessels, a similar concept is investigated here where a sloped fin is placed inside the vessel to create a release path for gas. A key potential advantage of using a sloped fin compared to a vessel with a sloped wall is that a small fin decreases the volume of a vessel available for sludge storage by a very small fraction compared to a cone-shaped vessel. The purpose of this study is to quantify the capability of sloped fins to disrupt VSBs and to conduct sufficient tests to estimate the performance of fins in full-scale STSCs. Experiments were conducted with a range of fin shapes to determine what slope and width were sufficient to disrupt VSBs. Additional tests were conducted to demonstrate how the fin performance scales with the sludge layer thickness and the sludge strength, density, and vessel diameter based on the gravity yield parameter, which is a dimensionless ratio of the force necessary to yield the sludge to its weight.( ) Further experiments evaluated the difference between vessels with flat and 2:1 elliptical bottoms and a number of different simulants, including the KW container sludge simulant (complete), which was developed to match actual K-Basin sludge. Testing was conducted in 5-in., 10-in., and 23-in.-diameter vessels to quantify how fin performance is impacted by the size of the test vessel. The most significant results for these scale-up tests are the trend in how behavior changes with vessel size and the results from the 23-in. vessel. The key objective in evaluating fin performance is to determine the conditions that minimize the volume of a VSB when disruption occurs because this reduces the potential for material inside the STSC from being released through vents.

Gauglitz, Phillip A.; Buchmiller, William C.; Jenks, Jeromy WJ; Chun, Jaehun; Russell, Renee L.; Schmidt, Andrew J.; Mastor, Michael M.

2010-09-22T23:59:59.000Z

198

Materials Reliability Project: Benchmark Study of Reactor Pressure Vessel Integrity Probabilistic Computational Results Using the Fracture Analysis of Vessels Oak Ridge (FAVOR) Software Code (MRP-371)  

Science Conference Proceedings (OSTI)

This report reports the results from the Fracture Analysis of Vessels Oak Ridge (FAVOR) software analysis of three transients that simulated pressurized thermal shock events in pressurized water reactor (PWR) reactor pressure vessels (RPVs). It was determined that software modifications would be required to complete the probabilistic analyses for the wide range of flaw sizes and locations of interest in the study. Consequently, two software revisions were provided by EPRI to enable ...

2013-08-22T23:59:59.000Z

199

BWRVIP-34-A: BWR Vessel and Internals Project, Technical Basis for Part Circumference Weld Overlay Repair of Vessel Internal Core Sp ray Piping  

Science Conference Proceedings (OSTI)

The Boiling Water Reactor Vessel and Internals Project (BWRVIP), formed in June 1994, is an association of utilities focused exclusively on boiling water reactor (BWR) vessel and internals issues. This report summarizes the results of the design and analysis activities and the testing programs conducted to provide BWR utilities with a contingency repair option for internal core spray piping for BWR2/6 plants. A previous version of this report was published as BWRVIP-34 (TR-108198). This report (BWRVIP-34...

2008-03-11T23:59:59.000Z

200

Research Opportunities  

Science Conference Proceedings (OSTI)

... industrial or academic partner perform joint research with outcomes ... these collaborations arise spontaneously and the researchers jointly pursue ...

2013-06-27T23:59:59.000Z

Note: This page contains sample records for the topic "research vessel mirai" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

PNNL: Research  

NLE Websites -- All DOE Office Websites (Extended Search)

Full Story Research at PNNL Home Featured Highlights Archive Research Directorates Energy & Environment Fundamental & Computational Sciences National Security Facilities...

202

Guest Researchers  

Science Conference Proceedings (OSTI)

... If confidentiality of cooperative research results are desired a Cooperative Research and Development Agreement (CRADA) may be appropriate. ...

2012-07-06T23:59:59.000Z

203

BWRVIP-269: BWR Vessel and Internals Project, Nondestructive Evaluation Development 2012  

Science Conference Proceedings (OSTI)

The purpose of this report is to describe the results of nondestructive evaluation (NDE) activities conducted in the previous year within the NDE Development task of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Inspection Focus Group. The scope of the ongoing NDE Development task includes the reactor vessel and its internal components. This task attempts to develop solutions for the more difficult ...

2012-12-12T23:59:59.000Z

204

BWR Vessel and Internals Project: Quantitative Safety Assessment of BWR Reactor Internals (BWRVIP-09)  

Science Conference Proceedings (OSTI)

The Boiling Water Reactor Vessel and Internals Project (BWRVIP), formed in June, 1994, is an association of utilities focused exclusively on BWR vessel and internals issues. This BWRVIP report documents the results of a quantitative safety assessment conducted to evaluate the safety significance of failures of certain BWR internal components.

1997-02-20T23:59:59.000Z

205

Qualification of In-Service Examination of the Yankee Rowe Reactor Pressure Vessel  

Science Conference Proceedings (OSTI)

An effective in-service examination of the reactor pressure vessel was an essential part of the restart program for the Yankee Atomic Power Company plant in Rowe, Massachusetts. This report describes development of an effective examination strategy, demonstration of performance of the examination procedures, and development of data on the distribution of flaws in reactor pressure vessels.

1993-01-01T23:59:59.000Z

206

HIGH TEMPERATURE THERMAL AND STRUCTURAL MATERIAL PROPERTIES FOR METALS USED IN LWR VESSELS  

Science Conference Proceedings (OSTI)

Because of the impact that melt relocation and vessel failure may have on subsequent progression and associated consequences of a Light Water Reactor (LWR) accident, it is important to accurately predict heating and relocation of materials within the reactor vessel, heat transfer to and from the reactor vessel, and the potential for failure of the vessel and structures within it. Accurate predictions of such phenomena require high temperature thermal and structural properties. However, a review of vessel and structural steel material properties used in severe accident analysis codes reveals that the required high temperature material properties are extrapolated with little, if any, data above 1000 K. To reduce uncertainties in predictions relying upon extrapolated high temperature data, Idaho National Laboratory (INL) obtained high data for two metals used in LWR vessels: SA 533 Grade B, Class 1 (SA533B1) low alloy steel, which is used to fabricate most US LWR reactor vessels; and Type 304 Stainless Steel SS304, which is used in LWR vessel piping, penetration tubes, and internal structures. This paper summarizes the new data, and compares it to existing data.

J.L. Rempe; D.L. Knudson; J. E. Daw; J. C. Crepeau

2008-06-01T23:59:59.000Z

207

RIS-M-2186 INTERPRETATIOM OF STRAIN HBASUREMEMTS ON NUCLEAR PRESSURE VESSELS  

E-Print Network (OSTI)

RIS?-M- 2186 INTERPRETATIOM OF STRAIN HBASUREMEMTS ON NUCLEAR PRESSURE VESSELS Svend Ib Andersen Preben Engbzk Abstract. Selected results from strain measurements on 4 nuclear pressure vessels procedure before and after the test as well as a detailed knowledge of the behaviour of the signal from

208

Repair Technology for Degraded Pressure Vessel and Heat Exchanger Shells: RRAC Task 91  

Science Conference Proceedings (OSTI)

The ability to repair pressure vessels and heat exchangers offers utilities significant cost savings compared to replacing these components. This is especially the case if outage time and loss of production are factored into the cost of replacement. This guide provides a review of various current and proposed repair methods that can be used for pressure vessel and heat exchanger applications.

2002-12-02T23:59:59.000Z

209

REACTION OF DOLPHINS TO A SURVEY VESSEL: EFFECTS ON CENSUS DATA  

E-Print Network (OSTI)

REACTION OF DOLPHINS TO A SURVEY VESSEL: EFFECTS ON CENSUS DATA RoGER P. HEWITI'l ABSTRACf A field of a survey vessel prior to their detection by shipboard observers and that the use of a monotonically decreasing detection function is adequate to minimize bias. Aerial and shipboard estimates of school size

210

Conceptual Design of a Reactor Pressure Vessel and its Internals for a HPLWR  

Science Conference Proceedings (OSTI)

A design for the Reactor Pressure Vessel (RPV) and its internals for a HPLWR (High Performance Light Water Reactor) is presented. The RPV has been dimensioned using the pressure vessel code for nuclear power plants in Germany. In order to use conventional vessel materials such as 20 MnMoNi 5 5 (United States: SA 508), the vessel inner wall has to be kept only in contact with coolant at inlet temperature. Therefore, the hot coolant pipe connection from the steam plenum to the outlet is separated from the RPV inner wall using a thermal sleeve. The core inside the vessel rests on a support plate which is connected to the core barrel. The steam plenum is fixed on top of the core using support brackets which are attached to the adjustable steam outlet pipes. This way, the steam plenum rests on the outlet flanges of the lower vessel, while the core barrel is suspended at the closure head flange of the vessel to control thermal expansions between the internals and the RPV and to minimize thermal stresses. Both, inlet and outlet mass flows are separated via C-ring seals to prevent mixing. The control rod guides in the upper plenum are also suspended at the vessel flange and aligned inside the core barrel using centering pins. (authors)

Fischer, Kai [EnBW Kraftwerke AG, Kernkraftwerk Philippsburg, Rheinschanzinsel D-76661 Philippsburg (Germany); Starflinger, Joerg; Schulenberg, Thomas [Forschungszentrum Karlsruhe GmbH, Institute for Nuclear and Energy Technologies P.O. Box 3640, D-76021 Karlsruhe (Germany)

2006-07-01T23:59:59.000Z

211

Marine Casualty and Pollution Database - Vessel Events for 2002 to 2010 |  

NLE Websites -- All DOE Office Websites (Extended Search)

Vessel Events for 2002 to 2010 Vessel Events for 2002 to 2010 Ocean Data Tools Technical Guide Map Gallery Regional Planning Feedback Ocean You are here Data.gov » Communities » Ocean » Data Marine Casualty and Pollution Database - Vessel Events for 2002 to 2010 Dataset Summary Description The Marine Casualty and Pollution Data files provide details about marine casualty and pollution incidents investigated by Coast Guard Offices throughout the United States. The database can be used to analyze marine accidents and pollution incidents by a variety of factors including vessel or facility type, injuries, fatalities, pollutant details, location, and date. The data collection period began in 1982 for marine casualties and 1973 for polluting incidents, and is ongoing. Documentation includes entity and attribute descriptions along with suggested solutions to general marine pollution, vessel casualty, and personnel injury and death questions.

212

Method of design for vertical oil shale retorting vessels and retorting therewith  

DOE Patents (OSTI)

A method of designing the gas flow parameters of a vertical shaft oil shale retorting vessel involves determining the proportion of gas introduced in the bottom of the vessel and into intermediate levels in the vessel to provide for lateral distribution of gas across the vessel cross section, providing mixing with the uprising gas, and determining the limiting velocity of the gas through each nozzle. The total quantity of gas necessary for oil shale treatment in the vessel may be determined and the proportion to be injected into each level is then determined based on the velocity relation of the orifice velocity and its feeder manifold gas velocity. A limitation is placed on the velocity of gas issuing from an orifice by the nature of the solid being treated, usually physical tests of gas velocity impinging the solid.

Reeves, Adam A. (Rifle, CO)

1978-01-03T23:59:59.000Z

213

BWRVIP-239: BWR Vessel and Internals Project, Updated Evaluation of the Integrated Surveillance Program (ISP) Capsule Withdrawal Sch edule  

Science Conference Proceedings (OSTI)

This report evaluates updated reactor pressure vessel and surveillance capsule fluence data for potential impacts on the Boiling Water Reactor Vessel and Internals Project Integrated Surveillance Program (BWRVIP ISP) capsule withdrawal schedule.

2010-07-16T23:59:59.000Z

214

Investigation of downward facing critical heat flux with water-based nanofluids for In-Vessel Retention applications  

E-Print Network (OSTI)

In-Vessel Retention ("IVR") is a severe accident management strategy that is power limiting to the Westinghouse AP1000 due to critical heat flux ("CHF") at the outer surface of the reactor vessel. Increasing the CHF level ...

DeWitt, Gregory L

2011-01-01T23:59:59.000Z

215

Method for forming a bladder for fluid storage vessels  

DOE Green Energy (OSTI)

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.

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

2000-01-01T23:59:59.000Z

216

In-vessel activation monitors in JET: Progress in modeling  

SciTech Connect

Activation studies were performed in JET with new in-vessel activation monitors. Though primarily dedicated to R and D in the challenging issue of lost {alpha} diagnostics for ITER, which is being addressed at JET with several techniques, these monitors provide for both neutron and charged particle fluences. A set of samples with different orientation with respect to the magnetic field is transported inside the torus by means of a manipulator arm (in contrast with the conventional JET activation system with pneumatic transport system). In this case, radionuclides with longer half-life were selected and ultralow background gamma-ray measurements were needed. The irradiation was closer to the plasma and this potentially reduces the neutron scattering problem. This approach could also be of interest for ITER, where the calibration methods have yet to be developed. The MCNP neutron transport model for JET was modified to include the activation probe and so provide calculations to help assess the new data. The neutron induced activity on the samples are well reproduced by the calculations.

Bonheure, Georges [Laboratory for Plasma Physics, Association 'Euratom-Belgian State', Avenue de la Renaissance 30, B-1000 Brussels (Belgium); Lengar, I. [Slovenian Fusion Association, Jozef Stefan Institute, Jamova 39, SI-1000 Ljubljana (Slovenia); Syme, B.; Popovichev, S. [Euratom/UKAEA Association, Culham Science Centre, Abingdon, OX14 3DB Oxon (United Kingdom); Wieslander, Elisabeth; Hult, Mikael; Gasparro, Joeel; Marissens, Gerd [EC-JRC-IRMM, Institute for Reference Materials and Measurements, Retieseweg 111, B-2440 Geel (Belgium); Arnold, Dirk [Physikalisch-Technische Bundesanstalt, 6.1 Radioactivity, Bundesallee 100, D-38116 Braunschweig (Germany); Laubenstein, Matthias [Laboratori Nazionali del Gran Sasso, S.S, 17/bis, km 18-910, I-67010 Assergi (Italy)

2008-10-15T23:59:59.000Z

217

Comparison of Pressure Vessel Design and Inspection Requirements as Defined by ASME Code and Germany's TRD Code  

Science Conference Proceedings (OSTI)

This report compares the American Society of Mechanical Engineers (ASME) Code with the German TRD Code for pressure vessel engineering, fabrication, inspection, and other pressure vessel processes. The report compares calculations of minimum required wall thickness for pressure vessels such as boiler tubes, pipes, headers, and drums. It also compares material allowable stress values and reviews the major materials permitted by both codes for use in pressure vessel engineering and manufacturing. The repor...

1994-09-22T23:59:59.000Z

218

Research Home  

NLE Websites -- All DOE Office Websites (Extended Search)

Cancer & Radiation Radiochemistry & Instrumentation Genome Dynamics BioenergyGTL Technology Centers Resources Research Research in the Life Sciences Division contributes to...

219

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

Effective Diameter in Ice Clouds and Its Application to Terrestrial Radiation Download a printable PDF Submitter: Mitchell, D. L., Desert Research Institute Area of Research:...

220

Research Facilities  

NLE Websites -- All DOE Office Websites (Extended Search)

FLEX lab image, windows testing lab, scientist inside a lab, Research Facilities EETD maintains advanced research and test facilities for buildings, energy technologies, air...

Note: This page contains sample records for the topic "research vessel mirai" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

Research Highlights Summaries Modeling the Sensitivity of Convection to Tropospheric Humidity Download a printable PDF Submitter: Del Genio, A. D., NASA Area of Research: General...

222

Research Library  

NLE Websites -- All DOE Office Websites (Extended Search)

LANL Research Library: delivering essential knowledge services for national security sciences since 1947 About the Research Library The Basics Mission We deliver agile, responsive...

223

Research Gallery  

NLE Websites -- All DOE Office Websites (Extended Search)

Research Gallery Research Gallery Inside the Museum Exhibitions Norris Bradbury Museum Lobby Defense Gallery Research Gallery History Gallery TechLab Virtual Exhibits invisible utility element Research Gallery Science serving society The Laboratory conducts leading-edge research in many areas of science and technology to help solve national problems related to energy, the environment, infrastructure, and health. Basic research conducted here enhances national defense and economic security. Exhibits you'll find in this gallery: Understanding Radiation LANSCE: Los Alamos Neutron Science Center Space Science Research Viewspace Environmental Monitoring and Research Nanotechnology: The Science of the Small Algae to Biofuels: Squeezing Power from Pond Scum Living with Wildfire: A Shared Community Experience

224

Impacts of Vessel Noise Perturbations on the Resident Sperm Whale Population in the Gulf of Mexico  

E-Print Network (OSTI)

The Gulf of Mexico is home to two of the world?s ten busiest ports by cargo volume, the Port of New Orleans and the Port of Houston; and in 2008, these ports hosted a combined 14,000 ships, a number which is likely only to increase. Past research shows that this increase in shipping worldwide has historically lead to an increase in ambient noise level of 3-5dB per decade. Sperm whales in the Gulf of Mexico are considered a genetically distinct, resident population. They have a preference for the Louisiana-Mississippi Shelf region which directly overlaps with the entrance to the Mississippi and the Port of New Orleans. Disruptions from vessel noise could influence feeding and breeding patterns essential to the health of the stock. Data used in this analysis were collected continuously over 36 days in the summer of 2001 from bottom moored Navy Environmental Acoustic Recording System (EARS) buoys. Results showed a significant difference (P<0.05) in noise level between hours with ships passing and hours without. Metrics for 56 ship passages were analyzed to compare duration of ship passage with duration of maximum received level (MRL) during ship passage. Results of that analysis showed an average ship passage of 29 minutes with average MRL lasting 23% of the ship passage and an average increase of 40dB. Lastly, click counts were made with the Pamguard. Click counts for ship passages were completed for 35 min and 17.5 min before and after the estimated closest point of approach (CPA) for each ship. Results showed a 36% decrease in the number of detectable clicks as a ship approaches when comparing clicks detected at intervals of both 35 minutes before and 17 minutes before the CPA; additionally, 22% fewer clicks were counted 30 min after the ship than 30 min before (results significant at the P=0.01 level). These results indicate a potential change in sperm whale behavior when exposed to large class size vessel traffic (e.g. tankers and container ships) from major shipping lanes. Recommendations for addressing this issue are discussed.

Azzara, Alyson

2012-05-01T23:59:59.000Z

225

USING AN ADAPTER TO PERFORM THE CHALFANT-STYLE CONTAINMENT VESSEL PERIODIC MAINTENANCE LEAK RATE TEST  

Science Conference Proceedings (OSTI)

Recently the Packaging Technology and Pressurized Systems (PT&PS) organization at the Savannah River National Laboratory was asked to develop an adapter for performing the leak-rate test of a Chalfant-style containment vessel. The PT&PS organization collaborated with designers at the Department of Energy's Pantex Plant to develop the adapter currently in use for performing the leak-rate testing on the containment vessels. This paper will give the history of leak-rate testing of the Chalfant-style containment vessels, discuss the design concept for the adapter, give an overview of the design, and will present results of the testing done using the adapter.

Loftin, B.; Abramczyk, G.; Trapp, D.

2011-06-03T23:59:59.000Z

226

Agile Research  

E-Print Network (OSTI)

This paper discusses the application of agile software development methods in software-based research environments.

Cunningham, Hamish

2012-01-01T23:59:59.000Z

227

Research Highlights  

NLE Websites -- All DOE Office Websites (Extended Search)

Highlights Highlights Form Submit a New Research Highlight Sort Highlights Submitter Title Research Area Working Group Submission Date DOE Progress Reports Notable Research Findings for 2001-2006 Biological and Environmental Research Abstracts Database Research Highlights Summaries Research Highlights Members of ARM's science team are major contributors to radiation and cloud research. ARM investigators publish about 150 refereed journal articles per year, and ARM data are used in many studies published by other scientific organizations. These documented research efforts represent tangible evidence of ARM's contribution to advances in almost all areas of atmospheric radiation and cloud research. Below is a selection of summaries highlighting recently-published ARM research. The entire collection of ARM

228

Fast neutron fluence of yonggwang nuclear unit 1 reactor pressure vessel  

Science Conference Proceedings (OSTI)

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)

Yoo, C.; Km, B.; Chang, K.; Leeand, S. [Korea Atomic Energy Research Inst., 150 Dukjin-dong, Yuseung-gu, Daejeon 305-353 (Korea, Republic of); Park, J. [Chungnam National Univ., 220 Gung-dong, Yuseung-gu, Daejeon 305-764 (Korea, Republic of)

2006-07-01T23:59:59.000Z

229

Potential market for LNG-fueled marine vessels in the United States  

E-Print Network (OSTI)

The growing global concern over ship emissions in recent years has driven policy change at the international level toward more stringent vessel emissions standards. The policy change has also been an impetus for innovation ...

Brett, Bridget C

2008-01-01T23:59:59.000Z

230

Substantiation of Thermodynamic Criteria of Explosion Safety in Process of Severe Accidents in Pressure Vessel Reactors  

E-Print Network (OSTI)

The paper represents original development of thermodynamic criteria of occurrence conditions of steam-gas explosions in the process of severe accidents. The received results can be used for modelling of processes of severe accidents in pressure vessel reactors.

Skalozubov, V I; Jarovoj, S S; Kochnyeva, V Yu

2012-01-01T23:59:59.000Z

231

Substantiation of Thermodynamic Criteria of Explosion Safety in Process of Severe Accidents in Pressure Vessel Reactors  

E-Print Network (OSTI)

The paper represents original development of thermodynamic criteria of occurrence conditions of steam-gas explosions in the process of severe accidents. The received results can be used for modelling of processes of severe accidents in pressure vessel reactors.

V. I. Skalozubov; V. N. Vashchenko; S. S. Jarovoj; V. Yu. Kochnyeva

2012-03-27T23:59:59.000Z

232

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

NLE Websites -- All DOE Office Websites (Extended Search)

Pipeline and Pressure Vessel R&D under the Hydrogen Regional Infrastructure Program In Pennsylvania Kevin L. Klug, Ph.D. 25 September 2007 DOE Hydrogen Pipeline Working Group...

233

In-Situ Repairs of Oil Industry Pipelines, Tanks and Vessels by ...  

Science Conference Proceedings (OSTI)

Abstract Scope, Metal arc welding under oil (MAW-UO) is a new, revolutionary process to repair a pipeline, tank or vessel by welding in case of flaws and...

234

Nonlinear response of vessel walls due to short-time thermomechanical loading  

Science Conference Proceedings (OSTI)

Maintaining structural integrity of the reactor pressure vessel (RPV) during a postulated core melt accident is an important safety consideration in the design of the vessel. This study addresses the failure predictions of the vessel due to thermal and pressure loadings fro the molten core debris depositing on the lower head of the vessel. Different loading combinations were considered based on the dead load, yield stress assumptions, material response and internal pressurization. The analyses considered only short term failure (quasi static) modes, long term failure modes were not considered. Short term failure modes include plastic instabilities of the structure and failure due to exceeding the failure strain. Long term failure odes would be caused by creep rupture that leads to plastic instability of the structure. Due to the sort time durations analyzed, creep was not considered in the analyses presented.

Pfeiffer, P.A.; Kulak, R.F.

1994-06-01T23:59:59.000Z

235

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

DOE Patents (OSTI)

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

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

1997-01-01T23:59:59.000Z

236

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

E-Print Network (OSTI)

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 ...

Fuquen-Molano, Rosendo

1982-01-01T23:59:59.000Z

237

A Small, Low Flow, High Sensitivity Reaction Vessel for NO Chemiluminescence Detectors  

Science Conference Proceedings (OSTI)

Details of a reaction vessel suitable for atmospheric measurements of nitric oxide at parts per trillion mixing ratios using the chemiluminescent reaction with ozone are provided. It is designed to operate at an ambient air flow of 1 standard ...

B. A. Ridley; F. E. Grahek

1990-04-01T23:59:59.000Z

238

CO/sub 2/ welding used to attach inspection manway to NASA hydrogen pressure vessel  

SciTech Connect

Welding of inspection manway for internal survey of a gaseous hydrogen storage vessel is described. Pre-welding activities are reviewed, along with welding operations, and in-process welding control. (JRD)

Palmer, G.; Conklin, D.

1976-09-01T23:59:59.000Z

239

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

DOE Patents (OSTI)

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

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

1997-12-16T23:59:59.000Z

240

An accurate model for seaworthy container vessel stowage planning with ballast tanks  

Science Conference Proceedings (OSTI)

Seaworthy container vessel stowage plans generated under realistic assumptions are a key factor for stowage decision support systems in the shipping industry. We propose a linear model with ballast tanks for generating master plans, the first phase of ...

Dario Pacino; Alberto Delgado; Rune Mller Jensen; Tom Bebbington

2012-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "research vessel mirai" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

Guidelines for Managing Reactor Vessel Material Uncertainties: Part 1: General Approach Part 2: Implementation Guide  

Science Conference Proceedings (OSTI)

Uncertainties about reactor vessel material toughness properties can be a concern for utilities when characterizing vessel integrity. In addition, recent emphasis on variability in material chemistry and initial toughness properties has added to regulatory concerns. This two-part guidelines document provides a general approach (Part 1) for dealing with weld metal property variability and material uncertainties and demonstrates examples of different approaches (Part 2) for dealing with these uncertainties...

1997-04-30T23:59:59.000Z

242

BWRVIP-160: BWR Vessel and Internals Project, BWRVIP Inspection Trends, 2006 Update  

Science Conference Proceedings (OSTI)

The BWR Vessel and Internals Project (BWRVIP) is an association of utilities focused exclusively on boiling water reactor (BWR) vessel and internals issues. As a group, the utilities have developed a set of guidelines that recommend inspecting specific BWR internal components. Results of these inspections are reported to EPRI where they are compiled and made available to all member utilities. This report documents results of inspections performed between approximately 1996 and early 2006.

2006-10-03T23:59:59.000Z

243

BWRVIP-198: BWR Vessel and Internals Project, BWRVIP Inspection Trends, 2008 Update  

Science Conference Proceedings (OSTI)

The BWR Vessel and Internals Project (BWRVIP) is an association of utilities focused exclusively on boiling water reactor (BWR) vessel and internals issues. As a group, the utilities have developed a set of guidelines that recommend inspecting specific BWR internal components. Results of these inspections are reported to EPRI where they are compiled and made available to all member utilities. This report documents results of inspections performed between approximately 1996 and spring of 2008.

2008-10-16T23:59:59.000Z

244

BWRVIP-242: BWR Vessel and Internals Project, BWRVIP Inspection Trends, 2010 Update  

Science Conference Proceedings (OSTI)

The BWR Vessel and Internals Project (BWRVIP) is an association of utilities focused exclusively on boiling water reactor (BWR) vessel and internals issues. As a group, the utilities have developed a set of guidelines that recommend inspecting specific BWR internal components. Results of these inspections are reported to EPRI where they are compiled and made available to all member utilities. This report documents results of inspections performed between approximately 1996 and spring of 2010.

2010-12-07T23:59:59.000Z

245

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

SciTech Connect

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.

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

2010-07-01T23:59:59.000Z

246

BWRVIP-277: BWR Vessel and Internals Project, Nondestructive Evaluation Development 2013  

Science Conference Proceedings (OSTI)

This report describes the results of nondestructive evaluation (NDE) activities conducted in the previous year within the NDE development task of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Inspection Focus Group. The scope of the ongoing task includes the reactor vessel and its internal components. This task attempts to develop solutions for the more difficult inspections recommended by the BWRVIP, to determine limitations to inspection capability, and sometimes to demonstrate ...

2013-11-27T23:59:59.000Z

247

NREL: Biomass Research - Research Staff  

NLE Websites -- All DOE Office Websites (Extended Search)

Research Staff Research Staff NREL's biomass research staff includes: Management team Technology and research areas Research support areas. Search the NREL staff directory to contact any of the research staff listed below. Management Team The biomass management team is composed of: Thomas Foust, National Bioenergy Center Director Robert Baldwin, Principal Scientist, Thermochemical Conversion Phil Pienkos, Applied Science Principal Group Manager Kim Magrini, Catalysis and Thermochemical Sciences and Engineering R&D Principal Group Manager Jim McMillan, Biochemical Process R&D Principal Group Manager Rich Bain, Principal Engineer, Thermochemical Sciences Mark Davis, Thermochemical Platform Lead Richard Elander, Biochemical Platform Lead Dan Blake, Emeritus Back to Top Technology and Research Areas

248

RESEARCH TITLES  

Science Conference Proceedings (OSTI)

... Wilmington 35 Eidgenssische Technische Hochschule, Switzerland 36 Emory University School of Medicine 37 ExxonMobil Research and ...

2001-02-27T23:59:59.000Z

249

In-Vessel Retention of Molten Core Debris in the Westinghouse AP1000 Advanced Passive PWR  

SciTech Connect

In-vessel retention (IVR) of molten core debris via external reactor vessel cooling is the hallmark of the severe accident management strategies in the AP600 passive PWR. The vessel is submerged in water to cool its external surface via nucleate boiling heat transfer. An engineered flow path through the reactor vessel insulation provides cooling water to the vessel surface and vents steam to promote IVR. For the 600 MWe passive plant, the predicted heat load from molten debris to the lower head wall has a large margin to the critical heat flux on the external surface of the vessel, which is the upper limit of the cooling capability. Up-rating the power of the passive plant from 600 to 1000 MWe (AP1000) significantly increases the heat loading from the molten debris to the reactor vessel lower head in the postulated bounding severe accident sequence. To maintain a large margin to the coolability limit for the AP1000, design features and severe accident management (SAM) strategies to increase the critical heat flux on the external surface of the vessel wall need to be implemented. A test program at the ULPU facility at University of California Santa Barbara (UCSB) has been initiated to investigate design features and SAM strategies that can enhance the critical heat flux. Results from ULPU Configuration IV demonstrate that with small changes to the ex-vessel design and SAM strategies, the peak critical heat flux in the AP1000 can be increased at least 30% over the peak critical heat flux predicted for the AP600 configuration. The design and SAM strategy changes investigated in ULPU Configuration IV can be implemented in the AP1000 design and will allow the passive plant to maintain the margin to critical heat flux for IVR, even at the higher power level. Continued testing for IVR phenomena is being performed at UCSB to optimize the AP1000 design and to ensure that vessel failure in a severe accident is physically unreasonable. (authors)

Scobel, James H.; Conway, L.E. [Westinghouse Electric Company LLC, P.O. Box 355, Pittsburgh, PA 15230-0355 (United States); Theofanous, T.G. [Center for Risk Studies and Safety, University of California Santa Barbara (United States)

2002-07-01T23:59:59.000Z

250

Neuroimaging Research  

NLE Websites -- All DOE Office Websites (Extended Search)

Neuroimaging Research Neuroimaging Research (NIAAA Intramural & NIH) Neuroimaging research at Brookhaven is a prime example of transdisciplinary research where the expertise of chemists, physicists, and biological and medical scientists blend to apply new imaging tools to problems in human health. Brookhaven has a network of complementary brain-imaging tools: PET Positron Emission Tomography (PET) Micro MRI MicroMRI Awake Animal Imaging Awake Animal Imaging Using these imaging tools, human neuroscience research has focused on understanding how the brain effects, and is affected by: obesity and eating disorders ADHD depression Behavioral Pharmacology and Neuroimaging, and Neuropsychoimaging enrich investigations of the relationships between brain chemistry and behavior. Top of Page

251

Research departments Materials Research Department  

E-Print Network (OSTI)

research reactor and X- radiation from the synchrotron facilities in Hamburg and Grenoble. In this con- nection, work is carried out on develop- ing advanced methods, as well as theory and computer simulation numerical simulation. Nuclear Safety Research and Facilities Department The department carries out research

252

US EPR Tests Performed to confirm the Mechanical and Hydraulic Design of the Vessel Internals  

SciTech Connect

The EPR is an Evolutionary high-Power Reactor which is based on the best French and German experience of the past twenty years in plant design construction and operation. In the present detailed engineering phase of the plant under construction in Finland (Okiluoto 3) or scheduled in France (Flamanville 3), a few actions are still ongoing mainly to complement equipment validation files. Design and validation of the main EPR components were performed within Framatome ANP's engineering teams and its two Technical Centers located in France and Germany, which develop state of the art methods in the field of thermo hydraulic testing. The Reactor Pressure Vessel internals are mainly derived from components already implemented on presently operating plants, but they differ in some features from the design used in French N4 or German Konvoi. The aim of this paper is to present the tests performed to confirm the hydraulic and mechanical design of the EPR vessel internals. - Four different mock-ups are presented to illustrate these tests: - JULIETTE for the reactor pressure vessel lower internals; - ROMEO for the reactor pressure vessel upper internals; - MAGALY for the design of the skeleton-type control rod guide assembly; - HYDRAVIB for the vibratory response of the reactor pressure vessel lowers internals. (authors)

Dolleans, Philippe; Chambrin, Jean-Luc; Muller, Thierry [FRAMATOME ANP, Tour AREVA 1 place de la Coupole, 92084 PARIS La D ense (France)

2006-07-01T23:59:59.000Z

253

Thermal energy storage using Prestressed Cast Iron Vessels (PCIV). Final report  

DOE Green Energy (OSTI)

The wide-spread application of thermal energy and high-pressure air storage to electric power generation has so far been hampered by the lack of large high-pressure storage vessels of reasonable cost. Welded steel vessels are too expensive for this purpose. However, the Prestressed Cast Iron Vessel (PCIV), developed as a nuclear reactor pressure vessel by Siempelkamp Giesserei KG of Krefeld, FRG, has the potential of complying with these requirements. Applications of the PCIV include: high-pressure air storage for the quick start-up of open cycle gas turbines; pressurized high-temperature sensible heat storage by means of solids with a gaseous heat transfer medium for closed cycle gas turbines of future solar power stations; and pressurized hot water storage for nuclear, solar, or coal-fired steam power plants, employing either separate peaking turbines or overloadable main turbine sets. A reference PCIV of 8000 m/sup 3/, 275/sup 0/C, with hot going walls and cold going tendons was developed, designed, and stress-analysed. A parametric study showed that pressures between 4 and 8 MPa and L/D ratios larger than 4 should be optimal. Cost of the reference vessel is about $10,000,000 or 33 to 50 $/kWh electric energy stored. Cost of peak power will be from 30 to 100 mills/kWh, depending on many parameters.

Gilli, P.V.; Beckmann, G.; Schilling, F.E.

1977-06-01T23:59:59.000Z

254

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

Science Conference Proceedings (OSTI)

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.

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

2008-03-01T23:59:59.000Z

255

Research Statement  

E-Print Network (OSTI)

My research is in the area of network control and management, with a research goal of improving the robustness and manageability of networked systems, and contributing to the design of future network architectures. Benefiting from my cross-disciplinary background in electrical engineering, telecommunications, and computer science, I try to bring a comprehensive viewpoint in my contributions to networking research. My vision is to facilitate the design of networks that are scalable, evolvable, and can work smartly with minimal human involvement.

Hammad Iqbal

2009-01-01T23:59:59.000Z

256

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

Secondary Organic Aerosol (SOA) and Sulfate Download a printable PDF Submitter: Martin, S. T., Harvard University Area of Research: Aerosol Properties Working Group(s):...

257

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

K-Distribution Method for a SW Radiative Transfer Model Submitter: Ackerman, T. P., University of Washington Area of Research: General Circulation and Single Column Models...

258

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

Status and Analysis Results: 1998 Submitter: Revercomb, H. E., University of Wisconsin, Madison Area of Research: Radiation Processes Working Group(s): Radiative Processes...

259

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

A., Pacific Northwest National Laboratory Area of Research: Atmospheric Thermodynamics and Vertical Structures Working Group(s): Cloud Life Cycle Journal Reference:...

260

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

A., Pacific Northwest National Laboratory Area of Research: Atmospheric Thermodynamics and Vertical Structures Working Group(s): Cloud-Aerosol-Precipitation Interactions...

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261

Operations Research  

E-Print Network (OSTI)

Mar 1, 2005 ... Operations Research. Report 2005-01. On a closedness theorem. Mikls Ujvri. Marc 2005. Etvs Lornd University of Sciences. Department...

262

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

of Energy (DOE) Atmospheric Radiation Measurement (ARM) Program, U.S. Department of Agriculture (USDA) UV-B Monitoring and Research Program, National Oceanic and Atmospheric...

263

UNIRIB: Research  

NLE Websites -- All DOE Office Websites (Extended Search)

mission focus of the University Radioactive Ion Beam (UNIRIB) consortium is to perform nuclear physics research, and provide training and education. UNIRIB member universities...

264

PNNL: Research  

NLE Websites -- All DOE Office Websites (Extended Search)

by PNNL and researchers from the University of Washington and Oregon Health & Science University shows how using a relatively simple method for engineering nanoparticle...

265

PNNL: Research  

NLE Websites -- All DOE Office Websites (Extended Search)

To achieve higher power levels, researchers now are turning their attention to advanced fuel designs. PNNL is developing a new metal fuel for light water reactors intended...

266

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

Small Ice Crystals on Ice Sedimentation Rates in Cirrus Clouds and GCM Simulations Download a printable PDF Submitter: Mitchell, D. L., Desert Research Institute Rasch, P., Pacific...

267

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

Predicting Arctic Sea Ice Loss Download a printable PDF Submitter: Liu, X., University of Wyoming Area of Research: Cloud-Aerosol-Precipitation Interactions Working Group(s):...

268

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

Characterizing the Co-Existence of Water and Ice in Arctic Clouds Submitter: McFarquhar, G., University of Illinois, Urbana Area of Research: Cloud DistributionsCharacterizations...

269

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

Nailing Down Ice in a Cloud Model Download a printable PDF Submitter: Comstock, J. M., Pacific Northwest National Laboratory Area of Research: Cloud Processes Working Group(s):...

270

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

On Thin Ice: Retrieval Algorithms for Ice Clouds Examined for Improvements Submitter: Comstock, J. M., Pacific Northwest National Laboratory Area of Research: Cloud Distributions...

271

Research Projects  

NLE Websites -- All DOE Office Websites (Extended Search)

Beam Physics to simulate a next generation light sources based on x-ray free electron lasers. My research includes: Designing parallel algorithms for numerical optimization....

272

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

The Brass Ring of Climate Modeling Download a printable PDF Submitter: Ghan, S. J., Pacific Northwest National Laboratory Area of Research: Aerosol Processes Working Group(s):...

273

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

Into Radiative Transfer in Cloudy Conditions Submitter: Min, Q., State University of New York, Albany Area of Research: Cloud DistributionsCharacterizations Working Group(s):...

274

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

Altering Cloud Microphysics and Precipitation Submitter: Min, Q., State University of New York, Albany Area of Research: Aerosol Properties Working Group(s): Aerosol Journal...

275

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

Pollution + Storm Clouds Warmer Atmosphere Download a printable PDF Submitter: Fan, J., Pacific Northwest National Laboratory Area of Research: Cloud-Aerosol-Precipitation...

276

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

ARM-Funded Algorithms Lead to Marked Improvements in Global Weather Forecast Model Submitter: Morcrette, J. J., European Centre for Medium-Range Weather Forecasts Area of Research:...

277

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

Many Forecast Errors Are Climate Errors Download a printable PDF Submitter: Xie, S., Lawrence Livermore National Laboratory Area of Research: General Circulation and Single Column...

278

PNNL: Research  

NLE Websites -- All DOE Office Websites (Extended Search)

Cutting Air Pollution Got Boost from Weather Cutting Air Pollution Got Boost from Weather View full sized image New research suggests that China's impressive feat of cutting...

279

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

Black Carbon Aerosols and the Third Polar Ice Cap Submitter: Menon, S., Lawrence Berkeley National Laboratory Area of Research: General Circulation and Single Column Models...

280

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

Effects of Relative Humidity on Aerosols-Implications for Climate Submitter: Lacis, A. A., NASA - Goddard Institute for Space Studies Area of Research: Aerosol Properties Working...

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281

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

Chemical Diffusivity and Viscosity of Secondary Organic Aerosols Download a printable PDF Submitter: Zelenyuk-Imre, A., Pacific Northwest National Laboratory Area of Research:...

282

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

A Dance of Aerosols Download a printable PDF Submitter: Song, C., Pacific Northwest National Laboratory Area of Research: Aerosol Processes Working Group(s): Aerosol Life Cycle...

283

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

Characterization of Atmospheric Aerosols Using MFRSR Measurements Download a printable PDF Submitter: Alexandrov, M. D., Columbia University Area of Research: Aerosol Properties...

284

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

Scientists then measured how the particles were distributed in the vapor using a mobility scanner that determined particle sizes. In the other approach, researchers...

285

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

Contributor to Low-Level Cloud Reflectivity Submitter: Penner, J. E., University of Michigan Area of Research: Aerosol Properties Working Group(s): Aerosol Journal Reference:...

286

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

Stratocumulus Clouds Download a printable PDF Submitter: Penner, J. E., University of Michigan Lee, S., University of Michigan Area of Research: Aerosol Properties Working...

287

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

and validation of a black carbon mixing state resolved three-dimensional model: Aging processes and radiative impact." Journal of Geophysical Research - Atmospheres, ,...

288

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

Arctic Clouds Download a printable PDF Submitter: Earle, M., Environment Canada Liu, P., Environment Canada Area of Research: Cloud DistributionsCharacterizations...

289

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

Cloud Boundary Detection and Analysis from Micro Pulse Lidar Submitter: Spinhirne, J., University of Arizona Area of Research: Cloud DistributionsCharacterizations Working...

290

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

Mexico City Carbon-Containing Particle Composition Simulated Download a printable PDF Submitter: Zaveri, R., Pacific Northwest National Laboratory Area of Research: Radiation...

291

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

Research Facility sites. For many years now, vertically pointing ARM instruments in Oklahoma, Alaska, and Manus Island in the Pacific Ocean (in Papua New Guinea) have...

292

BWRVIP-265: BWR Vessel and Internals Project, Crack Growth in High Fluence BWR Materials-Phase 2  

Science Conference Proceedings (OSTI)

The Boiling Water Reactor Vessel and Internals Project (BWRVIP) has developed a methodology to evaluate crack growth rates (CGR) in irradiated stainless steel components in the BWR vessel. This methodology is documented in BWRVIP-99-A: BWR Vessel and Internals Project, Crack Growth Rates in Irradiated Stainless Steels in BWR Internal Components (EPRI report 1016566), and is applicable to neutron doses of 0.7 to 4.2 displacements per atom (dpa) (5x1020 to 3x1021 ...

2012-11-14T23:59:59.000Z

293

BWRVIP-270, Revision 1: BWR Vessel and Internals Project, Compilation of Fluence Estimates for Boiling Water Reactor Materials  

Science Conference Proceedings (OSTI)

The Boiling Water Reactor Vessel and Internals Project (BWRVIP) is an association of utilities focused on BWR vessel and internals issues. Many of the BWR internal components receive high exposure to neutron flux due to their proximity to the fuel in the Reactor Pressure Vessel (RPV). Identifying how predicted fluence values will impact the materials at these locations is a focus of the BWRVIP proactive materials strategy. As part of this approach, this report provides visual and tabular summaries ...

2013-12-09T23:59:59.000Z

294

Research Highlights | ORNL Neutron Sciences  

NLE Websites -- All DOE Office Websites (Extended Search)

Coal Pores: Greenhouse Gases and Coal Pores: Greenhouse Gases and Methane Energy and Environmental Solutions Under Our Feet Mix of neutron scattering techniques helps resolve critical problems of confining greenhouse gases and extracting methane Research Contact: Yuri Melnichenko August 2011, Written by Agatha Bardoel Yuri Melnichenko at the GPSANS instrument GP-SANS instrument scientist Yuri Melnichenko (left) and postdoctoral associate Lilin He. When you heat water in a kettle, you can make tea or coffee. But what happens if the vessel is sealed? Ultimately, at a temperature called the liquid-gas critical point, the density of the liquid and the vapor become identical: There is no more water, there is no more gas. What you have is a supercritical fluid. The phenomenon of liquid-liquid and liquid-gas coexistence was a

295

Operations research  

Science Conference Proceedings (OSTI)

In Evita, Andrew Lloyd Webber and Tim Rice wrote: Politics, the Art of the Possible. To those of us in the operations research community, we postulate: Operations Research, the Science of Better - (i.e. better processes, better systems and better decisions). ...

William P. Pierskalla

2009-01-01T23:59:59.000Z

296

NREL: Wind Research - Research Staff  

NLE Websites -- All DOE Office Websites (Extended Search)

Research Staff Research Staff Here you will find contact information for NREL's research and support staff at the National Wind Technology Center. To learn more about us and our expertise, view our organizational charts and read the staff's biographies. Below is a listing of the research and support staff at the National Wind Technology Center. View organizational charts. Lab Program Manager, Wind and Water Power Program Brian Smith Program Integration, Wind and Water Power Program Elise DeGeorge Albert LiVecchi Dana Scholbrock Teresa Thadison Director, National Wind Technology Center Fort Felker, Center Director Laura Davis Kim Domenico Deputy Center Director, National Wind Technology Center Jim Green, Acting Research Fellow Bob Thresher Chief Engineer Paul Veers Wind Technology Research and Development

297

Comparison of ALICE-II code predictions with SRI complex vessel experiments  

Science Conference Proceedings (OSTI)

Several complex vessel experiments on 1/20-scale models of the Clinch River Breeder Reactor Project (CRBR) were performed by SRI International to help evaluate the containment structural integrity subjected to HCDAs. Among these experiments SM-3 is a simple model which consists of a radial shield, core barrel, upper internal structure (UIS), and a primary vessel. Tests SM-4 and SM-5 are more complex models than SM-3. This paper presents comparisons of the ALICE-II code (Arbitrary Lagrangian Implicit-explicit Continuous Fluid Eulerian containment code - second version) with experiments SM-3 through SM-5. Two calculations are performed with ALICE-II on each of these three experiments, using both the pressure-time histories (p-t) and the pressure-volume relationships (p-v) as input to describe the energy source. Pressure profiles, dynamic strains, and vessel deformations are used as the basis of the comparison.

Ku, J.L.; Wang, C.Y.; Zeuch, W.R.

1983-01-01T23:59:59.000Z

298

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

Lord of the Wings: Elevated Particles a Rising Star Lord of the Wings: Elevated Particles a Rising Star Download a printable PDF Submitter: Kassianov, E., Pacific Northwest National Laboratory Area of Research: Radiation Processes Working Group(s): Aerosol Life Cycle Journal Reference: Kassianov E, C Flynn, J Redemann, B Schmid, PB Russell, and A Sinyuk. 2012. "Initial assessment of the Spectrometer for Sky-Scanning, Sun-Tracking Atmospheric Research (4STAR)-based aerosol retrieval: Sensitivity study." Atmosphere, 3, doi:10.3390/atmos3040495. The 4STAR instrument. The 4STAR instrument (inset) is installed through the upper hull of the PNNL G-1 research aircraft, for in-flight sun-tracking and sky light-scanning. Researchers at Pacific Northwest National Laboratory, in collaboration with colleagues at NASA Ames Research Center, developed a next-generation

299

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

Improved Daytime Precipitable Water Vapor from Vaisala Radiosonde Humidity Improved Daytime Precipitable Water Vapor from Vaisala Radiosonde Humidity Sensors Download a printable PDF Submitter: Cady-Pereira, K. E., Atmospheric and Environmental Research, Inc. Mlawer, E. J., Atmospheric & Environmental Research, Inc. Turner, D. D., National Oceanic and Atmospheric Administration Shephard, M. W., Atmospheric and Environmental Research, Inc. Clough, S. A., Atmospheric and Environmental Research, Inc. Area of Research: Atmospheric Thermodynamics and Vertical Structures Working Group(s): Radiative Processes Journal Reference: Cady-Pereira, K, M Shephard, E Mlawer, D Turner, S Clough, and T Wagner. 2008. "Improved daytime column-integrated precipitable water vapor from Vaisala radiosonde humidity sensors." Journal of Atmospheric and Oceanic Technology doi: 10.1175/2007JTECHA1027.1.

300

Research projects  

NLE Websites -- All DOE Office Websites (Extended Search)

Yuan » Research projects Yuan » Research projects Research projects Research Interests Scientific computing, domain decomposition methods Linear solvers for sparse matrices Computational plasma physics Grid generation techniques GPU computing Current Research PDSLin: A hybrid linear solver for large-scale highly-indefinite linear systems The Parallel Domain decomposition Schur complement based Linear solver (PDSLin), which implements a hybrid (direct and iterative) linear solver based on a non-overlapping domain decomposition technique called chur complement method, and it has two levels of parallelism: a) to solve independent subdomains in parallel and b) to apply multiple processors per subdomain. In such a framework, load imbalance and excessive communication lead to the performance bottlenecks, and several techniques are developed

Note: This page contains sample records for the topic "research vessel mirai" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
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301

Basic Research  

NLE Websites -- All DOE Office Websites (Extended Search)

5 5 II Basic Research The Basic Energy Sciences (BES) office within the DOE Office of Science supports the DOE Hydrogen Program by providing basic, fundamental research in those technically challenging areas facing the Program, complementing the applied research and demonstration projects conducted by the Offices of Energy Efficiency and Renewable Energy; Fossil Energy; and Nuclear Engineering, Science and Technology. In May 2005 Secretary of Energy Samuel W. Bodman announced the selection of over $64 million in BES research and development projects aimed at making hydrogen fuel cell vehicles and refueling stations available, practical and affordable for American consumers by 2020. A total of 70 hydrogen research projects were selected to focus on fundamental science and enable

302

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

Science Conference Proceedings (OSTI)

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

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

2010-03-07T23:59:59.000Z

303

MAGNESIUM MONO POTASSIUM PHOSPHATE GROUT FOR P-REACTOR VESSEL IN-SITU DECOMISSIONING  

Science Conference Proceedings (OSTI)

The objective of this report is to document laboratory testing of magnesium mono potassium phosphate grouts for P-Reactor vessel in-situ decommissioning. Magnesium mono potassium phosphate cement-based grout was identified as candidate material for filling (physically stabilizing) the 105-P Reactor vessel (RV) because it is less alkaline than portland cement-based grout (pH of about 12.4). A less alkaline material ({ash), and (4) Ceramicrete{reg_sign} magnesium mono potassium phosphate-based grouts prepared at Argonne National Laboratory. Boric acid was evaluated as a set retarder in the magnesium mono potassium phosphate mixes.

Langton, C.; Stefanko, D.

2011-01-05T23:59:59.000Z

304

BWRVIP-53-A: BWR Vessel and lnternals Project, Standby Liquid Control Line Repair Design Criteria  

Science Conference Proceedings (OSTI)

The Boiling Water Reactor Vessel and Internals Project (BWRVIP), formed in June, 1994, is an association of utilities focused exclusively on BWR vessel and internals issues. This BWRVIP report documents criteria which can be used to design a repair for the standby liquid control (SLC) line in a BWR. A previous version of this report was published as BWRVIP-53 (TR-108716). This report (BWRVIP-53- A) incorporates changes proposed by the BWRVIP in response to U.S. Nuclear Regulatory Commission (NRC) Request...

2005-09-07T23:59:59.000Z

305

Protective interior wall and attach8ing means for a fusion reactor vacuum vessel  

DOE Patents (OSTI)

An array of connected plates mounted on the inside wall of the vacuum vessel of a magnetic confinement reactor in order to provide a protective surface for energy deposition inside the vessel. All fasteners are concealed and protected beneath the plates, while the plates themselves share common mounting points. The entire array is installed with torqued nuts on threaded studs; provision also exists for thermal expansion by mounting each plate with two of its four mounts captured in an oversize grooved spool. A spool-washer mounting hardware allows one edge of a protective plate to be torqued while the other side remains loose, by simply inverting the spool-washer hardware.

Phelps, Richard D. (Greeley, CO); Upham, Gerald A. (Valley Center, CA); Anderson, Paul M. (San Diego, CA)

1988-01-01T23:59:59.000Z

306

Structural integrity of vessels for coal conversion systems. [ASME and ANSI codes  

DOE Green Energy (OSTI)

The integrity of a coal conversion system need not be compromised by material considerations in design or fabrication. The ASME and ANSI Codes assure the structural integrity of the large pressure vessels and piping when they are placed into service. Imposing additional requirements, such as increased impact toughness, will further assure the reliability and safety of the Code-fabricated vessel. Incorporating in-service surveillance as part of the operational plan will ensure the integrity of the pressure-containing components for the anticipated service life.

Canonico, D.A.

1979-09-01T23:59:59.000Z

307

The dissolution vessel for plutonium pits at the U.S. DOE Pantex Plant  

Science Conference Proceedings (OSTI)

The US DOE Pantex Plant has been given the mission to recertify and requalify plutonium pits for reuse in existing War Reserve nuclear weapons. The first process common to both recertification and requalification is cleaning the plutonium pit. The pit will be cleaned in a dissolution vessel using N-methyl pyrrolidone (NMP) solvent. The recertification and requalification programs are both in the design concept phase at Pantex Plant. The US DOE Pantex Plant secures the national security of the United States by using safe vessels for cleaning plutonium pits in a manner that protects the health and safety of employees, the public and the environment.

Eifert, E.J.; Vickers, L.D.

2000-02-01T23:59:59.000Z

308

Tank vessels transferring Outer Continental Shelf (OCS) oil proposed design and equipment standards  

SciTech Connect

The US Coast Guard proposes to require US and foreign flag tank vessels engaged in the transfer of OCS oil in bulk as cargo from an offshore oil exploitation or production facility to shore to have segregated ballast tanks, dedicated clean ballast tanks, or special ballast arrangements by 6/1/80. This proposal would implement the Port and Tanker Safety Act of 1978 and would eliminate the mixing of ballast water and oil, thus reducing operational pollution that could occur if there was a substantial increase in vessel traffic. Comments must be received by 6/16/80.

1980-05-01T23:59:59.000Z

309

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

Science Conference Proceedings (OSTI)

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)

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)

2006-07-01T23:59:59.000Z

310

Research Areas  

NLE Websites -- All DOE Office Websites (Extended Search)

Research Areas Print Research Areas Print Scientists from a wide variety of fields come to the ALS to perform experiements. Listed below are some of the most common research areas covered by ALS beamlines. Below each heading are a few examples of the specific types of topics included in that category. Click on a heading to learn more about that research area at the ALS. Energy Science Photovoltaics, photosynthesis, biofuels, energy storage, combustion, catalysis, carbon capture/sequestration. Bioscience General biology, structural biology. Materials/Condensed Matter Correlated materials, nanomaterials, magnetism, polymers, semiconductors, water, advanced materials. Physics Atomic, molecular, and optical (AMO) physics; accelerator physics. Chemistry Surfaces/interfaces, catalysts, chemical dynamics (gas-phase chemistry), crystallography, physical chemistry.

311

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

ARM Program Achieves Milestone in Global Cloud Properties Research ARM Program Achieves Milestone in Global Cloud Properties Research Submitter: Revercomb, H. E., University of Wisconsin, Madison Area of Research: Radiation Processes Working Group(s): Radiative Processes Journal Reference: Knuteson, R.O., Best, F.A., Dedecker, R.G., Feltz, W.F., Revercomb, H.E., and Tobin, D.C., 2004: "10 Years of AERI Data from the DOE ARM Southern Great Plains Site," In Proceedings from the Fourteenth ARM Science Team Meeting, U.S. Department of Energy,Washington, D.C. Figure 1 Figure 2 From the unassuming farmlands of north-central Oklahoma comes a milestone for the global climate research community. March 2004 marked the 10-year anniversary for an instrument that now holds the prestigious distinction of providing the longest set of continuous atmospheric interferometer data

312

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

M., University of Colorado Area of Research: Cloud Processes Working Group(s): Cloud Life Cycle Journal Reference: Morrison H, G de Boer, G Feingold, J Harrington, M Shupe, and...

313

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

Del Genio, A. D., NASA Area of Research: Cloud Processes Working Group(s): Cloud Life Cycle Journal Reference: Del Genio AD, J Wu, and Y Chen. 2012. "Characteristics of...

314

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

How to Catch Aerosols in the Act Download a printable PDF Submitter: Wang, M., Pacific Northwest National Laboratory Area of Research: Cloud Processes Working Group(s): Cloud Life...

315

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

Ice Nucleation Link to Aerosols for Global Models Download a printable PDF Submitter: DeMott, P. J., Colorado State University Liu, X., University of Wyoming Area of Research:...

316

Advanced Research  

NLE Websites -- All DOE Office Websites (Extended Search)

05/2007 05/2007 NitrogeN evolutioN aNd CorrosioN MeChaNisMs With oxyCoMbustioN of Coal Description Under a grant from the University Coal Research (UCR) program, Brigham Young University (BYU) is leading a three-year research effort to investigate the physical processes that several common types of coal undergo during oxy-fuel combustion. Specifically, research addresses the mixture of gases emitted from burning, particularly such pollutants as nitrogen oxides (NO X ) and carbon dioxide (CO 2 ), and the potential for corrosion at the various stages of combustion. The UCR program is administered by the Advanced Research Program at the National Energy Technology Laboratory (NETL), under the U.S. Department of Energy's Office of

317

EERE Postdoctoral Research Awards: Research Topics  

NLE Websites -- All DOE Office Websites (Extended Search)

Topics to someone by E-mail Share EERE Postdoctoral Research Awards: Research Topics on Facebook Tweet about EERE Postdoctoral Research Awards: Research Topics on Twitter Bookmark...

318

EERE Postdoctoral Research Awards: Research Mentors  

NLE Websites -- All DOE Office Websites (Extended Search)

Mentors to someone by E-mail Share EERE Postdoctoral Research Awards: Research Mentors on Facebook Tweet about EERE Postdoctoral Research Awards: Research Mentors on Twitter...

319

EERE Postdoctoral Research Awards: Research Proposals  

NLE Websites -- All DOE Office Websites (Extended Search)

Proposals on Twitter Bookmark EERE Postdoctoral Research Awards: Research Proposals on Google Bookmark EERE Postdoctoral Research Awards: Research Proposals on Delicious Rank EERE...

320

Detection and characterization of indications in segments of reactor pressure vessels  

Science Conference Proceedings (OSTI)

Studies have been conducted to estimate flaw density in segments cut from light water reactor (LWR) pressure vessels as part of the Oak Ridge National Laboratory's Heavy-Section Steel Technology (HSST) Program. Segments from the Hope Creek Unit 2 vessel and the Pilgrim Unit 2 vessel were purchased from salvage dealers. Hope Creek was a boiling water reactor (BWR) design and Pilgrim was a pressurized water reactor (PWR) design. Neither were ever placed in service. Objectives were to evaluate these LWR segments for flaws with ultrasonic and liquid penetrant techniques and to compare the results with current assumptions related to probabilistic risk assessment. Both objectives were successfully completed. Ultrasonic techniques beyond those required by the 1986 edition of the ASME Boiler and Pressure Vessel Code were necessary for the detection and reporting of the detected discontinuities. Extra care and analysis must be exercised when conducting ultrasonic examination through cladding. The detection of the discontinuities in the arbitrarily selected sections implies that the Marshall report estimates (and others) are nonconservative for such small flaws. 8 refs., 9 figs.

Cook, K.V.; Cunningham, R.A. Jr.; McClung, R.W.

1989-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "research vessel mirai" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
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321

Vessel routing and scheduling under uncertainty in the liquefied natural gas business  

Science Conference Proceedings (OSTI)

Liquefied natural gas (LNG) is natural gas transformed into liquid state for the purpose of transportation mainly by specially built LNG vessels. This paper considers a real-life LNG ship routing and scheduling problem where a producer is responsible ... Keywords: Liquefied natural gas, Maritime transportation, Ship routing and scheduling, Simulation, Uncertainty

Elin E. Halvorsen-Weare; Kjetil Fagerholt; Mikael RNnqvist

2013-01-01T23:59:59.000Z

322

White Paper on Reactor Vessel Integrity Requirements for Level A and B Conditions  

Science Conference Proceedings (OSTI)

The ASME Section XI Task Group recommends that the Reactor Vessel Integrity Requirements of the ASME code be updated in several areas to reflect current technology. This report reviews current regulations to identify areas of conservatism and potential nonconservatism and to provide recommendations for future code improvements.

1993-03-09T23:59:59.000Z

323

Pressurized thermal shock probabilistic fracture mechanics sensitivity analysis for Yankee Rowe reactor pressure vessel  

SciTech Connect

The Nuclear Regulatory Commission (NRC) requested Oak Ridge National Laboratory (ORNL) to perform a pressurized-thermal-shock (PTS) probabilistic fracture mechanics (PFM) sensitivity analysis for the Yankee Rowe reactor pressure vessel, for the fluences corresponding to the end of operating cycle 22, using a specific small-break-loss- of-coolant transient as the loading condition. Regions of the vessel with distinguishing features were to be treated individually -- upper axial weld, lower axial weld, circumferential weld, upper plate spot welds, upper plate regions between the spot welds, lower plate spot welds, and the lower plate regions between the spot welds. The fracture analysis methods used in the analysis of through-clad surface flaws were those contained in the established OCA-P computer code, which was developed during the Integrated Pressurized Thermal Shock (IPTS) Program. The NRC request specified that the OCA-P code be enhanced for this study to also calculate the conditional probabilities of failure for subclad flaws and embedded flaws. The results of this sensitivity analysis provide the NRC with (1) data that could be used to assess the relative influence of a number of key input parameters in the Yankee Rowe PTS analysis and (2) data that can be used for readily determining the probability of vessel failure once a more accurate indication of vessel embrittlement becomes available. This report is designated as HSST report No. 117.

Dickson, T.L.; Cheverton, R.D.; Bryson, J.W.; Bass, B.R.; Shum, D.K.M.; Keeney, J.A. [Oak Ridge National Lab., TN (United States)

1993-08-01T23:59:59.000Z

324

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

E-Print Network (OSTI)

Pipeline and Pressure Vessel R&D under the Hydrogen Regional Infrastructure Program In Pennsylvania Kevin L. Klug, Ph.D. 25 September 2007 DOE Hydrogen Pipeline Working Group Meeting, Aiken, SCPerComp Engineering Inc. (HEI) ­ American Society Of Mechanical Engineers (ASME) ­ Pipeline Working Group (PWG) #12

325

Calvert Cliffs 1 Reactor Vessel: Pressurized Thermal Shock Analysis for a Small Steam Line Break  

Science Conference Proceedings (OSTI)

Analysis of this Maryland reactor revealed a wide safety margin in its two-loop Combustion Engineering PWR pressure vessel for transients caused by small steam line breaks. The study employed a new method for analyzing pressurized thermal shock effects that combines several EPRI computer codes.

1984-11-01T23:59:59.000Z

326

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

Science Conference Proceedings (OSTI)

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.

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

2012-10-01T23:59:59.000Z

327

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

SciTech Connect

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

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

2013-09-27T23:59:59.000Z

328

Fracture Toughness Characterization of Japanese Reactor Pressure Vessel Steels: Joint EPRI-CRIEPI RPV Embrittlement Studies  

Science Conference Proceedings (OSTI)

EPRI has examined five Japanese reactor pressure vessel steels to characterize the material properties over a complete temperature range, including the brittle/ductile transition region and the upper shelf typical of normal operation. The test results provide the unirradiated baseline needed for evaluating the effects of radiation embrittlement.

1993-07-01T23:59:59.000Z

329

Measurements of the hydrogenic recombination coefficient for the TFTR vacuum vessel  

DOE Green Energy (OSTI)

Characteristic values of the recombination rate coefficient for hydrogen and deuterium in stainless steel have been measured for the inner wall of the TFTR vacuum vessel for vessel temperatures of 25 to 100 C. In situ measurements of k/sub r/ are important for predicting the hydrogen isotope retention in the wall as a function of time, temperature, and discharge exposure, particularly because existing laboratory measurements of k/sub r/ for stainless steel span a range of four orders of magnitude. The measurement technique involved the observation of the decrease in hydrogen pressure during a glow discharge in the TFTR vacuum vessel with an initial static gas fill. The resulting values of k/sub r/ at 25 C are in the range of (0.4 to 4) x 10/sup -27/cm/sup 4/-s/sup -1/ assuming a value of the hydrogenic diffusivity of 2 x 10/sup -12/cm/sup 2/-s/sup -1/ at room temperature. No significant isotopic dependence was observed and the temperature dependence of k/sub r/ is consistent with the literature value (0.5 eV) of the activation energy. The implications of this range of values of k/sub r/, for the estimation of the in-vessel tritium inventory following D-T operation in TFTR are discussed.

Dylla, H.F.; Cecchi, J.L.; Knize, R.J.

1983-12-01T23:59:59.000Z

330

K West Basin Integrated Water Treatment System (IWTS) E-F Annular Filter Vessel Accident Calculations  

DOE Green Energy (OSTI)

Four bounding accidents postulated for the K West Basin integrated water treatment system are evaluated against applicable risk evaluation guidelines. The accidents are a spray leak during fuel retrieval, spray leak during backflushing a hydrogen explosion, and a fire breaching filter vessel and enclosure. Event trees and accident probabilities are estimated. In all cases, the unmitigated dose consequences are below the risk evaluation guidelines.

PIEPHO, M.G.

2000-01-10T23:59:59.000Z

331

BWRVIP-199: BWR Vessel and Internals Project, Testing and Evaluation of the Monticello 300 Degree Capsule  

Science Conference Proceedings (OSTI)

In the late 1990s, a BWR Vessel and Internals Project (BWRVIP) Integrated Surveillance Program (ISP) was developed to improve the surveillance of the U. S. BWR fleet. This report describes testing and evaluation of the Monticello 300 Capsule. These results will be used to monitor embrittlement as part of the BWRVIP ISP.

2008-12-03T23:59:59.000Z

332

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

E-Print Network (OSTI)

in this paper. Keywords: Remote inspection, Service robot, Non-destructive test, Nuclear, Climbing robotWalking 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

Chen, Sheng

333

Vessel centerline tracking in CTA and MRA images using hough transform  

Science Conference Proceedings (OSTI)

Vascular disease is characterized by any condition that affects the circulatory system. Recently, a demand for sophisticated software tools that can characterize the integrity and functional state of vascular networks from different vascular imaging ... Keywords: CTA, MRA, angiographic images, hough transform, lumen segmentation, vessel tracking

Maysa M. G. Macedo; Choukri Mekkaoui; Marcel P. Jackowski

2010-11-01T23:59:59.000Z

334

ITER Engineering Design Activities -R & DITER-In-Vessel Remote Handling  

E-Print Network (OSTI)

ITER Engineering Design Activities - R & DITER- In-Vessel Remote Handling Blanket Module Remote Handling Project (L-6) Divertor Remote Handling Project (L-7) Objective To develop and demonstrate handling equipment, port handling equipment, auxiliary remote handling tools and a blanket mockup structure

335

Test Results Using a Bell Jar to Measure Containment Vessel Pressurization  

SciTech Connect

A bell jar is used to determine containment vessel pressurization due to outgassing of plutonium materials. Fifteen food cans containing plutonium bearing materials, including plutonium packaged in direct contact with plastic and plutonium contaminated enriched oxide have been tested to date.

Hensel, S.J.

2002-05-10T23:59:59.000Z

336

MAGNESIUM MONO POTASSIUM PHOSPHATE GROUT FOR P-REACTOR VESSEL IN-SITU DECOMISSIONING  

SciTech Connect

The objective of this report is to document laboratory testing of magnesium mono potassium phosphate grouts for P-Reactor vessel in-situ decommissioning. Magnesium mono potassium phosphate cement-based grout was identified as candidate material for filling (physically stabilizing) the 105-P Reactor vessel (RV) because it is less alkaline than portland cement-based grout (pH of about 12.4). A less alkaline material ({<=} 10.5) was desired to address a potential materials compatibility issue caused by corrosion of aluminum metal in highly alkaline environments such as that encountered in portland cement grouts. Information concerning access points into the P-Reactor vessel and amount of aluminum metal in the vessel is provided elsewhere. Fresh and cured properties were measured for: (1) commercially blended magnesium mono potassium phosphate packaged grouts, (2) commercially available binders blended with inert fillers at SRNL, (3) grouts prepared from technical grade MgO and KH{sub 2}PO{sub 4} and inert fillers (quartz sands, Class F fly ash), and (4) Ceramicrete{reg_sign} magnesium mono potassium phosphate-based grouts prepared at Argonne National Laboratory. Boric acid was evaluated as a set retarder in the magnesium mono potassium phosphate mixes.

Langton, C.; Stefanko, D.

2011-01-05T23:59:59.000Z

337

BWRVIP-200: BWR Vessel and Internals Project, Implementation Plan for Two-sided Inspection of BWR Shroud Welds  

Science Conference Proceedings (OSTI)

The Boiling Water Reactor Vessel and Internals Project (BWRVIP) formed in June 1994 and is an association of utilities focused exclusively on BWR vessel and internals issues. This BWRVIP report provides the technical basis for implementing two-sided inspections of BWR shrouds to satisfy the ultrasonic testing (UT) inspection requirements contained in BWRVIP-03 and BWRVIP-76.

2008-11-10T23:59:59.000Z

338

Design of control system for hydraulic lifting platform with jack-up wind-power installation vessel  

Science Conference Proceedings (OSTI)

Jack-up wind-power installation vessel is the most important tool in construction of wind farm. And the control system for hydraulic lifting platform is the key point of jack-up wind-power installation vessel. Therefore the design of the control system ... Keywords: hydraulic control, hydraulic lifting platform, programmable logic controller, wind-power

Xuejin Yang; Dingfang Chen; Mingwang Dong; Taotao Li

2012-11-01T23:59:59.000Z

339

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

DOE Green Energy (OSTI)

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.

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

2010-04-13T23:59:59.000Z

340

Research Areas  

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Areas Areas Research Areas Print Scientists from a wide variety of fields come to the ALS to perform experiements. Listed below are some of the most common research areas covered by ALS beamlines. Below each heading are a few examples of the specific types of topics included in that category. Click on a heading to learn more about that research area at the ALS. Energy Science Photovoltaics, photosynthesis, biofuels, energy storage, combustion, catalysis, carbon capture/sequestration. Bioscience General biology, structural biology. Materials/Condensed Matter Correlated materials, nanomaterials, magnetism, polymers, semiconductors, water, advanced materials. Physics Atomic, molecular, and optical (AMO) physics; accelerator physics. Chemistry Surfaces/interfaces, catalysts, chemical dynamics (gas-phase chemistry), crystallography, physical chemistry.

Note: This page contains sample records for the topic "research vessel mirai" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

Research Highlight  

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ARM Measurements Help to Evaluate Radiation Codes Used in Global Modeling ARM Measurements Help to Evaluate Radiation Codes Used in Global Modeling Download a printable PDF Submitter: Oreopoulos, L., NASA Mlawer, E. J., Atmospheric & Environmental Research, Inc. Area of Research: Radiation Processes Working Group(s): Cloud Life Cycle Journal Reference: Oreopoulos L, E Mlawer, J Delamere, T Shippert, J Cole, B Fomin, M Iacono, Z Jin, J Li, J Manners, P Raisanen, F Rose, Y Zhang, MJ Wilson, and WB Rossow. 2012. "The Continual Intercomparison of Radiation Codes: results from Phase I." Journal of Geophysical Research - Atmospheres, 117, doi:10.1029/2011JD016821. The total error of each participating radiation code for all LW (left) and SW (right) cases in the CIRC intercomparison. The identity of each participating code can be found in the paper; codes built due to ARM

342

Research Highlight  

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Modified Climate Model Better Replicates Global Rainfall Modified Climate Model Better Replicates Global Rainfall Submitter: Bhattacharya, A., Pacific Northwest National Laboratory Area of Research: Cloud-Aerosol-Precipitation Interactions Working Group(s): Cloud-Aerosol-Precipitation Interactions Journal Reference: Song X, GJ Zhang, and JF Li. 2012. "Evaluation of microphysics parameterization for convective clouds in the NCAR Community Atmosphere Model CAM5." Journal of Climate, 25(24), doi:10.1175/JCLI-D-11-00563.1. Rainfall in the tropics. By improving an existing, sophisticated, global climate model, scientists can now simulate cloud and rainfall more accurately. Supported by the U.S. Department of Energy's Atmospheric System Research program, a research team from the Scripps Institution of Oceanography and

343

Research Highlight  

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Improving Water Vapor Continuum Absorption and Its Impact on a GCM Improving Water Vapor Continuum Absorption and Its Impact on a GCM Simulation Download a printable PDF Submitter: Turner, D. D., National Oceanic and Atmospheric Administration Mlawer, E. J., Atmospheric & Environmental Research, Inc. Area of Research: Radiation Processes Working Group(s): Cloud Life Cycle Journal Reference: Turner DD, A Merrelli, D Vimont, and EJ Mlawer. 2012. "Impact of modifying the longwave water vapor continuum absorption model on community Earth system model simulations." Journal of Geophysical Research, 117, D04106, doi:10.1029/2011JD016440. The mean difference profiles (experiment minus control) for clear-sky longwave radiative heating (QRLC); shortwave clear-sky radiative heating (QRSC); the longwave cloud radiative forcing (QRLCF); the precipitation

344

For Researchers  

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Export Control Export Control Berkeley Lab policy is to comply with all applicable state and federal laws, including those relating to Export Control. Berkeley Lab's Export Control Program is designed to support Berkeley Lab's and the University of California's international activities by ensuring compliance with U.S. export laws and regulations in the context of our fundamental research mission. Much of the Lab's compliance with U.S. export laws and regulations is based on our remaining within the "fundamental research" exception, i.e. performing basic or applied research for which the resulting information is ordinarily published and shared broadly within the scientific community. Do not sign non-disclosure or confidentiality agreements. Contact Parul Jain at 495-2306 or the Tech Transfer Department if you need or are

345

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

Chinese Researchers Report Reliable Method for Monitoring Soil Moisture Chinese Researchers Report Reliable Method for Monitoring Soil Moisture Submitter: Bhattacharya, A., Pacific Northwest National Laboratory Area of Research: Surface Properties Working Group(s): Cloud Life Cycle Journal Reference: Sun L, R Sun, XW Li, SL Liang, and RH Zhang. 2012. "Monitoring surface soil moisture status based on remotely sensed surface temperature and vegetation index information." Agricultural and Forest Meteorology, 166, doi:10.1016/j.agrformet.2012.07.015. Shown here is the SGP Central Facility, where the most comprehensive instrument suite is hosted. Moisture trapped in soil provides water necessary for vegetation and crops, but how much of that moisture makes its way into the atmosphere and influences regional meteorology? The poor understanding of the role of soil

346

Research Highlight  

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Putting the Pieces Together Putting the Pieces Together Download a printable PDF Submitter: Fan, J., Pacific Northwest National Laboratory Area of Research: Cloud Distributions/Characterizations Working Group(s): Cloud Life Cycle Journal Reference: Fan J, S Ghan, M Ovchinnikov, X Liu, P Rasch, and A Korolev. 2011. "Representation of arctic mixed-phase clouds and the Wegener-Bergeron-Findeisen process in climate models: Perspectives from a cloud-resolving study." Journal of Geophysical Research - Atmospheres, 116, D00T07, doi:10.1029/2010JD015375. PNNL's Arctic mixed-phase cloud research was augmented with field observations from the 2008 Indirect and Semi-Direct Aerosol Campaign (ISDAC) in Northern Alaska. Photo courtesy of A. Korolev, Environment Canada. Vertical cross sections of (a) the vertical velocity (the contour lines)

347

Research Highlight  

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Parameterizing the Ice Fall Speed in Climate Models: Results from TC4 and Parameterizing the Ice Fall Speed in Climate Models: Results from TC4 and ISDAC Download a printable PDF Submitter: Mitchell, D. L., Desert Research Institute Mishra, S., NOAA - Coop. Inst. for Mesoscale Meteorological Studies Area of Research: General Circulation and Single Column Models/Parameterizations Working Group(s): Cloud Life Cycle, Cloud-Aerosol-Precipitation Interactions Journal Reference: Mitchell DL, S Mishra, and RP Lawson. 2011. "Representing the ice fall speed in climate models: Results from Tropical Composition, Cloud and Climate Coupling (TC4) and the Indirect and Semi-Direct Aerosol Campaign (ISDAC)." Journal of Geophysical Research - Atmospheres, 116, D00T03, doi:10.1029/2010JD015433. Relationship between De and Vm for all tropical cirrus cloud types (solid

348

Research Highlight  

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Raman Lidar Observations of Aerosol Humidification Near Clouds Raman Lidar Observations of Aerosol Humidification Near Clouds Submitter: Ferrare, R. A., NASA - Langley Research Center Area of Research: Aerosol Properties Working Group(s): Aerosol Journal Reference: Ferrare, R., et al., Evaluation of Daytime Measurements of Aerosols and Water Vapor Made by an Operational Raman Lidar over the Southern Great Plains, J. Geophys. Res., 111, D05S08, doi:10.1029/2005JD005836, 2006. Relative humidity profiles derived from the Raman lidar during the ALIVE 2005 field experiment. Aerosol extinction profiles derived from the Raman lidar during the ALIVE 2005 field experiment. Aerosol humidification factor f(RH) from Raman lidar measured profiles of aerosol extinction and relative humidity. Upgrades to the Raman lidar at the ARM Climate Research Facility (ACRF)

349

Research Highlight  

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Spectral Invariant Behavior of Zenith Radiance Around Cloud Edges Observed Spectral Invariant Behavior of Zenith Radiance Around Cloud Edges Observed by ARM SWS Download a printable PDF Submitter: Marshak, A., NASA - Goddard Space Flight Center Knyazikhin, Y., Boston University Chiu, J., University of Reading Wiscombe, W. J., Brookhaven National Laboratory Area of Research: Radiation Processes Working Group(s): Radiative Processes Journal Reference: Marshak A, Y Knyazikhin, JC Chiu, and WJ Wiscombe. 2009. "Spectral invariant behavior of zenith radiance around cloud edges observed by ARM SWS." Geophysical Research Letters, 36, L16802, doi:10.1029/2009GL039366. (top) Time-wavelength color contour plot of ARM shortwave spectrometer (SWS) spectra measured from 21:35:24 to 21:40:24 UTC on 18 May 2007 at the ARM Climate Research Facility (ACRF) Southern Great Plains (SGP) site in

350

Research Highlight  

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Evaluation of a New Mixed-Phase Cloud Microphysics Parameterization with Evaluation of a New Mixed-Phase Cloud Microphysics Parameterization with SCAM, CAPT Forecasts and M-PACE Observations Download a printable PDF Submitter: Liu, X., University of Wyoming Area of Research: General Circulation and Single Column Models/Parameterizations Working Group(s): Cloud Modeling Journal Reference: Liu, X, S Xie, and SJ Ghan. 2007. "Evaluation of a new mixed-Phase cloud microphysics parameterization with the NCAR single column climate model (SCAM) and ARM M-PACE observations." Geophysical Research Letters 34, L23712, doi:10.1029/2007GL031446. Xie, S, J Boyle, SA Klein, X Liu and S Ghan. 2008. "Simulations of arctic mixed-phase clouds in forecasts with CAM3 and AM2 for M-PACE." Journal of Geophysical Research, in press.

351

Research Highlight  

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ARM Program Research Improves Longwave Radiative Transfer Models ARM Program Research Improves Longwave Radiative Transfer Models Submitter: Turner, D. D., National Oceanic and Atmospheric Administration Area of Research: General Circulation and Single Column Models/Parameterizations Working Group(s): Radiative Processes Journal Reference: The QME AERI LBLRTM: A closure experiment for downwelling high spectral resolution infrared radiance. D.D. Turner, D.C. Tobin, S.A. Clough, P.D. Brown, R.G. Ellingson, E.J. Mlawer, R.O. Knuteson, H.E. Revercomb, T.R. Shippert, and W.L. Smith. 2004. Journal of Atmospheric Science, 61, 2657-2675. Top panels: Examples of downwelling infrared radiance observed by the AERI for two different clear sky cases with different amounts of water vapor. Bottom panels: Differences between the AERI observations and calculations

352

A Relaxed Eddy Accumulator for Surface Flux Measurements on Ground-Based Platforms and Aboard Research Vessels  

Science Conference Proceedings (OSTI)

The relaxed eddy accumulation (REA) method has become a standard tool for scalar flux measurements near the surface during field experiments. With this technique, turbulent fluxes of relatively slowly reacting species are measured using the ...

A. Brut; D. Legain; P. Durand; P. Laville

2004-03-01T23:59:59.000Z

353

Research Focus  

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Focus Focus Work at FEERC is centered on three interrelated areas of research: fuels, engines, and emis- sions. FEERC scientists study the impacts of fuel properties on advanced combustion processes as well as on emissions and emission control strategies and devices. The range of fuels studied includes gaseous (natural gas) and liquid fuels from conventional and unconventional fossil- based sources, as well as non-petroleum fuels from synthetic and renewable sources. The FEERC conducts research on innovative internal combustion engine technologies and control systems for improved efficiency. Combining novel diagnostic and experimental methods with modeling, the Center's scientists also develop improved understanding of the functions and key mechanisms of emission control devices

354

Research Highlight  

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Classifying Cloud Phase Classifying Cloud Phase Download a printable PDF Submitter: Shupe, M., University of Colorado Area of Research: Cloud Distributions/Characterizations Working Group(s): Cloud Properties Journal Reference: Shupe, MD. 2007. "A ground-based multisensory cloud phase classifier." Geophysical Research Letters 34, L22809, doi:10.1029/2007GL031008. Observations of (a) lidar backscatter, (b) lidar depolarization ratio, (c) radar reflectivity, (d) radar mean Doppler velocity, (e) radar Doppler spectrum width, (f) microwave radiometer-derived liquid water path, and (g) the resulting multisensor cloud-phase classification mask. Cloud phase identification is a necessary prerequisite to performing cloud property retrievals from remote sensor measurements. Most retrieval

355

NREL: Photovoltaics Research - Research Staff  

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Research Staff Research Staff Our silicon group members have backgrounds in physics, chemistry, mathematics, materials science, and electrical engineering. Russell Bauer Howard Branz Sachit Grover Vincenzo LaSalvia Benjamin Lee William Nemeth Matt Page Lorenzo Roybal Pauls Stradins, (Acting Group Manager) Charles Teplin Qi Wang David Young Hao-Chih Yuan Photo of 21 people standing in front of a building with a silver, cylinder-shaped structure on one side. Photo of Pauls Stradins Pauls Stradins Senior Scientist II Group Manager Primary Research Interests High-efficiency silicon photovoltaics: advanced passivation techniques and industrially-relevant processes Interfacing Si cell with other materials for high-efficiency tandem Nanostructured semiconductor materials for photovoltaics: Si quantum

356

Research Highlight  

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Entrainment Rate in Shallow Cumuli: Probabilistic Distribution and Entrainment Rate in Shallow Cumuli: Probabilistic Distribution and Dependence on Dry Air Sources Download a printable PDF Submitter: Liu, Y., Brookhaven National Laboratory Lu, C., Brookhaven National Laboratory Area of Research: Cloud Processes Working Group(s): Cloud Life Cycle Journal Reference: Lu C, Y Liu, S Niu, and AM Vogelmann. 2012. "Lateral entrainment rate in shallow cumuli: Dependence on dry air sources and probability density functions." Geophysical Research Letters, 39, L20812, doi:10.1029/2012GL053646. Probability density functions (PDFs) of entrainment rate (λ) for different dry air sources in eight cumulus flights. The rate at which cloud engulfs dry air (entrainment rate) has proven to be one of the strongest controls on the climate sensitivity of climate models;

357

Research Highlight  

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Downward Longwave Irradiance Uncertainty Under Arctic Atmospheres: Downward Longwave Irradiance Uncertainty Under Arctic Atmospheres: Measurements and Modeling Submitter: Marty, C., Swiss Federal Institute of Snow and Avalanche Research Area of Research: Radiation Processes Working Group(s): Radiative Processes Journal Reference: Marty, C., R. Philipona, J. Delamere, E.G. Dutton, J. Michalsky, K. Stamnes, R. Storvold, T. Stoffel, S.A. Clough, and E.J. Mlawr, Downward longwave irradiance uncertainty under arctic atmospheres: Measurements and modeling, J. Geophys. Res., 108(D12), 4358, doi:10.1029/2002JD002937, 2003. IPASRC-II instruments deployed at ARM's Barrow Station. Members of 11 international institutions converged at the Atmospheric Radiation Measurement (ARM) Program's North Slope of Alaska (NSA) site in Barrow, Alaska, to conduct the Second International Pyrgeometer and

358

Research Highlight  

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The Short and the Long of Storms: Tracing a Deep Convective System's Life The Short and the Long of Storms: Tracing a Deep Convective System's Life in the Midlatitude Download a printable PDF Submitter: Feng, Z., Pacific Northwest National Laboratory Area of Research: Cloud Processes Working Group(s): Cloud Life Cycle Journal Reference: Feng Z, X Dong, B Xi, S McFarlane, A Kennedy, B Lin, and P Minnis. 2012. "Life cycle of midlatitude deep convective systems in a Lagrangian framework." Journal of Geophysical Research - Atmospheres, 117(D23), D23201, doi:10.1029/2012JD018362. The life cycle of a convective system tracked by the automated tracking algorithm in the study domain. Time increases from the top left to the bottom right, and each image represents an hour. The colors represent regions given by the hybrid classification.

359

Research Highlight  

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ARM Measurements Validate New Satellite Multilayer Cloud Remote Sensing ARM Measurements Validate New Satellite Multilayer Cloud Remote Sensing Method Submitter: Minnis, P., NASA - Langley Research Center Area of Research: Cloud Distributions/Characterizations Working Group(s): Cloud Properties Journal Reference: Huang, J., P. Minnis, B. Lin, Y. Yi, T.-F. Fan, S. Sun-Mack, and J. K. Ayers, 2006: Determination of ice water path in ice-over-water cloud systems using combined MODIS and AMSR-E measurements. Geophys. Res. Lett., 33, L21801, 10.1029/2006GL027038. Minnis, P., J. Huang, B. Lin, Y. Yi, R. F. Arduini, T.-F. Fan, J. K. Ayers, and G. G. Mace, 2007: Ice cloud properties in ice-over-water cloud systems using TRMM VIRS and TMI data. J. Geophys. Res., 112, D06206, doi:10.1029/2006JD007626. Figure 1. Comparison of the VISST and MCRS retrievals with simultaneous

360

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Precipitation Forecast Improved with a New Convective Triggering Mechanism Precipitation Forecast Improved with a New Convective Triggering Mechanism Download a printable PDF Submitter: Xie, S., Lawrence Livermore National Laboratory Zhang, M., Stony Brook University Area of Research: General Circulation and Single Column Models/Parameterizations Working Group(s): Cloud Modeling Journal Reference: Xie, S, and M Zhang. 2000. "Impact of the convective triggering function on single-column model simulations." Journal of Geophysical Research 105: 14983-14996. Six-hour accumulated precipitation valid at 12 UTC 18 July 2005. (a) Radar Observation, (b) DCAPE, (c) GSM without the DCAPE trigger, and (d) GSM with the DCAPE trigger. Considerable improvement of precipitation forecast is obtained by the GSM with the new trigger compared to the radar observation.

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361

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Strong Impacts of Vertical Velocity on Cloud Microphysics and Implications Strong Impacts of Vertical Velocity on Cloud Microphysics and Implications for Aerosol Indirect Download a printable PDF Submitter: Liu, Y., Brookhaven National Laboratory Lu, C., Brookhaven National Laboratory Area of Research: Cloud-Aerosol-Precipitation Interactions Working Group(s): Cloud Life Cycle, Cloud-Aerosol-Precipitation Interactions Journal Reference: Lu C, Y Liu, S Niu, and AM Vogelmann. 2012. "Observed impacts of vertical velocity on cloud microphysics and implications for aerosol indirect effects." Geophysical Research Letters, 39, L21808, doi:10.1029/2012GL053599. Joint probability density functions (PDF) of relative dispersion (ε) versus vertical velocity (w) along horizontal aircraft legs for each cumulus flight (date given in legend). The red lines denote weighted least

362

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Hemispherical Simulations Show Impact of Aerosols on Cloud Reflectivity Hemispherical Simulations Show Impact of Aerosols on Cloud Reflectivity Submitter: Rotstayn, L., Commonwealth Scientific and Industrial Research Organization Area of Research: Aerosol Properties Working Group(s): Aerosol Journal Reference: Rotstayn, L., and Y. Liu, Sensitivity of the First Indirect Aerosol Effect to an Increase in Cloud Droplet Spectral Dispersion with Droplet Number Concentration, Journal of Climate: Vol. 16, No. 21, pp.3476-3481, May 2003. Figure 1. Measurements of the relation between the relative dispersion of the cloud droplet spectrum and the cloud droplet number concentration (N). The lower, middle, and upper curves show the parameterizations used in the LOWER, MIDDLE, and UPPER simulations, respectively. A recent study by DOE Atmospheric Radiation Measurement (ARM) Program

363

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Giants in the Sky Giants in the Sky For original submission and image(s), see ARM Research Highlights http://www.arm.gov/science/highlights/ Research Highlight A few large particles in a crowd of tiny ones have often been ignored when calculating the amount of sunlight bounced back into space in clean-sky conditions. Scientists at Pacific Northwest National Laboratory found that these "giant" particles have a larger-than-expected impact on the amount of sunlight reflected away from Earth, by as much as 45 percent. They also showed that particles larger than one micron (0.000039 inch) occur much more frequently than expected, up to 85 percent of the time. "Many routine measurements are unable to sample large particles, thus they may overlook the residence of many 'Gullivers in the country of Lilliput,' said Dr. Evgueni

364

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ARM Science Applications of AERI Measurements: 1997 Progress ARM Science Applications of AERI Measurements: 1997 Progress Submitter: Smith, W. L., NASA - Langley Research Center Area of Research: Radiation Processes Working Group(s): Cloud Modeling Journal Reference: N/A Figure 1. Figs. 1a and 1b contain rms differences from 72 radiosondes for AERI retrievals (blue), GOES retrievals (black), and AERI+GOES retrievals (red) for temperature and mixing ratio respectively during the 1997 Water Vapor IOP. A measure of meteorological the variability of the temperature and water vapor is indicated by the green line. Figs. 1c and 1d show the TPW for the same cases from GOES, AERI+GOES, radiosonde, and the ARM SGP CART microwave radiometer and relative percent differences in TPW amounts. Figure 2. Four consecutive radiosonde, GOES, and AERI+GOES comparisons from

365

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Weather and Atmospheric Overview During Study of Natural and Urban Weather and Atmospheric Overview During Study of Natural and Urban Emissions (CARES) Download a printable PDF Submitter: Fast, J. ., Pacific Northwest National Laboratory Area of Research: Aerosol Properties Working Group(s): Aerosol Life Cycle Journal Reference: Fast JD, WI Gustafson, LK Berg, WJ Shaw, M Pekour, M Shrivastava, JC Barnard, RA Ferrare, CA Hostetler, JA Hair, M Erickson, BT Jobson, B Flowers, MK Dubey, S Springston, RB Pierce, L Dolislager, J Pederson, and RA Zaveri. 2012. "Transport and mixing patterns over central California during the Carbonaceous Aerosol and Radiative Effects Study (CARES)." Atmospheric Chemistry and Physics, 12, 1759-1783. Aircraft sampling flight patterns are shown over central California in this aerial overlay. Researchers collected and analyzed measurements from

366

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Micropulse Lidar-Derived Aerosol Optical Depth Climatology at ARM Sites Micropulse Lidar-Derived Aerosol Optical Depth Climatology at ARM Sites Worldwide Download a printable PDF Submitter: Kafle, D. N., University of California, Riverside Coulter, R. L., Argonne National Laboratory Area of Research: Aerosol Properties Working Group(s): Aerosol Life Cycle Journal Reference: Kafle DN and RL Coulter. 2013. "Micropulse lidar-derived aerosol optical depth climatology at ARM sites worldwide." Journal of Geophysical Research - Atmospheres, 118(13), 10.1002/jgrd.50536. Vertical profiles of multi-year annually averaged AOD (z) at different ARM sites: SGP, NSA, TWP, GRW, and FKB. Inset plots are the profiles of corresponding relative standard deviation, Srel (z). The corresponding 1-sigma measurement errors are given in horizontal bars.

367

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Ice Heating Up Cold Clouds Ice Heating Up Cold Clouds Download a printable PDF Submitter: Ovchinnikov, M., Pacific Northwest National Laboratory Area of Research: Cloud Distributions/Characterizations Working Group(s): Cloud-Aerosol-Precipitation Interactions Journal Reference: Ovchinnikov M, A Korolev, and J Fan. 2011. "Effects of ice number concentration on dynamics of a shallow mixed-phase stratiform cloud." Journal of Geophysical Research - Atmospheres, 116, D00T06, doi:10.1029/2011JD015888. The mighty cloud ice crystal appears deceptively delicate but has the power to tip the balance between ice and water in Arctic clouds. This image of an ice crystal was obtained from a Cloud Particle Imager during ISDAC. The imager was mounted on aircraft flying through clouds at a speed of 100 m/s.

368

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New Method for Three-Dimensional Imaging of Cirrus Clouds New Method for Three-Dimensional Imaging of Cirrus Clouds Submitter: Liou, K., University of California, Los Angeles Area of Research: Cloud Distributions/Characterizations Working Group(s): Cloud Properties Journal Reference: Liou, K.N, S.C. Ou, Y. Takano, J. Roskovensky, G.G. Mace, K. Sassen, and M. Poellot, 2002: "Remote sensing of three-dimensional inhomogeneous cirrus clouds using satellite and mm-wave cloud radar data," Geophysical Research Letters 29(9): 1360. Figure 1 ARM Data Enables the Development and Verification of a New Method for Three-Dimensional Imaging of Cirrus Clouds to Improve Climate Predictions Cirrus clouds cover about 30% of the Earth's surface. Because ice crystals both reflect sunlight and absorb thermal energy emitted from the earth

369

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Critical Role of Cloud Drop Effective Radius >14 Micron Radius in Rain Critical Role of Cloud Drop Effective Radius >14 Micron Radius in Rain Initiation Download a printable PDF Submitter: Rosenfeld, D., The Hebrew University of Jerusalem Wang, H., Pacific Northwest National Laboratory Area of Research: Radiation Processes Working Group(s): Cloud-Aerosol-Precipitation Interactions Journal Reference: Rosenfeld D, H Wang, and PJ Rasch. 2012. "The roles of cloud drop effective radius and LWP in determining rain properties in marine stratocumulus." Journal of Geophysical Research - Atmospheres, 39, doi:10.1029/2012GL052028. The dependence of rain rate on cloud drop effective radius (re) near cloud top. The color scale is for the median value of column maximum rain rate in each joint bin of CWP-re (cloud liquid water path and cloud-top re).

370

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The Apparent Bluing of Aerosols Near Clouds The Apparent Bluing of Aerosols Near Clouds Download a printable PDF Submitter: Marshak, A., NASA - Goddard Space Flight Center Area of Research: Radiation Processes Working Group(s): Radiative Processes Journal Reference: Marshak, A, G Wen, JA Coakley, LA Remer, NG Loeb, and RF Cahalan. 2008. "A simple model of the cloud adjacency effect and the apparent bluing of aerosols near clouds." Journal of Geophysical Research 113, D14S17, doi: 10.1029/2007JD009196. (upper panel) A schematic two-layer model of a broken cloud field and Rayleigh scatterers. (lower panel) An example of the Poisson distribution of broken cloud fields with cloud fraction Ac = 0.3 for a 10 by 10 km area. For a cloud vertical thickness of 1 km, the left lower panel has cloud

371

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Improving the Treatment of Radiation in Climate Models Improving the Treatment of Radiation in Climate Models Download a printable PDF Submitter: Delamere, J. S., Tech-X Corporation Area of Research: Radiation Processes Working Group(s): Aerosol Life Cycle, Cloud Life Cycle Journal Reference: Delamere JS, SA Clough, VH Payne, EJ Mlawer, DD Turner, and RR Gamache. 2010. "A far-infrared radiative closure study in the Arctic: Application to water vapor." Journal of Geophysical Research - Atmospheres, 115, D17106, 10.1029/2009JD012968. The mean AERI-ER radiances for a select set of cloud-free cases at NSA in 2007 are presented in the top panel. The bottom panel presents mean spectral differences between the measurements and model calculations. The red line demonstrates the differences when using the pre-RHUBC version of

372

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Global Dimming and Brightening: an Update Beyond 2000 Global Dimming and Brightening: an Update Beyond 2000 Download a printable PDF Submitter: Long, C. N., Pacific Northwest National Laboratory Wild, M., Institute for Atmospheric and Climate Science - ETH Zurich Truessel, B., Institute for Atmospheric and Climate Science - ETH Zurich Ohmura, A., Swiss Federal Institute of Technology Koenig-Langlo, G., Alfred Wegener Institute Dutton, E. G., NOAA/OAR/ESRL Tsvetkov, A. V., World Radiation Data Centre Area of Research: Radiation Processes Working Group(s): Radiative Processes Journal Reference: Wild M, B Trüssel, A Ohmura, CN Long, G König-Langlo, EG Dutton, and A Tsvetkov. 2009. "Global dimming and brightening: An update beyond 2000." Journal of Geophysical Research - Atmospheres, 114, D00D13, 10.1029/2008JD011382.

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Field Experiments to Improve the Treatment of Radiation in the Mid-to-Upper Field Experiments to Improve the Treatment of Radiation in the Mid-to-Upper Troposphere Download a printable PDF Submitter: Turner, D. D., National Oceanic and Atmospheric Administration Mlawer, E. J., Atmospheric & Environmental Research, Inc. Area of Research: Radiation Processes Working Group(s): Cloud-Aerosol-Precipitation Interactions Journal Reference: Turner DD and EJ Mlawer. 2010. "The Radiative Heating in Underexplored Bands Campaigns (RHUBC)." Bulletin of the American Meteorological Society, 91, doi:10.1175/2010BAMS2904.1. (a) Atmospheric transmittance at 1 cm-1 resolution in the far-infrared for three atmospheres that are representative of the ARM SGP site, NSA site, and RHUBC-II site in the Chajnantor plateau (CJC). (b) The transmittance

374

Research Highlight  

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Cloud Susceptibility Measures Potential Cloud Sensitivity to First Aerosol Cloud Susceptibility Measures Potential Cloud Sensitivity to First Aerosol Indirect Effect Download a printable PDF Submitter: Oreopoulos, L., NASA Platnick, S., NASA - Goddard Space Flight Center Area of Research: Cloud Distributions/Characterizations Working Group(s): Radiative Processes Journal Reference: Platnick, S, and L Oreopoulos. 2008. "Radiative susceptibility of cloudy atmospheres to droplet number perturbations: 1. Theoretical analysis and examples from MODIS." Journal of Geophysical Research doi:10.1029/2007JD009654, in press. Oreopoulos, L., and S. Platnick. 2008. Radiative susceptibility of cloudy atmospheres to droplet number perturbations: 2. Global analysis from MODIS, J. Geophys. Res., doi:10.1029/2007JD009655, in press. Theoretical calculations with a shortwave broadband radiative transfer

375

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Probabilistic Approach Useful for Evaluating Cloud System Models Probabilistic Approach Useful for Evaluating Cloud System Models Submitter: Jakob, C., Monash University Area of Research: General Circulation and Single Column Models/Parameterizations Working Group(s): Cloud Modeling Journal Reference: Jakob, C., R. Pincus, C. Hannay, and K.M. Xu (2004). Use of cloud radar observations for model evaluation: A probabilistic approach, J. Geophys. Res., 109, D03202, doi:10.1029/2003JD003473. In evaluating climate models, time and space represent key challenges when extrapolating observations into simulations. Researchers supported by DOE's Atmospheric Radiation Measurement (ARM) Program have explored an alternative method based on "point series data" to arrive at model cloud predictions. Point series data are obtained over time through measurements

376

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The Mixing State of Carbonaceous Aerosol Particles in Northern and Southern The Mixing State of Carbonaceous Aerosol Particles in Northern and Southern California Measured During CARES and CalNex Download a printable PDF Submitter: Zaveri, R., Pacific Northwest National Laboratory Area of Research: Aerosol Processes Working Group(s): Aerosol Life Cycle Journal Reference: Cahill JF, K Suski, JH Seinfeld, RA Zaveri, and KA Prather. 2012. "The mixing state of carbonaceous aerosol particles in Northern and Southern California measured during CARES and CalNex 2010." Atmospheric Chemistry and Physics, 12, doi:10.5194/acp-12-10989-2012. The CARES campaign took place in Sacramento in order to sample the city's urban plume. Photo courtesy of Jason Tomlinson. Researchers, including DOE scientists working at Pacific Northwest National

377

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Cloud Observations at Niamey During the AMF Deployment Cloud Observations at Niamey During the AMF Deployment Submitter: Kollias, P., McGill University Area of Research: Cloud Distributions/Characterizations Working Group(s): Cloud Properties Journal Reference: Kollias, P. and M. A. Miller, 2007: Cloud and Precipitation Observations at Niamey During the 2006 ARM Mobile Facility Deployment. Submitted to Geophysical Research Letters. Daily observed cloud fraction in Niamey during the AMF deployment. The cloud fraction is derived using measurements from the 94-GHz radar, the MPL, and the ceilometer. The vertical resolution is 260 m, and a 5-day temporal filter is applied to the daily cloud fraction profiles. (a) Monthly-averaged cloud and precipitation fraction. The monthly mean and standard deviation of cirrus cloud top (white line), middle cloud tops

378

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Cloud-Radiation Effects on Sea Ice Loss Cloud-Radiation Effects on Sea Ice Loss Download a printable PDF Submitter: Stephens, G. L., Colorado State University Area of Research: Cloud Distributions/Characterizations Working Group(s): Cloud Properties Journal Reference: Kay, JE, T L'Ecuyer, A Gettelman, G Stephens, and C O'Dell. "The contribution of cloud and radiation anomalies to the 2007 Arctic sea ice extent minimum." To appear in Geophysical Research Letters. Clouds and downwelling radiation 2007-2006 differences (June 15-Sept 15). a. Total cloud fraction differences based on radar and lidar data. b. Downwelling SW radiative flux difference. c. Downwelling LW radiative flux difference. The Western Arctic Ocean is outlined in brown. ARM ground-based radiation observations at Barrow, Alaska.

379

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The Surprisingly Large Contribution of Small Marine Clouds to Cloud The Surprisingly Large Contribution of Small Marine Clouds to Cloud Fraction and Reflectance Download a printable PDF Submitter: Oreopoulos, L., NASA Feingold, G., NOAA - Earth System Research Laboratory Koren, I., Weizmann Institute of Science Remer, L., NASA - GSFC, Laboratory for Atmospheres Area of Research: Clouds with Low Optical [Water] Depths (CLOWD) Working Group(s): Cloud Properties Journal Reference: Koren, I, L Oreopoulos, G Feingold, LA Remer, and O Altaratz. 2008. "How small is a small cloud?" Atmospheric Chemistry and Physics Journal, in press Cloud mask for a sparse cumulus cloud field as inferred by using the same threshold at four different spatial resolutions. The upper-left panel is for the original Landsat resolution and the lower-right panel is for a

380

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Burning on the Prairies Burning on the Prairies Submitter: Bhattacharya, A., Pacific Northwest National Laboratory Area of Research: Radiation Processes Working Group(s): Cloud-Aerosol-Precipitation Interactions Journal Reference: Fischer ML, MS Torn, DP Billesbach, G Doyle, B Northup, and SC Biraud. 2012. "Carbon, water, and heat flux responses to experimental burning and drought in a tallgrass prairie." Agricultural and Forest Meteorology, 166, doi:10.1016/j.agrformet.2012.07.011. Pasture burning during the beginning of the experiment at the USDA Grazing Lands Research Laboratory in March 2005. What does it mean for the carbon cycle? The deep drought in the United States that fueled wildfires and damaged crops in 2012 has now continued well into 2013. However, long before the droughts and fires wreaked havoc, a team of

Note: This page contains sample records for the topic "research vessel mirai" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

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Wildfires Lead to More Warming Than Climate Models Predict, a New Mexico Wildfires Lead to More Warming Than Climate Models Predict, a New Mexico Fire Study Reports Download a printable PDF Submitter: Bhattacharya, A., Pacific Northwest National Laboratory Area of Research: Aerosol Properties Working Group(s): Aerosol Life Cycle Journal Reference: China S, C Mazzoleni, K Gorkowski, AC Aiken, and MK Dubey. 2013. "Morphology and mixing state of individual freshly emitted wildfire carbonaceous particles." Nature Communications, 4, 2122, doi:10.1038/ncomms3122. La Conchas fire, New Mexico Analyzing fresh, carbon-rich aerosols in smoke from the largest wildfire in New Mexico (2011), scientists report large impacts of wildfires on climate. A research study, published last week in Nature Communications, has revealed that smoke from wildfires, or biomass-burning events, contains

382

Research Highlight  

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Clouds Get in the Way: How Climate Models Calculate the Effects of Clouds Clouds Get in the Way: How Climate Models Calculate the Effects of Clouds on Earth's Warming Download a printable PDF Submitter: Qian, Y., Pacific Northwest National Laboratory Area of Research: Cloud Distributions/Characterizations Working Group(s): Cloud Life Cycle Journal Reference: Qian Y, CN Long, H Wang, JM Comstock, SA McFarlane, and S Xie. 2012. "Evaluation of cloud fraction and its radiative effect simulated by IPCC AR4 global models against ARM surface observations." Atmospheric Chemistry and Physics, 12(4), doi:10.5194/acp-12-1785-2012. Clouds get in the way of the dawn light, perfectly framing the Raman lidar instrument at the ARM Climate Research Facility Southern Great Plains site. This ground-based laser is a remote sensing instrument used for measuring

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Remote Sensing of Cirrus Cloud Vertical Size Profile Using MODIS Data Remote Sensing of Cirrus Cloud Vertical Size Profile Using MODIS Data Download a printable PDF Submitter: Ou, S., University of California, Los Angeles Area of Research: Cloud Distributions/Characterizations Working Group(s): Cloud Properties Journal Reference: Wang X, KN Liou, SS Ou, GG Mace, and M Deng. 2009. "Remote sensing of cirrus cloud vertical size profile using MODIS data." Journal of Geophysical Research - Atmospheres, 114, D09205, doi:10.1029/2008JD011327. (a) MODIS true color composite images for March 6, 2001 at 1736UTC, (b) retrieved Τc; (c) retrieved Dt for selected domain; (d) retrieved Db for selected domain; (e) scatter plot for retrieved Τc versus MODIS Τc for selected domain; (f) scatter plot for retrieved De versus MODIS De for

384

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Millimeter Wave Scattering from Ice Crystals and Their Aggregates Millimeter Wave Scattering from Ice Crystals and Their Aggregates Download a printable PDF Submitter: Botta, G., Pennsylvania State University Verlinde, J., Pennsylvania State University Area of Research: Radiation Processes Working Group(s): Cloud Life Cycle Journal Reference: Botta G, K Aydin, J Verlinde, A Avramov, A Ackerman, A Fridlind, M Wolde, and G McFarquhar. 2011. "Millimeter wave scattering from ice crystals and their aggregates: Comparing cloud model simulations with X- and Ka-band radar measurements." Journal of Geophysical Research - Atmospheres, 116, D00T04, doi:10.1029/2011JD015909. Observational data sets are needed to drive and evaluate results from cloud-resolving model (CRM) simulations in order to improve parameterizations of the physical processes. Radar is one of the few

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Remote Sensing of Mineral Dust Using AERI Remote Sensing of Mineral Dust Using AERI Download a printable PDF Submitter: Hansell, R. A., University of California, Los Angeles Area of Research: Radiation Processes Working Group(s): Aerosol Journal Reference: Hansell R, KN Liou, SC Ou, SC Tsay, Q Ji, and JS Reid. 2008. "Remote sensing of mineral dust aerosol using AERI during the UAE2: A modeling and sensitivity study." Journal of Geophysical Research - Atmospheres, 113, D18202, doi:10.1029/2008JD010246. BT sensitivity to dust optical depth at 962 cm-1 with markers denoting locations of AERI subbands 1-17 from left to right. (a) Volz compact hexagon model spectra for four optical depths with best fit AERI spectrum. (b) Same as (a) but for a kaolinite/50% calcium carbonate mixturedust model.

386

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The Evolution and Distribution of Water Vapor and Microphysical Properties The Evolution and Distribution of Water Vapor and Microphysical Properties in Cirrus Clouds Download a printable PDF Submitter: Comstock, J. M., Pacific Northwest National Laboratory Area of Research: Radiation Processes Working Group(s): Cloud Modeling, Cloud Properties Journal Reference: Comstock JM, R Lin, DO Starr, and P Yang. 2008. "Understanding ice supersaturation, particle growth, and number concentration in cirrus clouds." Journal of Geophysical Research - Atmospheres, 113, D23211, doi:10.1029/2008JD010332. Vertical velocity (Vm) derived from millimeter cloud radar (MMCR) Doppler velocity measurements in cirrus clouds observed over the ACRF SGP site. Cloud model simulations of cirrus clouds using large-scale forcing (left panel) and cloud-scale forcing (right panel).

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Quantifying the Impact of Dust on Ice Generation in Supercooled Stratiform Quantifying the Impact of Dust on Ice Generation in Supercooled Stratiform Clouds Download a printable PDF Submitter: Wang, Z., University of Wyoming Zhang, D., University of Wyoming Area of Research: Cloud-Aerosol-Precipitation Interactions Working Group(s): Cloud-Aerosol-Precipitation Interactions Journal Reference: Zhang D, Z Wang, A Heymsfield, J Fan, D Liu, and M Zhao. 2012. "Quantifying the impact of dust on heterogeneous ice generation in midlevel supercooled stratiform clouds." Journal of Geophysical Research - Atmospheres, 39, L18805, doi:10.1029/2012GL052831. An example of dusty MSSC: (a) CALIOP TAB profiles at 532nm; (b) CALIOP depolarization profiles at 532nm; (c) CloudSat CPR radar reflectivity profiles; (d) Identified dust layers and MSSC; (e) Global distribution of

388

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Wide Angle Imaging Lidar: Active Optical Sensor Technology for Ground-Based Wide Angle Imaging Lidar: Active Optical Sensor Technology for Ground-Based Probing of Dense Clouds Download a printable PDF Submitter: Davis, A. B., Jet Propulsion Laboratory Area of Research: Cloud Distributions/Characterizations Working Group(s): Cloud Properties Journal Reference: Davis, AB. 2008. "Multiple-scattering lidar from both sides of the clouds: Addressing internal structure." Journal of Geophysical Research 113, D14S10, doi:10.1029/2007JD009666. Figure 1. Lidar observations of a dense cloud. Left: standard (single-scattering/on-beam) lidar. Right: multiple-scattering/off-beam lidar. Note the extreme narrowness of the FOV in the standard case, as is required to restrict as much as possible the signal to a single backscatter. Also note the weak penetration, O(1) MFP, of the two-way

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Testing and Comparing the Modified Anomalous Diffraction Approximation Testing and Comparing the Modified Anomalous Diffraction Approximation Submitter: Mitchell, D. L., Desert Research Institute Area of Research: Cloud Distributions/Characterizations Working Group(s): Radiative Processes Journal Reference: Mitchell, D.L., A.J. Baran, W.P. Arnott, C. Schmitt, 2006: Testing and comparing the anomalous diffraction approximation. J. Atmos. Sci., 63, 2948-2962. Comparison of MADA and T-matrix with measured Qext. Regions without data were contaminated by water vapor or CO2 absorption. MADA and T-matrix calculations are based on the measured PSD of hexagonal columns having an effective diameter of 14 microns. Comparison of the PSD weighted Qabs predicted by FDTD and MADA for a tunneling efficiency corresponding to aggregates. Cirrus clouds play a large role in the Earth's radiation budget and the way

390

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Vertical Variation of Cloud Droplet Size Using Ship and Space-borne R/S Vertical Variation of Cloud Droplet Size Using Ship and Space-borne R/S Data Download a printable PDF Submitter: Li, Z., University of Maryland Chen, R., University of Maryland Wood, R., University of Washington Chang, F., Science Systems and Applications, Inc. Ferraro, R., NOAA/NESDIS, WWBG Area of Research: Cloud Distributions/Characterizations Working Group(s): Cloud Properties Journal Reference: Chen, R, R Wood, Z Li, R Ferraro, and F Chang. 2008. "Studying the vertical variation of cloud droplet effective radius using ship and space-borne remote sensing data." Journal of Geophysical Research 113, doi:10.1029/2007JD009596. Figure 1. Coincident images of C-band radar reflectivity and MODIS cloud profile at UTC 15:55, Oct. 18, 2001. a) RHB C-band radar reflectivity

391

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Continuous Clear-Sky Longwave from Surface Measurements Continuous Clear-Sky Longwave from Surface Measurements Download a printable PDF Submitter: Long, C. N., Pacific Northwest National Laboratory Turner, D. D., National Oceanic and Atmospheric Administration Area of Research: Radiation Processes Working Group(s): Radiative Processes Journal Reference: Long, CN, and DD Turner. 2008. "A method for continuous estimation of clear-sky downwelling longwave radiative flux developed using ARM surface measurements." Journal of Geophysical Research 113, D18206, doi:10.1029/2008JD009936. Comparison of clear-sky RT model calculations (black) and our estimates (gray) with detected LW effective clear-sky measurements from the ACRF SGP site from 1 March through 31 May 2003, showing that our LW estimates do as well as detailed model calculations in comparison with actual LW

392

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Progress in Understanding Water Vapor's Role in Models Progress in Understanding Water Vapor's Role in Models Submitter: Ackerman, T. P., University of Washington Area of Research: General Circulation and Single Column Models/Parameterizations Working Group(s): Cloud Modeling Journal Reference: N/A Time-height cross sections of water vapor mixing ratio, which is observed directly by the ARM Raman lidar at 10-min and approximately 100 m resolution, and relative humidity for 29 November through 2 December 2002. The bottom panel shows the comparison of the precipitable water vapor observed by the Raman lidar and the collocated microwave radiometer. The time-height cross sections, as well as the integrated field, show the large variability in water vapor that exists over the ARM Southern Great Plains site. After years of sustained research efforts into the accuracy of atmospheric

393

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ARM M-PACE Data Used to Evaluate and Improve Arctic Mixed-Phase Clouds ARM M-PACE Data Used to Evaluate and Improve Arctic Mixed-Phase Clouds Simulated in Climate Models Download a printable PDF Submitter: Xie, S., Lawrence Livermore National Laboratory Area of Research: General Circulation and Single Column Models/Parameterizations Working Group(s): Cloud Modeling Journal Reference: Xie, S, J Boyle, SA Klein, X Liu, and S Ghan. 2008. "Simulations of Arctic mixed-phase clouds in forecasts with CAM3 and AM2 for M-PACE." Journal of Geophysical Research 113, D04211, doi:10.1029/2007JD009225. Time-height cross sections of active remote sensing cloud layer (ARSCL) cloud frequency (a) and modeled cloud fraction (b) CAM3, (c) AM2, and (d) CAM3LIU at Barrow during M-PACE. The unit is %. Liquid fraction as a function of cloud height. (a) UND citation data, (b)

394

Research Highlight  

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How Aerosols Affect Cloud Properties in Arctic Mixed-Phase Stratocumulus How Aerosols Affect Cloud Properties in Arctic Mixed-Phase Stratocumulus Download a printable PDF Submitter: McFarquhar, G., University of Illinois, Urbana Area of Research: Cloud-Aerosol-Precipitation Interactions Working Group(s): Cloud-Aerosol-Precipitation Interactions Journal Reference: Jackson RC, GM McFarquhar, AV Korolev, ME Earle, PS Liu, RP Lawson, S Brooks, M Wolde, A Laskin, and M Freer. 2012. "The dependence of ice microphysics on aerosol concentration in arctic mixed-phase stratus clouds during ISDAC and M-PACE." Journal of Geophysical Research - Atmospheres, 117, D15207, doi:10.1029/2012JD017668. Cloud mean ice crystal concentration Nice(D ≥ 50 micrometers) versus mean aerosol concentration (NPCASP) above cloud for all 41 vertical profiles

395

Research Highlight  

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CCN and Vertical Velocity Influences CCN and Vertical Velocity Influences Submitter: Hudson, J. G., Desert Research Institute Area of Research: Cloud-Aerosol-Precipitation Interactions Working Group(s): Cloud-Aerosol-Precipitation Interactions Journal Reference: Hudson JG and S Noble. 2013. "CCN and vertical velocity influences on droplet concentrations and supersaturations in clean and polluted stratus clouds." Journal of the Atmospheric Sciences, , . ACCEPTED. Figure 1. Effective cloud supersaturation (Seff) against CCN concentration at 1% S (N1%) for horizontal cloud penetrations, 50 for MASE and 34 for POST. Seff is the S for which nearby below cloud CCN spectra, NCCN(S), equals mean droplet concentration (Nc). Figure 2. One second droplet concentration, Nc, and vertical velocity

396

Research Highlight  

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ARM Science Applications of AERI Measurements ARM Science Applications of AERI Measurements Submitter: Smith, W. L., NASA - Langley Research Center Area of Research: Radiation Processes Working Group(s): Cloud Modeling Journal Reference: DeSlover, D. H. 1996. Analysis of Visible and Infrared Cirrus Cloud Optical Properties Using High Spectral Resolution Remote Sensing, M.S. Thesis, University of Wisconsin - Madison. Ho, S.-P. 1997. Atmospheric Profiles From Simultaneous Observations of Upwelling and Downwelling Spectral Radiance, Ph.D. Thesis, University of Wisconsin - Madison. Knuteson, R. O., F. A. Best, H. B. Howell, P. Minnett, H. E. Revercomb, W. L. Smith. 1997. "High Spectral Resolution Infrared Observations at the Ocean-Atmosphere Interface in the Tropical Western Pacific using a Marine

397

Research Highlight  

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Desert Dust Determines Aerial Spread of Thunderstorm Clouds Desert Dust Determines Aerial Spread of Thunderstorm Clouds Submitter: Bhattacharya, A., Pacific Northwest National Laboratory Area of Research: Cloud Distributions/Characterizations Working Group(s): Cloud Life Cycle Journal Reference: Zeng X, W Tao, SW Powell, RA Houze, P Ciesielski, N Guy, H Pierce, and T Matsui. 2013. "A comparison of the water budgets between clouds from AMMA and TWP-ICE." Journal of the Atmospheric Sciences, 70(2), doi:10.1175/JAS-D-12-050.1. The sun, seen through a dusty atmosphere, sets at Niamey, the capital of Niger, which is located in the African Sahara. Anvil clouds that accompany thunderstorms. Contrasts often provide unique perspectives, and scientists seize any such opportunity-when it arises. In a new research paper, published in the Journal of Atmospheric Sciences,

398

Research Highlight  

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Aerosols Help Heat Up the Yangtze River Delta in China Aerosols Help Heat Up the Yangtze River Delta in China Download a printable PDF Submitter: Flynn, C. J., Pacific Northwest National Laboratory Area of Research: Aerosol Properties Working Group(s): Aerosol Life Cycle Journal Reference: Liu J, Z Li, Y Zheng, C Flynn, and M Cribb. 2012. "Seasonal variations of aerosol optical properties, vertical distribution and associated radiative effects in the Yangtze Delta region of China." Journal of Geophysical Research, 117, D00K38, doi:10.1029/2011JD016490. A team of scientists found that aerosols significantly alter the vertical profile of solar heating in the central Yangtze River Delta region in eastern China. Aerosols were identified from as far away as Mongolia and Siberia. These findings have considerable implications for atmospheric

399

Research Highlight  

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Invisible Giants in the Sky Invisible Giants in the Sky Download a printable PDF Submitter: Ovink, J., Pacific Northwest National Laboratory Kassianov, E., Pacific Northwest National Laboratory Area of Research: Cloud-Aerosol-Precipitation Interactions Working Group(s): Cloud-Aerosol-Precipitation Interactions Journal Reference: Kassianov E, M Pekour, and J Barnard. 2012. "Aerosols in central California: Unexpectedly large contribution of coarse mode to aerosol radiative forcing." Geophysical Research Letters, 39, L20806, doi:10.1029/2012GL053469. Photo courtesy of the U.S. National Park Service Daily averaged values of (a, b) the direct aerosol radiative forcing (DARF) and (c, d) aerosol radiative forcing efficiency at the top-of-atmosphere calculated for the "original" aerosol optical properties (blue) and

400

Research Highlight  

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Structure of Cirrus Properties and Its Coupling with the State of the Structure of Cirrus Properties and Its Coupling with the State of the Large-Scale Atmosphere Download a printable PDF Submitter: Ivanova, K., Pennsylvania State University Ackerman, T. P., University of Washington Area of Research: Atmospheric Thermodynamics and Vertical Structures Working Group(s): Cloud Properties Journal Reference: Ivanova K and TP Ackerman. 2009. "Tracking nucleation-growth-sublimation in cirrus clouds using ARM millimeter wavelength radar observations." Journal of Geophysical Research - Atmospheres, , D06113, 10.1029/2008JD010271. Figure 1. Values of the drift and diffusion coefficients of the Fokker-Planck equation derived from the MMCR radar reflectivity observations. The diffusion coefficient characterizes the small scale, fast

Note: This page contains sample records for the topic "research vessel mirai" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

Research Highlight  

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Climatology of Aerosol Optical Depth in North-Central Oklahoma: Climatology of Aerosol Optical Depth in North-Central Oklahoma: 1992-2008 Download a printable PDF Submitter: Michalsky, J. J., DOC/NOAA/OAR/ESRL Area of Research: Aerosol Properties Working Group(s): Aerosol Life Cycle Journal Reference: Michalsky J, F Denn, C Flynn, G Hodges, P Kiedron, A Koontz, J Schlemmer, and SE Schwartz. 2010. "Climatology of aerosol optical depth in north-central Oklahoma: 1992-2008." Journal of Geophysical Research - Atmospheres, 115, D07203, doi: 10.1029/2009JD012197. Box plots of each complete year\'s daily averaged aerosol optical depth (AOD) at 500 nm. The dark horizontal line in each box plot is the median daily averaged AOD for the year; the top and bottom of the rectangular box spans the middle 50% of the data. The mean values for the year are plotted

402

Research Highlight  

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Variations of Meridional Aerosol Distribution and Solar Dimming Variations of Meridional Aerosol Distribution and Solar Dimming Download a printable PDF Submitter: Long, C. N., Pacific Northwest National Laboratory Kishcha, P., Tel-Aviv University Starobinets, B., Tel-Aviv University Kalashnikova, O., Jet Propulsion Laboratory Alpert, P., Tel-Aviv University Area of Research: Radiation Processes Working Group(s): Aerosol, Radiative Processes Journal Reference: Kishcha P, B Starobinets, O Kalashnikova, CN Long, and P Alpert. 2009. "Variations of meridional aerosol distribution and solar dimming." Journal of Geophysical Research - Atmospheres, 114, D00D14, 10.1029/2008JD010975. The distribution of four-year aerosol differences (δAOT/δFAOT) between the last four years (March 2004 - February 2008) and the first four years

403

Errvironmentaf Research  

Office of Legacy Management (LM)

online at www.sciencedirect.com online at www.sciencedirect.com Environmental Research 10 1 (2006) 3 4 4 1 Errvironmentaf Research Do scientists and fishermen collect the same size fish? Possible implications for exposure assessment Joanna urger^^^^', Michael ~ o c h f e l d ~ ~ ~ , Sean Christian W. ~ e i t n e r ~ . ~ , Stephen ~ e w e t t ~ , Daniel SnigarofP, Ronald snigarofff, Tim Starnrng, Shawn ~ a r ~ e f , Max ~ o b e r ~ * , Heloise chenelotd, Robert patrickh, Conrad D. volzi, James ~ e s t o d 'Division of Life Sciences, Rutgers University, 604 Allison Road, Piscataway, NJ 08854-8082, USA b~onsortium for Risk Evaluation with Stakeholder Participation (CRESP), and Environmental and Occupational Healrh Sciences Institute (EOHSI), Piscataway, NJ, USA CEnvironmental and Community Medicine, UMDNJ-Robert Wood Johnson Medical School, Piscataway, NJ 08854, USA

404

Research Highlight  

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Minimalist Approach to Modeling Complex Arctic Clouds Minimalist Approach to Modeling Complex Arctic Clouds Download a printable PDF Submitter: Shaw, R. A., Michigan Technological University - Physics Department Area of Research: Cloud-Aerosol-Precipitation Interactions Working Group(s): Cloud Life Cycle Journal Reference: Yang F, M Ovchinnikov, and RV Shaw. 2013. "Minimalist model of ice microphysics in mixed-phase stratiform clouds." Geophysical Research Letters, 40(14), doi:10.1002/grl.50700. Nordic winter landscape. Mixed-phase stratiform clouds are common features in the Arctic environment. They contain a mix of ice and "supercooled" water that, despite the freezing temperatures, remains in liquid form. Scientists aren't sure why these clouds exist in the Arctic for long periods of time, even while steadily losing ice particles through precipitation.

405

Research Highlight  

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Understanding Ice Formation in Arctic Mixed-Phase Boundary-Layer Clouds Understanding Ice Formation in Arctic Mixed-Phase Boundary-Layer Clouds During ISDAC Download a printable PDF Submitter: Ackerman, A., NASA - Goddard Institute for Space Studies Fridlind, A. M., NASA - Goddard Institute for Space Studies Area of Research: Cloud Distributions/Characterizations Working Group(s): Cloud-Aerosol-Precipitation Interactions Journal Reference: Avramov A, AS Ackerman, AM Fridlind, B van Diedenhoven, G Botta, K Aydin, J Verlinde, KV Alexei, W Strapp, GM McFarquhar, R Jackson, SD Brooks, A Glen, and M Wolde. 2011. "Towards ice formation closure in Arctic mixed-phase boundary layer clouds during ISDAC." Journal of Geophysical Research - Atmospheres, 116, D00T08, doi:10.1029/2011JD015910. Ice number size distributions as simulated (dendrites in red, aggregates in

406

Research Highlight  

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TOA Radiation Budget of Convective Core/Stratiform Rain/Anvil Clouds from TOA Radiation Budget of Convective Core/Stratiform Rain/Anvil Clouds from Deep Convection Download a printable PDF Submitter: Feng, Z., Pacific Northwest National Laboratory Dong, X., University of North Dakota Area of Research: Cloud Distributions/Characterizations Working Group(s): Cloud Life Cycle Journal Reference: Feng Z, XQ Dong, BK Xi, C Schumacher, P Minnis, and M Khaiyer. 2011. "Top-of-atmosphere radiation budget of convective core/stratiform rain and anvil clouds from deep convective systems." Journal of Geophysical Research - Atmospheres, 116, D23202, doi:10.1029/2011JD016451. An example of the hybrid classification process. (a) GOES IR temperature, (b) NEXRAD radar reflectivity at 2.5 km MSL, (c) cloud patch segmentation from GOES IR temperature (the color patches are identified as deep

407

Research Highlight  

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Shortwave Absorption in Tropical Clouds Shortwave Absorption in Tropical Clouds Download a printable PDF Submitter: McFarlane, S. A., U.S. Department of Energy Mather, J. H., Pacific Northwest National Laboratory Ackerman, T. P., University of Washington Liu, Z., University of Washington Area of Research: Cloud Distributions/Characterizations Working Group(s): Radiative Processes Journal Reference: McFarlane, SA, JH Mather, TP Ackerman, and Z Liu. 2008. "Effect of clouds on the vertical distribution of SW absorption in the Tropics." Journal of Geophysical Research, in press. Daily average all-sky and clear-sky calculated SW column absorption at Manus and Nauru. On average, there is little difference in absorption between the all-sky and clear-sky conditions because of the compensating

408

Research Highlight  

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Broadband Albedo Observations in the Southern Great Plains Broadband Albedo Observations in the Southern Great Plains Submitter: Lamb, P. J., University of Oklahoma Area of Research: Aerosol Properties Working Group(s): Aerosol Journal Reference: Journal of Applied Meteorology and Climatology, Vol. 45, 2006, pp. 210-235. Figure 1 Figure 2 Because surface reflection of solar radiation plays a fundamental role in the surface energy budget, knowledge of its spatial and temporal variability is important for understanding the weather and climate of a specific region. Research instrumentation at the U.S. Southern Great Plains site-one of three locales around the world managed by the U.S. Department of Energy's Atmospheric Radiation Measurement Program-continuously collects these types of data to help scientist investigate differences in

409

Research Highlight  

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Direct Aerosol Forcing: Calculation from Observables and Sensitivities to Direct Aerosol Forcing: Calculation from Observables and Sensitivities to Inputs Download a printable PDF Submitter: McComiskey, A. C., National Oceanic and Atmospheric Administration Area of Research: Aerosol Properties Working Group(s): Aerosol Journal Reference: McComiskey, A, SE Schwartz, B Schmid, H Guan, ER Lewis, P Ricchiazzi, and JA Ogren. 2008. "Direct aerosol forcing: Calculation from observables and sensitivities to inputs." Journal of Geophysical Research 113, D09202, doi:10.1029/2007JD009170. Figure 1. The sensitivity of calculated aerosol direct radiative forcing to input parameters has been examined to determine the consequences of uncertainties in these input parameters on calculated radiative forcing and to identify areas where measurements might be most profitably improved. Input

410

Research Highlight  

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Measured Radiative Cooling from Reflective Roofs in India Measured Radiative Cooling from Reflective Roofs in India Download a printable PDF Submitter: Fischer, M. L., Lawrence Berkeley National Laboratory Area of Research: Radiation Processes Working Group(s): Aerosol Life Cycle, Cloud Life Cycle, Cloud-Aerosol-Precipitation Interactions Journal Reference: Salamanca F, S Tonse, S Menon, V Garg, KP Singh, M Naja, and ML Fischer. 2012. "Top-of-atmosphere radiative cooling with white roofs: Experimental verification and model-based evaluation." Environmental Research Letters, 7(4), 044007, doi:10.1088/1748-9326/7/4/044007. True color image of light (PW1, PW2) and unpainted tar (PD1), and concrete (PD2) roofs at the Pantnagar, India site taken on October 21, 2011. We note that the concrete roof is considerably more reflective than the tar roof

411

Research Highlight  

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Evaluate the Diurnal Cycle in the Multiscale Modeling Framework Using Evaluate the Diurnal Cycle in the Multiscale Modeling Framework Using Satellite and ARM Data Download a printable PDF Submitter: Zhang, Y., Lawrence Livermore National Laboratory Klein, S., Lawrence Livermore National Laboratory Area of Research: General Circulation and Single Column Models/Parameterizations Working Group(s): Cloud Modeling Journal Reference: Zhang, Y, SA Klein, C Liu, B Tian, RT Marchand, JM Haynes, RB McCoy, Y Zhang, and TP Ackerman. 2008. "On the diurnal cycle of deep convection, high-level cloud, and upper troposphere water vapor in the Multiscale Modeling Framework." Journal of Geophysical Research 113, D16105, doi:10.1029/2008JD009905. Figure 1: Diurnal anomalies for tropical (left) ocean and (right) land: (top) the precipitation index (PI), high-level cloud (CLD) and upper

412

Research Highlight  

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Climate Warming Due to Soot and Smoke? Maybe Not. Climate Warming Due to Soot and Smoke? Maybe Not. Submitter: Penner, J. E., University of Michigan Area of Research: Aerosol Properties Working Group(s): Aerosol Journal Reference: Penner, J.E., S.Y. Zhang, and C.C. Chuang, Soot and smoke aerosol may not warm climate, J. Geophys. Res., 108(D21), 4657, doi:10.1029/2003JD003409, 2003. New research results from the Department of Energy's Atmospheric Radiation Measurement (ARM) Program suggest that fossil fuel soot emissions and biomass smoke may actually have a negligible warming effect and, in some cases, may even result in a net cooling effect. Black carbon is the absorbing component of smoke aerosols that result from the incomplete combustion of various fuels, the most significant sources being fossil fuel

413

Research Highlight  

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Exploring Parameterization for Turbulent Entrainment-Mixing Processes in Exploring Parameterization for Turbulent Entrainment-Mixing Processes in Clouds Download a printable PDF Submitter: Liu, Y., Brookhaven National Laboratory Lu, C., Brookhaven National Laboratory Area of Research: Cloud-Aerosol-Precipitation Interactions Working Group(s): Cloud Life Cycle, Cloud-Aerosol-Precipitation Interactions Journal Reference: Lu C, S Niu, S Krueger, and T Wagner. 2013. "Exploring parameterization for turbulent entrainment-mixing processes in clouds." Journal of Geophysical Research - Atmospheres, 118(1), doi:10.1029/2012JD018464. Relationships between the three microphysical measures of homogeneous mixing degree (ψ1, ψ2, ψ3) and the two transition scale numbers (NLa, NL0), respectively. The results shown here are from the EMPM simulations.

414

Research Highlight  

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Surface Summertime Radiative Forcing by Shallow Cumuli at the ARM SGP Surface Summertime Radiative Forcing by Shallow Cumuli at the ARM SGP Download a printable PDF Submitter: Berg, L., Pacific Northwest National Laboratory Area of Research: Radiation Processes Working Group(s): Cloud Life Cycle Journal Reference: Berg LK, EI Kassianov, CN Long, and DL Mills. 2011. "Surface summertime radiative forcing by shallow cumuli at the ARM SGP." Journal of Geophysical Research - Atmospheres, 116, D01202, 10.1029/2010JD014593. Histogram of hourly average shortwave CRF (black) and longwave CRF (red) for all periods with shallow cumuli. (a) Hourly average shortwave CRF (circles), binned shortwave CRF (squares); (b) total number of hourly averages for each sky cover bin; and (c) the change in shortwave TED as a function of sky cover for all hours with

415

Research Highlight  

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Estimating Fractional Sky Cover from Spectral Measurements Estimating Fractional Sky Cover from Spectral Measurements Download a printable PDF Submitter: Long, C. N., Pacific Northwest National Laboratory Min, Q., State University of New York, Albany Wang, T., State University of New York, Albany Duan, M., Institute of Atmospheric Physics/Chinese Academy of Science Area of Research: Cloud Distributions/Characterizations Working Group(s): Radiative Processes Journal Reference: Min Q, T Wang, CN Long, and M Duan. 2008. "Estimating fractional sky cover from spectral measurements." Journal of Geophysical Research - Atmospheres, 113, D20208, doi:10.1029/2008JD010278. Retrieved and observed cloud fractions and corresponding TSI cloud imagers on 8 July 2005 at Pt. Reyes. Scatterplot of retrieved cloud fraction from spectral ratio method and SW

416

Research Highlight  

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Development and Recent Evaluation of the MT_CKD Model of Continuum Development and Recent Evaluation of the MT_CKD Model of Continuum Absorption Download a printable PDF Submitter: Mlawer, E. J., Atmospheric & Environmental Research, Inc. Area of Research: Radiation Processes Working Group(s): Cloud Life Cycle Journal Reference: Mlawer EJ, VH Payne, J Moncet, JS Delamere, MJ Alvarado, and DD Tobin. 2012. "Development and recent evaluation of the MT_CKD model of continuum absorption." Philosophical Transactions of The Royal Society A, 370, doi: 10.1098/rsta.2011.0295. For seven AERI cases with 4-6 cm PWV: (a) average AERI radiances (black) and corresponding calculations using radiation code with previous version of MT_CKD continuum model (red); (b) residuals between AERI and calculations with older model; (c) residuals after the CO2 continuum in

417

Research Highlight  

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Field Campaign Resource Allocation Using Statistical Decision Analysis Field Campaign Resource Allocation Using Statistical Decision Analysis Download a printable PDF Submitter: Hanlon, C., Pennsylvania State University Area of Research: Cloud Processes Working Group(s): Cloud Life Cycle Journal Reference: Hanlon CJ, JB Stefik, AA Small, J Verlinde, and GS Young. 2013. "Statistical decision analysis for flight decision support: The SPartICus campaign." Journal of Geophysical Research - Atmospheres, , . ACCEPTED. In many atmospheric science field campaigns, investigators are budgeted some number of flight hours to collect data under specific, imperfectly forecastable atmospheric conditions. In such field campaigns, investigators must assess atmospheric conditions each day and make a resource-allocation decision: are conditions good enough to use some of our scarce flight hours

418

Research Highlight  

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Clouds Brighten Up the Sky Near Them Clouds Brighten Up the Sky Near Them Download a printable PDF Submitter: Varnai, T., University of Maryland, Baltimore County/JCEST Marshak, A., NASA - Goddard Space Flight Center Area of Research: Radiation Processes Working Group(s): Radiative Processes Journal Reference: Varnai T and A Marshak. 2009. "MODIS observations of enhanced clear sky reflectance near clouds." Geophysical Research Letters, 36, L06807, doi:10.1029/2008GL037089. Figure 1. Illustration of clouds enhancing the brightness of sky in nearby clear areas. In cloud-free areas light is scattered mainly by air molecules, but aerosols also contribute. Figure 2. Top: Average increase in MODIS clear-sky reflectivity (R) near clouds. The difference between areas near illuminated and shadowy cloud

419

Research Highlight  

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Cloud-Resolving Model (CRM) Simulations: Robust Results for Use in Climate Cloud-Resolving Model (CRM) Simulations: Robust Results for Use in Climate Model Development Download a printable PDF Submitter: Fridlind, A. M., NASA - Goddard Institute for Space Studies Smith-Mrowiec, A. A., Columbia University/NASA Goddard Institute for Space Studies Area of Research: Cloud Processes Working Group(s): Cloud Life Cycle, Cloud-Aerosol-Precipitation Interactions Journal Reference: Mrowiec AA, C Rio, AM Fridlind, AS Ackerman, AD Del Genio, OM Pauluis, AC Varble, and J Fan. 2012. "Analysis of cloud-resolving simulations of a tropical mesoscale convective system observed during TWP-ICE: Vertical fluxes and draft properties in convective and stratiform regions." Journal of Geophysical Research, 117, D19201, doi:10.1029/2012JD017759.

420

Research Highlight  

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A Downwelling Infrared Radiance Climatology for the ARM Southern Great A Downwelling Infrared Radiance Climatology for the ARM Southern Great Plains Site Download a printable PDF Submitter: Turner, D. D., National Oceanic and Atmospheric Administration Gero, J., University of Wisconsin Area of Research: Radiation Processes Working Group(s): Cloud Life Cycle Journal Reference: Turner DD and PJ Gero. 2011. "Downwelling infrared radiance temperature climatology for the Atmospheric Radiation Measurement Southern Great Plains site." Journal of Geophysical Research - Atmospheres, 116, D08212, doi:10.1029/2010JD015135. The distribution of downwelling 10-micron infrared radiance observed at the SGP site by the AERI from June 1996 to May 2010, separated into all-sky (all samples) and the three distinct sky classifications.

Note: This page contains sample records for the topic "research vessel mirai" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


421

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

"Invisible" Giants in the Sky "Invisible" Giants in the Sky Download a printable PDF Submitter: Kassianov, E., Pacific Northwest National Laboratory Area of Research: Radiation Processes Working Group(s): Aerosol Life Cycle Journal Reference: Kassianov E, M Pekour, and J Barnard. 2012. "Aerosols in central California: Unexpectedly large contribution of coarse mode to aerosol radiative forcing." Geophysical Research Letters, 39, L20806, doi:10.1029/2012GL053469. Daily averaged values of (a, b) the direct aerosol radiative forcing (DARF) and (c, d) aerosol radiative forcing efficiency at the top-of-atmosphere calculated for the "original" aerosol optical properties (blue) and their PM1.0 (red) and PM2.5 (green) counterparts at the CARES (left) T0 and (right) T1 sites.

422

Research Highlight  

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A New Method for Satellite/Surface Comparisons A New Method for Satellite/Surface Comparisons Download a printable PDF Submitter: Long, C. N., Pacific Northwest National Laboratory Area of Research: Radiation Processes Working Group(s): Cloud Properties, Radiative Processes Journal Reference: Zhang Y, CN Long, WB Rossow, and EG Dutton. 2010. "Exploiting diurnal variations to evaluate the ISCCP-FD flux calculations and radiative-flux-analysis-processed surface observations from BSRN, ARM, and SURFRAD." Journal of Geophysical Research - Atmospheres, 115, D00K11, 10.1029/2009JD012812. Figure 1: Scatter plot for the column aerosol optical depth (AOD) at 550 nm, measured at the surface (PSO) and used as input for the ISCCP-FD calculations (FD) at 10 ARM/SURFRAD/BSRN stations. The robust linear regression line is also shown.

423

Research Highlight  

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Cumuli Impact on Solar Radiation at Surface: Spectral Changes Cumuli Impact on Solar Radiation at Surface: Spectral Changes Download a printable PDF Submitter: Kassianov, E., Pacific Northwest National Laboratory Area of Research: Aerosol Properties Working Group(s): Aerosol Life Cycle, Cloud Life Cycle, Cloud-Aerosol-Precipitation Interactions Journal Reference: Kassianov E, J Barnard, LK Berg, CN Long, and C Flynn. 2011. "Shortwave spectral radiative forcing of cumulus clouds from surface observations." Geophysical Research Letters, 38, L07801, doi:10.1029/2010GL046282. Figure 1. Normalized total cloud radiative forcing and its direct and diffuse components as a function of wavelength. Typically, under cloudy conditions, radiative transfer parameterizations in climate models have been evaluated by calculating the total cloud impact on

424

Joint EPRI-CEA Research on Small Punch Testing for Nuclear Application  

Science Conference Proceedings (OSTI)

A joint research project between EPRI and the Commissariat a l'Energie Atomique (CEA) has been under way since 1998 to compare the fracture behavior of reactor pressure vessel (RPV) materials in the transition region as tested by a subsize impact test (Charpy) and subsize specimen techniques. This report summarizes the progress made under this joint effort.

2001-12-13T23:59:59.000Z

425

Design, fabrication and testing of a model heating and cooling system for a vacuum vessel  

SciTech Connect

A full-size model of a typical cooling and heating system for a vacuum vessel was manufactured and examined in order to clarify and enhance the efficiency and reliability of the designed system. The model consisted of two parts; one of which had the same structure as the other and was located facing each other to simulate the adiabatic condition of the vacuum-side of a vacuum vessel. Its components were rectangular plates, eletric heater units, cooling pipes inside of which water and air flew as cooling fluid. A lot of kinds of tests and measurements were performed to evaluate efficiency and reliability on the model. The numerical and theoretical analyses on the system were also carried out using the dimensional finite difference technique. The analytical results agreed pretty well with the experimental.

Shimizu, M.; Miyauchi, Y.; Nakamura, H.; Kajiura, S.; Koizumi, M.; Hata, M.

1981-01-01T23:59:59.000Z

426

Vessel-Spanning Bubble Formation in K-Basin Sludge Stored in Large-Diameter Containers  

DOE Green Energy (OSTI)

The K Basin sludge to be retrieved and stored in the large diameter containers (LDCs) contains some fraction of uranium metal that generates hydrogen gas, which introduces potential upset conditions. One postulated upset condition is a rising plug of sludge supported by a hydrogen bubble that is driven into the vent filters at the top of the container. In laboratory testing with actual K Basin sludge, vessel-spanning bubbles that lifted plugs of sludge were observed in 3-inch-diameter graduated cylinders. This report presents a series of analytical assessments performed by the Pacific Northwest National Laboratory to address the potential for the generation of a vessel spanning bubble in the LDCs. The assessments included the development and evaluation of static and dynamic bubble formation models over the projected range of K Basin sludge physical properties. Additionally, the theory of circular plates was extrapolated to examine conditions under which a plug of sludge would collapse and release a spanning bubble.

Terrones, Guillermo; Gauglitz, Phillip A.

2002-03-01T23:59:59.000Z

427

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

Science Conference Proceedings (OSTI)

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.

Cannell, Gary L. [Fluor Enterprises, Inc.; Huth, Ralph J. [CH2MHill Plateau Remediation Company; Hallum, Randall T. [Fluor Government Group

2013-08-26T23:59:59.000Z

428

Passive air cooling of liquid metal-cooled reactor with double vessel leak accommodation capability  

DOE Patents (OSTI)

A passive and inherent shutdown heat removal method with a backup air flow path which allows decay heat removal following a postulated double vessel leak event in a liquid metal-cooled nuclear reactor is disclosed. The improved reactor design incorporates the following features: (1) isolation capability of the reactor cavity environment in the event that simultaneous leaks develop in both the reactor and containment vessels; (2) a reactor silo liner tank which insulates the concrete silo from the leaked sodium, thereby preserving the silo`s structural integrity; and (3) a second, independent air cooling flow path via tubes submerged in the leaked sodium which will maintain shutdown heat removal after the normal flow path has been isolated. 5 figures.

Hunsbedt, A.; Boardman, C.E.

1995-04-11T23:59:59.000Z

429

Passive air cooling of liquid metal-cooled reactor with double vessel leak accommodation capability  

SciTech Connect

A passive and inherent shutdown heat removal method with a backup air flow path which allows decay heat removal following a postulated double vessel leak event in a liquid metal-cooled nuclear reactor. The improved reactor design incorporates the following features: (1) isolation capability of the reactor cavity environment in the event that simultaneous leaks develop in both the reactor and containment vessels; (2) a reactor silo liner tank which insulates the concrete silo from the leaked sodium, thereby preserving the silo's structural integrity; and (3) a second, independent air cooling flow path via tubes submerged in the leaked sodium which will maintain shutdown heat removal after the normal flow path has been isolated.

Hunsbedt, Anstein (Los Gatos, CA); Boardman, Charles E. (Saratoga, CA)

1995-01-01T23:59:59.000Z

430

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

SciTech Connect

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

Loftin, Bradley [Savannah River National Laboratory; Koenig, Richard [Savannah River National Laboratory

2013-08-08T23:59:59.000Z

431

EERE Postdoctoral Research Awards: Postdoctoral Research Awards...  

NLE Websites -- All DOE Office Websites (Extended Search)

Postdoctoral Research Awards: Investing in Innovative Clean Energy Technologies to someone by E-mail Share EERE Postdoctoral Research Awards: Postdoctoral Research Awards:...

432

Sandia National Labs: PCNSC: Research: Research Briefs  

NLE Websites -- All DOE Office Websites (Extended Search)

Research Briefs The annually published Physical, Chemical, and Nano Sciences Center Research Briefs highlights recent accomplishments supporting our missions. Our research focuses...

433

NREL: Wind Research - Large Wind Turbine Research  

NLE Websites -- All DOE Office Websites (Extended Search)

Wind Research Search More Search Options Site Map Printable Version Large Wind Turbine Research NREL's utility scale wind system research addresses performance and...

434

Human Subjects Research, Office of Research Administration  

NLE Websites -- All DOE Office Websites (Extended Search)

research includes a wide variety of activities such as in vivo and in vitro studies, research on medical records, collection of data through surveys or observation, research...

435

Materials Reliability Program, Reactor Vessel Head Boric Acid Corrosion Testing (MRP-165)  

Science Conference Proceedings (OSTI)

Pressurized water reactor (PWR) coolant leakage from stress corrosion cracking of an Alloy 600 control rod drive mechanism (CRDM) penetration has led to one case of severe corrosion and cavity formation in a low-alloy steel reactor vessel head (RVH). The detailed progression of RVH wastage following initial leakage is complicated and probably involves several corrosion mechanisms. The Materials Reliability Program (MRP) has completed three tasks of a comprehensive program to examine postulated sequential...

2005-12-14T23:59:59.000Z

436

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

DOE Patents (OSTI)

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.

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

2013-01-15T23:59:59.000Z

437

Qualification of in-service examination of the Yankee Rowe reactor pressure vessel  

SciTech Connect

Technical support was provided to assist the Yankee Atomic Electric Company with their restart effort for the Yankee plant in Rowe, Massachusetts. Demonstration of adequate margin during a postulated pressurized thermal shock accident was an important part of the justification for restarting the plant, and effective inservice examination of the critical inner surface of the vessel in the beltline region was a key objective and a significant component of the safety analysis. This report discussed this inservice inspection.

Ammirato, F.; Kietzman, K.; Becker, L.; Ashwin, P.; Selby, G.; Krzywosz, K.; Findlan, S. (Electric Power Research Inst., Charlotte, NC (United States). Nondestructive Evaluation Center); Lance, J. (Yankee Atomic Electric Co., Bolton, MA (United States))

1992-12-01T23:59:59.000Z

438

Analysis of the ANL Test Method for 6CVS Containment Vessels  

Science Conference Proceedings (OSTI)

In the fall of 2010, Argonne National Laboratory (ANL) contracted with vendors to design and build 6CVS containment vessels as part of their effort to ship Fuel Derived Mixed Fission Product material. The 6CVS design is based on the Savannah River National Laboratory's (SRNL) design for 9975 and 9977 six inch diameter containment vessels. The main difference between the designs is that the 6CVS credits the inner O-ring seal as the containment boundary while the SRNL design credits the outer O-ring seal. Since the leak test must be done with the inner O-ring in place, the containment vessel does not have a pathway for getting the helium into the vessel during the leak test. The leak testing contractor was not able to get acceptable leak rates with the specified O-ring, but they were able to pass the leak test with a slightly larger O-ring. ANL asked the SRNL to duplicate the leak test vendor's method to determine the cause of the high leak rates. The SRNL testing showed that the helium leak indications were caused by residual helium left within the 6CVS Closure Assembly by the leak test technique, and by helium permeation through the Viton O-ring seals. After SRNL completed their tests, the leak testing contractor was able to measure acceptable leak rates by using the slightly larger O-ring size, by purging helium from the lid threads, and by being very quick in getting the bell jar under a full vacuum. This paper describes the leak test vendor's test technique, and other techniques that could be have been used to successfully leak test the 6CVS's.

Trapp, D.; Crow, G.

2011-06-06T23:59:59.000Z

439

AUTHORIZATION OF THE TROJAN REACTOR VESSEL PACKAGE FOR ONE-TIME SHIPMENT FOR DISPOSAL (1)  

E-Print Network (OSTI)

Request Commission approval, by negative consent, for the staff to grant two specific exemptions from package test requirements specified in 10 CFR Part 71 for the Trojan Reactor Vessel Package (TRVP), and to authorize the TRVP for one-time transport for disposal. BACKGROUND: Portland General Electric Company (PGE) has requested approval of the TRVP (including internals) for transport to the disposal facility operated by US

L. Joseph; Callan Executive; Director Operations; John R. Cook

1998-01-01T23:59:59.000Z

440

Materials Reliability Program: San Onofre Nuclear Generating Station Reactor Vessel Internals Management Engineering Program (MRP-303)  

Science Conference Proceedings (OSTI)

All operating pressurized water reactors must have a reactor vessel internals aging management document in place by December 2011 according to the mandatory requirement under Nuclear Energy Institute (NEI) 03-08. This program should be developed to meet the guidance provided by Materials Reliability Program (MRP) -227, Rev. 0, Pressurized Water Reactor Internals Inspection and Evaluation Guidelines. For non-license renewal plants, the requirements are valid within the current license period, and the Elec...

2011-02-28T23:59:59.000Z

Note: This page contains sample records for the topic "research vessel mirai" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


441

Materials Reliability Program: Reactor Vessel Head Boric Acid Corrosion Testing (MRP-199)  

Science Conference Proceedings (OSTI)

PWR coolant leakage from stress corrosion cracking of an Alloy 600 control rod drive mechanism (CRDM) penetration has led to one case of severe corrosion and cavity formation in a low-alloy steel reactor vessel head (RVH). The detailed progression of RVH wastage following initial leakage is complicated and probably involves several corrosion mechanisms. The Materials Reliability Program (MRP) has completed three tasks of a comprehensive program to examine postulated sequential stages of boric acid corros...

2007-06-27T23:59:59.000Z

442

Materials Reliability Program: Destructive Examination of the North Anna 2 Reactor Pressure Vessel Head (MRP-198)  

Science Conference Proceedings (OSTI)

This document is the final of three reports concerning the nondestructive and destructive examinations of selected control rod drive mechanism (CRDM) penetrations from the decommissioned North Anna Unit 2 reactor vessel head (RVH). The phase-1 report of the EPRI-MRP (Materials Reliability Program) managed program described the selection and removal of penetrations from the decommissioned RVH and the penetration decontamination and laboratory nondestructive evaluation (NDE). The phase-2 report detailed th...

2006-11-13T23:59:59.000Z

443

Materials Reliability Program: Utility Preparation for Nondestructive Evaluation of Reactor Vessel Upper Head Penetrations (MRP-360)  

Science Conference Proceedings (OSTI)

The purpose of this report is to provide nuclear power plant owners with recommendations for planning and executing reactor vessel upper head (RVUH) penetration examinations in a manner that will minimize the occurrence of human errors while maximizing the probability of success. RVUH penetrations include control rod drive mechanism, control element drive mechanism, in-core instrumentation, and vent line penetrations. These encompass the standard nomenclatures for domestic utilities but might not ...

2013-12-19T23:59:59.000Z

444

Trojan Nuclear Power Plant Reactor Vessel and Internals Removal: Trojan Nuclear Plant Decommissioning Experience  

Science Conference Proceedings (OSTI)

One goal of the EPRI Decommissioning Technology Program is to capture the growing utility experience in nuclear plant decommissioning activities for the benefit of other utilities facing similar challenges in the future. This report provides historical information on the background, scope, organization, schedule, cost, contracts, and support activities associated with the Trojan Nuclear Plant Reactor Vessel and Internals Removal (RVAIR) Project. Also discussed are problems, successes, and lessons learned...

2000-10-16T23:59:59.000Z

445

BWRVIP-118: BWR Vessel and Internals Project: NMCA Experience Report and Applications Guidelines, 2003 Revision  

Science Conference Proceedings (OSTI)

The boiling water reactor (BWR) fleet has widely embraced noble metal chemical addition (NMCA) to provide protection against intergranular stress corrosion cracking (IGSCC). This report, prepared by a Boiling Water Reactor Vessel and Internals Project (BWRVIP) focus group, updates a report issued in 2001 that compiled data from plants operating on NMCA. It provides guidance for BWRs planning to implement NMCA, and information about expected plant response to operation with NMCA. It also identifies steps ...

2003-11-24T23:59:59.000Z

446

File:06HIGBoilerPressureVesselPermit.pdf | Open Energy Information  

Open Energy Info (EERE)

HIGBoilerPressureVesselPermit.pdf HIGBoilerPressureVesselPermit.pdf Jump to: navigation, search File File history File usage File:06HIGBoilerPressureVesselPermit.pdf Size of this preview: 463 × 599 pixels. Other resolution: 464 × 600 pixels. Full resolution ‎(1,275 × 1,650 pixels, file size: 47 KB, MIME type: application/pdf) File history Click on a date/time to view the file as it appeared at that time. Date/Time Thumbnail Dimensions User Comment current 09:08, 24 October 2012 Thumbnail for version as of 09:08, 24 October 2012 1,275 × 1,650 (47 KB) Dklein2012 (Talk | contribs) 12:32, 23 October 2012 Thumbnail for version as of 12:32, 23 October 2012 1,275 × 1,650 (47 KB) Dklein2012 (Talk | contribs) 16:30, 24 July 2012 Thumbnail for version as of 16:30, 24 July 2012 1,275 × 1,650 (44 KB) Alevine (Talk | contribs)

447

A Flaw Tolerance Approach to Address Reactor Vessel Head Penetration Cracking Issue  

SciTech Connect

Nickel-based alloys and the associated welds are susceptible to Primary Water Stress Corrosion Cracking. In Pressurized Water Reactor nuclear power plants, the reactor vessel closure head upper penetration nozzles used for the Control Rod Drive Mechanisms and other instrumentation systems are made of such nickel-based alloys. Cracking and leakage have been observed in the upper head penetration nozzles in nuclear power plants worldwide. Such cracking and the resulting leakage is a degradation of the reactor vessel pressure boundary. Regulatory requirements have been issued by the Nuclear Regulatory Commission regarding periodic inspection of the susceptible areas to enable detection of indications and provide reasonable assurance of continued structural integrity for reactor vessel closure head. A flaw tolerance approach has been used in the disposition of detected indications to minimize outage delays, by performing up-front fracture mechanics evaluations for the common types of indications detected in the susceptible areas. Details of the flaw tolerance approach are presented in this paper. (authors)

Ng, C. K.; Jirawongkraisorn, S.; Swamy, S. [Westinghouse Electric Company, LLC, Nuclear Services Division, P. O. Box 158, Madison, PA 15663 (United States)

2006-07-01T23:59:59.000Z

448

DESIGN OF A CONTAINMENT VESSEL CLOSURE FOR SHIPMENT OF TRITIUM GAS  

SciTech Connect

This paper presents a design summary of the containment vessel closure for the Bulk Tritium Shipping Package (BTSP). This new 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 new design is based on changes in the regulatory requirements. The BTSP design incorporates many improvements over its predecessor by implementing improved testing, handling, and maintenance capabilities, while improving manufacturability and incorporating new engineered materials that enhance the package's ability to withstand dynamic loading and thermal effects. This paper will specifically summarize the design philosophy and engineered features of the BTSP containment vessel closure. The closure design incorporates a concave closure lid, metallic C-Ring seals for containing tritium gas, a metal bellows valve and an elastomer O-Ring for leak testing. The efficient design minimizes the overall vessel height and protects the valve housing from damage during postulated drop and crush scenarios. Design features will be discussed.

Eberl, K; Paul Blanton, P

2007-07-03T23:59:59.000Z

449

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

DOE Patents (OSTI)

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

Hubble, D.H.; Ulrich, K.H.

1998-09-22T23:59:59.000Z

450

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

DOE Patents (OSTI)

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

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

1998-01-01T23:59:59.000Z

451

HYDROGEN EFFECTS ON THE BURST PROPERTIES OF TYPE 304L STAINLESS STEEL FLAWED VESSELS  

DOE Green Energy (OSTI)

The effect of hydrogen on the burst properties Type 304L stainless steel vessels was investigated. The purpose of the study was to compare the burst properties of hydrogen-exposed stainless steel vessels burst with different media: water, helium gas, or deuterium gas. A second purpose of the tests was to provide data for the development of a predictive finite-element model. The burst tests were conducted on hydrogen-exposed and unexposed axially-flawed cylindrical vessels. The results indicate that samples burst pneumatically had lower volume ductility than those tested hydraulically. Deuterium gas tests had slightly lower ductility than helium gas tests. Burst pressures were not affected by burst media. Hydrogen-charged samples had lower volume ductility and slightly higher burst pressures than uncharged samples. Samples burst with deuterium gas fractured by quasi-cleavage near the inside wall. The results of the tests were used to improve a previously developed predictive finite-element model. The results show that predicting burst behavior requires as a material input the effect of hydrogen on the plastic strain to fracture from tensile tests. The burst test model shows that a reduction in the plastic strain to fracture of the material will result in lower volume ductility without a reduction in burst pressure which is in agreement with the burst results.

Morgan, M; Monica Hall, M; Ps Lam, P; Dean Thompson, D

2008-03-27T23:59:59.000Z

452

Fabrication Flaw Density and Distribution In Repairs to Reactor Pressure Vessel and Piping Welds  

Science Conference Proceedings (OSTI)

The Pacific Northwest National Laboratory is developing a generalized fabrication flaw distribution for the population of nuclear reactor pressure vessels and for piping welds in U.S. operating reactors. The purpose of the generalized flaw distribution is to predict component-specific flaw densities. The estimates of fabrication flaws are intended for use in fracture mechanics structural integrity assessments. Structural integrity assessments, such as estimating the frequency of loss-of-coolant accidents, are performed by computer codes that require, as input, accurate estimates of flaw densities. Welds from four different reactor pressure vessels and a collection of archived pipes have been studied to develop empirical estimates of fabrication flaw densities. This report describes the fabrication flaw distribution and characterization in the repair weld metal of vessels and piping. This work indicates that large flaws occur in these repairs. These results show that repair flaws are complex in composition and sometimes include cracks on the ends of the repair cavities. Parametric analysis using an exponential fit is performed on the data. The relevance of construction records is established for describing fabrication processes and product forms. An analysis of these records shows there was a significant change in repair frequency over the years when these components were fabricated. A description of repair flaw morphology is provided with a discussion of fracture mechanics significance. Fabrication flaws in repairs are characterized using optimized-access, high-sensitivity nondestructive ultrasonic testing. Flaw characterizations are then validated by other nondestructive evaluation techniques and complemented by destructive testing.

GJ Schuster, FA Simonen, SR Doctor

2008-04-01T23:59:59.000Z

453

Advanced Research  

NLE Websites -- All DOE Office Websites (Extended Search)

Ductility EnhancEmEnt of molybDEnum Ductility EnhancEmEnt of molybDEnum PhasE by nano-sizED oxiDE DisPErsions Description Using computational modeling techniques, this research aims to develop predictive capabilities to facilitate the design and optimization of molybdenum (Mo), chromium (Cr), and other high-temperature structural materials to enable these materials to withstand the harsh environments of advanced power generation systems, such as gasification-based systems. These types of materials are essential to the development of highly efficient, clean energy technologies such as low-emission power systems that use coal or other fossil fuels.

454

Advanced Research  

NLE Websites -- All DOE Office Websites (Extended Search)

Super HigH-TemperaTure alloyS and Super HigH-TemperaTure alloyS and CompoSiTeS From nb-W-Cr SySTemS Description The U.S. Department of Energy's Office of Fossil Energy (DOE-FE) has awarded a three-year grant to the University of Texas at El Paso (UTEP) and Argonne National Laboratory (ANL) to jointly explore the high-temperature properties of alloys composed of niobium (Nb), tungsten (W), and chromium (Cr). The grant is administered by the Advanced Research (AR) program of the National

455

Sandia National Laboratories: Research: Research Foundations...  

NLE Websites -- All DOE Office Websites (Extended Search)

Geoscience Materials Science Nanodevices and Microsystems Radiation Effects and High Energy Density Science Research Geoscience Geoscience photo The Geoscience Research...

456

Measurement of Wind Waves and Wave-Coherent Air Pressures on the Open Sea from a Moving SWATH Vessel  

Science Conference Proceedings (OSTI)

The design and implementation on a Small Waterline Area Twin Hull (SWATH) vessel of a complete system for measuring the directional distribution of wind waves and the concomitant fluctuations of air pressure and wind speed immediately above them ...

Mark A. Donelan; Fred W. Dobson; Hans C. Graber; Niels Madsen; Cyril McCormick

2005-07-01T23:59:59.000Z

457

Investigation of downward facing critical heat flux with water-based nanofluids for In-Vessel Retention applications.  

E-Print Network (OSTI)

??In-Vessel Retention ("IVR") is a severe accident management strategy that is power limiting to the Westinghouse AP1000 due to critical heat flux ("CHF") at the (more)

DeWitt, Gregory L

2011-01-01T23:59:59.000Z

458

Investigation of the use of nanofluids to enhance the In-Vessel Retention capabilities of Advanced Light Water Reactors  

E-Print Network (OSTI)

Nanofluids at very low concentrations experimentally exhibit a substantial increase in Critical Heat Flux (CHF) compared to water. The use of a nanofluid in the In-Vessel Retention (IVR) severe accident management strategy, ...

Hannink, Ryan Christopher

2007-01-01T23:59:59.000Z

459

Microanalysis Research Group Staff  

Science Conference Proceedings (OSTI)

*. Bookmark and Share. Microanalysis Research Group Staff. ... Joseph M. Conny, Research Chemist. Jeff M. Davis, Materials Research Engineer. ...

2013-05-15T23:59:59.000Z

460

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

Anthropogenic Aerosols: a Clearer Understanding Anthropogenic Aerosols: a Clearer Understanding Submitter: Daum, P., Brookhaven National Laboratory Area of Research: Aerosol Properties Working Group(s): Aerosol Journal Reference: Liu, Y., and P. H. Daum, 2002: "Indirect warming effect from dispersion forcing," Nature 419(6872):580-581. Figure 1. Key = Green symbols: triangle - FIRE, northeastern Pacific; Crossed circles - SOCEX, Southern Ocean; Filled circle - ACE1, Southern Ocean; Blue symbols: Filled circles - ASTEX 8, northeastern Atlantic; Diamonds - SCMS 8, Florida coast; Filled triangles - Sounding 9, ASTEX; Filled squares - horizontal 9, ASTEX; Open inverted triangles - level 1; Open upright triangles - level 2; Open circles - level 3, all from southwest of San Diego 10; open diamonds - SCMS 11; stars - vertical, ASTEX

Note: This page contains sample records for the topic "research vessel mirai" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


461

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

Biases in Column Absorption for Fractal Clouds Biases in Column Absorption for Fractal Clouds Submitter: Wiscombe, W. J., Brookhaven National Laboratory Area of Research: Radiation Processes Working Group(s): Radiative Processes Journal Reference: Marshak, Alexander; Davis, Anthony; Wiscombe, Warren; Ridgway, William; Cahalan, Robert; 1998: "Biases in Shortwave Column Absorption in the Presence of Fractal Clouds," J. Climate 11(3):431-446. Figure 1: Water vapor transmission spectra for solar zenith angle of 60 degree. From the top: from TOA to 5 km, from TOA to 1 km, from TOA to 0.5 km and, finally, from TOA to surface. Figure 2: Fractional cloudiness N = 0.777. (a) Horizontal distribution of optical depth, the same for both models. (b) Horizontal distribution of cloud height for optical model. Constant cloud top and cloud base; thus

462

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

More Like Shades of Gray: the Effects of Black Carbon in Aerosols More Like Shades of Gray: the Effects of Black Carbon in Aerosols Submitter: McComiskey, A. C., National Oceanic and Atmospheric Administration Area of Research: Aerosol Properties Working Group(s): Aerosol Life Cycle Journal Reference: Cappa CD, TB Onasch, P Massoli, DR Worsnop, TS Bates, ES Cross, P Davidovits, J Hakala, KL Hayden, BT Jobson, KR Kolesar, DA Lack, BM Lerner, SM Li, D Mellon, I Nuaaman, JS Olfert, T Petaja, PK Quinn, C Song, R Subramanian, EJ Williams, and RA Zaveri. 2012. "Radiative absorption enhancements due to the mixing state of atmospheric black carbon." Science, 337(6098), doi:10.1126/science.1223447. Black to the core: Scientists are combining field and laboratory measurements to understand more about the physical properties of aerosols

463

Research Highlight  

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Simulating Mixed-Phase Clouds: Sensitivity to Ice Initiation Simulating Mixed-Phase Clouds: Sensitivity to Ice Initiation Download a printable PDF Submitter: Sednev, I., Lawrence Berkeley National Laboratory Menon, S., Lawrence Berkeley National Laboratory McFarquhar, G., University of Illinois, Urbana Area of Research: General Circulation and Single Column Models/Parameterizations Working Group(s): Cloud Modeling Journal Reference: I Sednev, S Menon, and G McFarquhar. 2008. "Simulating mixed-phase Arctic stratus clouds: Sensitivity to ice initiation mechanisms." Atmospheric Chemistry and Physics Discussion 8: 11755-11819. The vertical structure and radiative properties of persistent low-level Arctic clouds depend on their microphysics, and thus, estimation of the relative significance of the microphysical processes that occur in these

464

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

A New Bulk Microphysical Scheme That Includes Riming Intensity and A New Bulk Microphysical Scheme That Includes Riming Intensity and Temperature Dependent Ice Ch Download a printable PDF Submitter: Lin, Y., Geophysical Fluid Dynamics Laboratory Area of Research: General Circulation and Single Column Models/Parameterizations Working Group(s): Cloud Life Cycle Journal Reference: Lin Y and BA Colle. 2011. "A new bulk microphysical scheme that includes riming intensity and temperature dependent ice characteristics." Monthly Weather Review, 139(3), 10.1175/2010MWR3293.1. (a) Coefficients of area-diameter (A-D) relationship in the new scheme. (b) Same as (a), except for the mass-diameter (M-D) relationship. (c) Same as (a), but for the velocity-diameter (V-D) relationship. (d) Same as (c), but each line shows the variation with Ri. More details of the figure are

465

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

New Method Simulates 3D Ice Crystal Growth Within Clouds New Method Simulates 3D Ice Crystal Growth Within Clouds Submitter: Bhattacharya, A., Pacific Northwest National Laboratory Area of Research: Radiation Processes Working Group(s): Cloud Life Cycle Journal Reference: Harrington JY, K Sulia, and H Morrison. 2013. "A method for adaptive habit prediction in bulk microphysical models. Part I: theoretical development." Journal of the Atmospheric Sciences, 70(2), doi:10.1175/JAS-D-12-040.1. Harrington JY, K Sulia, and H Morrison. 2013. "A method for adaptive habit prediction in bulk microphysical models. Part II: parcel model corroboration." Journal of the Atmospheric Sciences, 70(2), doi:10.1175/JAS-D-12-0152.1. A close-up of ice crystals. Ever noticed the different shapes of snowflakes sticking on the windowpane

466

Research Highlight  

NLE Websites -- All DOE Office Websites (Extended Search)

Dust in the Wind... and the Clouds... and the Atmosphere Dust in the Wind... and the Clouds... and the Atmosphere Submitter: Sassen, K., University of Alaska, Fairbanks Area of Research: Aerosol Properties Working Group(s): Aerosol Journal Reference: Sassen, K., P.J. DeMott, J.M. Propsero, and M.R. Poellot, Saharan Dust Storms and Indirect Aerosol Effects on Clouds: CRYSTAL-FACE Results, Geophys. Res. Ltt., 30(12), 1633, doi:10/1029/2003GL017371, 2003. PDL linear depolarization ratio (color scale on top) and relative returned power (in gray scale) of height versus time displays obtained on July 29, 2002, during the CRYSTAL-FACE experiment. Depicted are strong depolarizing upper tropospheric clouds (~10km), aerosols (δ ~.10 to .15) extending up to ~5.5km, and at lower right (scale adjusted to account for signal

467

Research Highlight  

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Heating Up the Arctic: Most Complete Data Set Ever Collected Helps Heating Up the Arctic: Most Complete Data Set Ever Collected Helps Scientists Understand Aerosol Download a printable PDF Submitter: Ghan, S. J., Pacific Northwest National Laboratory Area of Research: Radiation Processes Working Group(s): Aerosol Life Cycle Journal Reference: McFarquhar GM, S Ghan, J Verlinde, A Korolev, JW Strapp, B Schmid, JM Tomlinson, M Wolde, SD Brooks, D Cziczo, MK Dubey, JW Fan, C Flynn, I Gultepe, J Hubbe, MK Gilles, A Laskin, P Lawson, WR Leaitch, P Liu, XH Liu, D Lubin, C Mazzoleni, AM Macdonald, RC Moffet, H Morrison, M Ovchinnikov, MD Shupe, DD Turner, SC Xie, A Zelenyuk, K Bae, M Freer, and A Glen. 2011. "Indirect and Semi-Direct Aerosol Campaign: the impact of Arctic aerosols on clouds." Bulletin of the American Meteorological

468

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Ice Nuclei and Global Warming Ice Nuclei and Global Warming Download a printable PDF Submitter: Zeng, X., NASA - Goddard Space Flight Center Tao, W., NASA - Goddard Space Flight Center Zhang, M., Stony Brook University Hou, A., NASA - Goddard Space Flight Center Xie, S., Lawrence Livermore National Laboratory Lang, S. E., NASA - Goddard Space Flight Center Li, X., University of Maryland, Baltimore County Starr, D. O., NASA - Goddard Space Flight Center Area of Research: General Circulation and Single Column Models/Parameterizations Working Group(s): Cloud Modeling Journal Reference: Zeng X, WK Tao, M Zhang, AY Hou, S Xie, S Lang, X Li, DO Starr, and X Li. 2009. "A contribution by ice nuclei to global warming." Quarterly Journal Royal Meteorological Society, EARLY VIEW, doi:10.1002/qj.449.

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"Radiance Assimilation" Correction Method Improves Water Vapor Radiosonde "Radiance Assimilation" Correction Method Improves Water Vapor Radiosonde Observations in the Upper Troposphere Submitter: Soden, B. J., University of Miami Area of Research: General Circulation and Single Column Models/Parameterizations Working Group(s): Cloud Modeling Journal Reference: Soden, B.J., D.D. Turner, B.M. Lesht, and L.M. Miloshevich (2004), An analysis of satellite, radiosonde, and lidar observations of upper tropospheric water vapor from the Atmospheric Radiation Measurement Program, J. Geophys. Res., 109, D04105, doi:10/1029/2003JD003828. Time-average relative humidity profiles from both original (black) and radiance-adjusted (blue) radiosonde soundings compared to the lidar (red) retrievals from field campaigns in 1996, 1997, 1999, and 2000.

470

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Modeled Vs. Measured Direct-Normal Solar Irradiance Modeled Vs. Measured Direct-Normal Solar Irradiance Submitter: Schwartz, S. E., Brookhaven National Laboratory Area of Research: Radiation Processes Working Group(s): Radiative Processes Journal Reference: Halthore R. N., Schwartz, S. E., Michalsky, J. J., Anderson, G. P., Ferrare R. A., Holben B. N., and ten Brink H. M. 1997. "Comparison of Model Estimated and Measured Direct-Normal Solar Irradiance," J. Geophys. Res. 102(D25): 29991-30002 Figure 1 Figure 2 Figure 3 Figure 4 Direct-normal solar irradiance (DNSI), the total energy in the solar spectrum incident in unit time on a unit area at the earth's surface perpendicular to the direction to the Sun, Figure 1, depends only on atmospheric extinction of solar energy without regard to the details of the

471

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Continuous Dataset of Water Vapor Measurements Throws Water on Assumptions Continuous Dataset of Water Vapor Measurements Throws Water on Assumptions of Cirrus Cloud Formation Submitter: Comstock, J. M., Pacific Northwest National Laboratory Area of Research: Cloud Distributions/Characterizations Working Group(s): Cloud Properties Journal Reference: Comstock, J. M., T. P. Ackerman, and D. D. Turner, 2004: Evidence of high ice supersaturation in cirrus clouds using ARM Raman lidar measurements. Geophys. Res. Letters, doi:10.1029/2004GL019705. To illustrate their findings, a continuous nine-hour segment of Raman lidar measurements showed upper tropospheric RHI measurements ranging from 120% near cloud tops and decreasing to about 70% at cloud base. To study the link between water vapor, cirrus cloud formation (homogenous and heterogenous) mechanisms, and their potential climatic impacts,

472

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All Mixed Up-Probing Large and Small Scale Turbulence Structures in All Mixed Up-Probing Large and Small Scale Turbulence Structures in Continental Stratocumulus Clouds Download a printable PDF Submitter: Fang, M., University of Miami Albrecht, B. A., University of Miami Area of Research: Radiation Processes Working Group(s): Cloud Life Cycle Journal Reference: Fang M, BA Albrecht, VP Ghate, and P Kollias. 2013. "Turbulence in continental stratocumulus, Part I: External forcings and turbulence structures." Boundary-Layer Meteorology, 149(454), doi:10.1007/s10546-013-9873-3. Coherent structures of the vertical velocity (left panels) and the energy dissipation rate (right panels) in updraft region during the day (a, b), night (c, d), and for entire 16 hours (e, f) of continental stratocumulus. Continental stratocumulus clouds are frequently observed in the cold side

473

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Preferred States of the Winter Arctic Atmosphere, Surface, and Sub-Surface Preferred States of the Winter Arctic Atmosphere, Surface, and Sub-Surface Download a printable PDF Submitter: Del Genio, A. D., NASA Area of Research: Surface Properties Working Group(s): Cloud Life Cycle Journal Reference: Stramler K, AD Del Genio, and WB Rossow. 2011. "Synoptically driven Arctic winter states." Journal of Climate, 24(6), doi:10.1175/2010JCLI3817.1. SHEBA winter hourly surface net (down - up) longwave radiation flux versus surface temperature. Blue circles indicate times when a combined radar-lidar cloud detection indicated clear skies, and red plus signs indicate times when clouds were detected. Time series of SHEBA winter hourly temperatures at the atmospheric temperature inversion altitude (magenta), surface (black), snow-sea ice

474

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Seasonal Variation of the Physical Properties of Marine Boundary Clouds Seasonal Variation of the Physical Properties of Marine Boundary Clouds Download a printable PDF Submitter: Zhang, M., Stony Brook University Area of Research: Cloud Distributions/Characterizations Working Group(s): Cloud Modeling, Cloud Properties Journal Reference: Lin W, M Zhang, and NG Loeb. 2009. "Seasonal variation of the physical properties of marine boundary layer clouds off the California coast." Journal of Climate, 22(10), doi:10.1175/2008JCLI2478.1. Image (a). Seasonal contrast of marine boundary-layer clouds between (a) summer (above) and (b) winter (below) off the California coast. Shown are cloud amount in the shaded box, cloud top and base heights and lifting condensation level (LCL) to the left, and cloud thickness and adiabatic

475

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The Vertical Structure of Cloud Radiative Forcing at the ACRF SGP Revealed The Vertical Structure of Cloud Radiative Forcing at the ACRF SGP Revealed by 8 Years of Continuous Measurements Submitter: Mace, G., Utah State University Area of Research: Cloud Distributions/Characterizations Working Group(s): Cloud Modeling, Cloud Properties Journal Reference: Accepted to Journal of Climate, 2007. Figure 1. Cloud occurrence, coverage, radiative forcing, and radiation effects over a composite annual cycle that is derived by averaging all observations collected during a particular month for all years. a) cloud occurrence in 100 mb vertical bins, b) cloud coverage, c) infrared cloud radiative forcing in 100 mb vertical bins, d) solar cloud radiative forcing, e) net cloud radiative forcing, f,g,h) solar (dotted), IR (solid), and net (dashed) cloud radiative effect for TOA (f), atmosphere (g), and

476

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New Characterization of Organic Aerosol Evolution Will Help Improve Models New Characterization of Organic Aerosol Evolution Will Help Improve Models Download a printable PDF Submitter: Jimenez, J., University of Colorado Area of Research: Aerosol Properties Working Group(s): Aerosol Life Cycle Journal Reference: Jimenez JL and . et al. 2009. "Evolution of organic aerosols in the atmosphere." Science, 326, doi: 10.1126/science.1180353. Total mass concentration (in micrograms per cubic meter) and mass fractions of non-refractory inorganic species and organic components in submicrometer aerosols measured with the AMS at multiple surface locations in the Northern Hemisphere. Inset: Distributions of O:C for the OA components identified at the different sites. Relationship between O:C and hygroscopicity (k, or equivalently the

477

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Validation of CERES-MODIS Cloud Properties Using ARM Data Validation of CERES-MODIS Cloud Properties Using ARM Data Submitter: Dong, X., University of North Dakota Area of Research: Cloud Distributions/Characterizations Working Group(s): Cloud Properties Journal Reference: Dong, X., P. Minnis, B. Xi, S. Sun-Mack, and Y. Chen, 2007: Validation of CERES-MODIS stratus cloud properties using ground-based measurements at the DOE ARM SGP site. Accepted by J. Geophys. Res. Wielicki, B. A. and Co-authors (2000), CERES Validation Plan Overview, Release 4, 10/20/00, 58 pp. (Available at http://asd-www.larc.nasa.gov/ceres/validation/ ceresval_r4.0_over.pdf) Figure 1. Time series of surface-derived cloud-base and -top heights and temperatures (1-hour average) and matched MODIS-derived effective cloud heights and temperatures (30-km x 30-km box) for daytime single-layer and

478

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Single-Scattering Properties of Aggregates of Plates Single-Scattering Properties of Aggregates of Plates Download a printable PDF Submitter: Um, J., University of Illinois, Urbana McFarquhar, G., University of Illinois, Urbana Area of Research: Cloud Distributions/Characterizations Working Group(s): Radiative Processes Journal Reference: Um J and GM McFarquhar. 2009. "Single-scattering properties of aggregates of plates." Quarterly Journal Royal Meteorological Society, 135(639), 10.1002/qj.378. Aggregates of plates imaged by Cloud Particle Imager (left panel) and idealized geometry of aggregates of plates with AI=0.61 (right panel). Asymmetry parameter (g) at λ=0.55 μm of 80 different aggregates of seven 100 μm plates attached together, as functions of (a) AI, (b) 1-AR, and (c) An. The correlation coefficient and constants for a fitting equation,

479

Research Highlight  

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A Finer Mesh to Improve Cloud Representation in Climate Models? A Finer Mesh to Improve Cloud Representation in Climate Models? Submitter: Bhattacharya, A., Pacific Northwest National Laboratory Area of Research: Cloud Processes Working Group(s): Cloud Life Cycle Journal Reference: Boutle IA, SJ Abel, PG Hill, and CJ Morcrette. 2013. "Spatial variability of liquid cloud and