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1

UNIRIB Participant Experiences: Ron Goans  

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

Ron Goans Ron Goans Ron Goans Ron Goans Ron Goans is a graduate research assistant working on the thesis component of his master's degree in physics while performing experiments at the Holifield Radioactive Ion Beam Facility (HRIBF) at Oak Ridge National Laboratory (ORNL). His thesis research specifically relates to the field of radioactive ion beam development. The purpose of radioactive ion beam development is to study and produce high-intensity, high-purity beams of radioactive nuclides. These beams are used by nuclear physicists to study the structure of short-lived nuclei. Below is a question and answer dialog about Goans' experience in Oak Ridge. The video featured on the right side of this page also spotlights his experience with the University Radioactive Ion Beam (UNIRIB)

2

BWRVIP-271NP: BWR Vessel and Internals Project, Testing and Evaluation of the Browns Ferry Unit 2 120 Capsule  

Science Conference Proceedings (OSTI)

In the late 1990s, a Boiling Water Reactor 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 Browns Ferry Unit 2 120 capsule. These results will be used to monitor embrittlement as part of the BWRVIP ISP.BackgroundThe BWRVIP ISP represents a major enhancement to the process of monitoring embrittlement for the U.S. ...

2013-04-03T23:59:59.000Z

3

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

4

Nancy Brown  

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

Brown, Nancy J., Lucas A. J. Bastien, and Phillip N. Price. "Transport Properties for Combustion Modeling." Progress in Energy and Combustion Science 37 (2011): 565-582. 2010...

5

Faculty of Technology Heat Engineering Laboratory course 424508 E Ron Zevenhoven  

E-Print Network (OSTI)

Faculty of Technology Heat Engineering Laboratory course 424508 E Ron Zevenhoven TRP exam 9 jan;Faculty of Technology Heat Engineering Laboratory course 424508 E Ron Zevenhoven TRP exam 9 jan 2008 2/(m.K), determine numerically, using the grid shown in the Figure: a. the temperatures at the points 1, 2, 3, 4, 5

Zevenhoven, Ron

6

Thermal and Flow Engineering Laboratory course 424512 E Ron Zevenhoven c.s.  

E-Print Network (OSTI)

Thermal and Flow Engineering Laboratory course 424512 E Ron Zevenhoven c.s. April 2012 Exercises I of II ­ Numerical fluid dynamics 1. A tornado can be modelled as a steady, incompressible flow : rCv rCv v r x / / 2 1 0 where C1 and C2 are constants. a. Show that this model satisfies

Zevenhoven, Ron

7

Thermal and Flow Engineering Laboratory course 424512 E Ron Zevenhoven c.s.  

E-Print Network (OSTI)

Thermal and Flow Engineering Laboratory course 424512 E Ron Zevenhoven c.s. April 2013 Exercises I of II ­ Numerical fluid dynamics 1. A tornado can be modelled as a steady, incompressible flow : rCv rCv v r x / / 2 1 0 where C1 and C2 are constants. a. Show that this model satisfies

Zevenhoven, Ron

8

bo Akademi University 424101 Processteknikens Grunder Introduction to Process Engineering by / av: Ron Zevenhoven  

E-Print Network (OSTI)

volume. This is further illustrated in Fig. 2.2. 2.2 Balance equations 2.2.1 Mass balances Important: Ron Zevenhoven 2-1 2. Systemgränser, balansekvationer System boundaries, balance equations 2.1 System is referred to as the surroundings or the environment ­ see Fig. 2.1. Engineering systems can be divided

Zevenhoven, Ron

9

bo Akademi University 424101 Processteknikens Grunder Introduction to Process Engineering by / av: Ron Zevenhoven  

E-Print Network (OSTI)

to as control volume. This is further illustrated in Fig. 2.2. 2.2 Balance equations 2.2.1 Mass balances: Ron Zevenhoven 2-1 2. Systemgränser, balansekvationer System boundaries, balance equations 2.1 System is referred to as the surroundings or the environment ­ see Fig. 2.1. Engineering systems can be divided

Zevenhoven, Ron

10

bo Akademi University 424101 Processteknikens Grunder Introduction to Process Engineering by / av: Ron Zevenhoven  

E-Print Network (OSTI)

of internal energy U for open systems, especially if chemical conversions take place that give different, mixtures) composed of one or several chemical species during energy conversion processes depends strongly: Ron Zevenhoven 3-1 3. Energy conversion, balances, efficiency, equilibrium - An introduction

Zevenhoven, Ron

11

Switching algorithms for extending battery life in Electric Vehicles Ron Adany a,*, Doron Aurbach b  

E-Print Network (OSTI)

of automobiles. The propulsion solutions for EVs are based on hybrid or fully battery powered electric vehiclesSwitching algorithms for extending battery life in Electric Vehicles Ron Adany a,*, Doron Aurbach b 27 December 2012 Keywords: Electric Vehicles (EV) Switching algorithms Battery life Lithium ion

Kraus, Sarit

12

Ron Ross  

Science Conference Proceedings (OSTI)

... Dr. Ross also leads the Joint Task Force Transformation Initiative, a ... Dr. Ross has also received many private sector cyber security awards and ...

2013-03-16T23:59:59.000Z

13

NREL: Energy Analysis - Austin Brown  

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

Austin Brown Photo of Austin Brown Austin Brown is a member of the Washington D.C. Office in the Strategic Energy Analysis Center. Senior Analyst (Strategic Planning) On staff...

14

2012 SG Peer Review - GridWise Architecture Council - Ron Melton, PNNL  

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

Architecture and Standards and GridWise® Architecture and Standards and GridWise® Architecture Council (GWAC) Ron Melton, GWAC Administrator Pacific Northwest National Laboratory PNNL-SA-88349 June 7, 2012 December 2008 Architecture and Standards GridWise Architecture Council Objective Life-cycle Funding Summary ($K) Prior to FY 12 FY12, authorized FY13, requested Out-year(s) $5,400K $560K $200K $500K/yr Technical Scope 2 Advance interoperability to enable full-scale smart grid deployments by engaging stakeholders in defining interoperability principles, methods, and tools. Provide DOE related point of coordination for NIST in response to EISA 2007 legislation. Organizational (Pragmatics) 8: Economic/Regulatory Policy 7: Business Objectives 6: Business Procedures Informational (Semantics) 5: Business Context

15

Hmelo, Bin Hu, Alamgir Karim, Martyn McLachlan, and Ron Jones (by phone)  

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

Meeting of the CNMS User Executive Committee Meeting of the CNMS User Executive Committee September 13, 2010 - ORNL Bldg 8600, Room C-152 Members attending: Venkat Gopalan (Chair), Mark Dadmun (Vice Chair), David Bucknall (Secretary), Tony Hmelo, Bin Hu, Alamgir Karim, Martyn McLachlan, and Ron Jones (by phone) CNMS representatives: Peter Cummings, Laura Edwards, Tony Haynes, Mike Simonson Meeting convened 6:10pm. Discussion was guided by Chair's slides (attached). CNMS update provided by Mike Simonson (slides attached). Discussed several suggestions for CNMS user program and for future UEC activities. See slides 7 and 9 in Chair's presentation and the following. For UEC * Include an Industry liaison in UEC telecons/meetings- invited by UEC * Alternatively, designate an At-Large position on UEC for industrial member (requires change to by-laws)

16

ON THE KINETIC ENERGY AND RADIATIVE EFFICIENCY OF GAMMA-RAY BURSTS Nicole M. Lloyd-Ronning1  

E-Print Network (OSTI)

ON THE KINETIC ENERGY AND RADIATIVE EFFICIENCY OF GAMMA-RAY BURSTS Nicole M. Lloyd-Ronning1 of 17 gamma-ray bursts (GRBs) during the afterglow phase and ac- counting for radiative losses, we the implications of these results for the GRB radiation and jet models. Subject headinggs: gamma rays: bursts

Zhang, Bing

17

Degradation of monoethanolamine in soil Anne W. Ndegwa, Ron C.K. Wong, Angus Chu, Laurence R. Bentley, and  

E-Print Network (OSTI)

of Geology and Geophysics, The University of Calgary, Al- berta, AB T2N 1N4, Canada. S.R.D. Lunn. Imperial137 Degradation of monoethanolamine in soil Anne W. Ndegwa, Ron C.K. Wong, Angus Chu, Laurence R. Bentley, and Stuart R.D. Lunn Abstract: Monoethanolamines (MEA) are commonly used by the natural gas

18

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

19

brown-98.pdf  

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

High Resolution Validation in the Shortwave: High Resolution Validation in the Shortwave: ASTI/LBLRTM QME P. D. Brown, S. A. Clough, and E. J. Mlawer Atmospheric and Environmental Research, Inc. Cambridge, Massachusetts T. R. Shippert Pacific Northwest National Laboratory Richland, Washington F. J. Murcray Denver University Denver, Colorado Introduction To assess our modeling capability in the shortwave and to resolve issues including those described by Cess et al. (1995) and others (Li and Moreau 1996; Arking 1996), a Quality Measurement Experiment (QME) has been initiated that extends the approach of the longwave AERI/LBLRTM (atmospheric emitted radiance interferometer/line by line radiative transfer model) QME (Brown et al. 1998) to shorter wavelengths. This shortwave QME for the clear sky focuses upon three components: 1) the ability to accurately

20

Alabama Nuclear Profile - Browns Ferry  

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

Browns Ferry" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration date"...

Note: This page contains sample records for the topic "vessel ron brown" 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

Fermilab Today | Brown University Profile  

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

Cho and Gena Kukartsev. Front row from left: David Khatidze, Selda Esen Koylu, Duong Nguyen, Shabnam Jabeen, Saptaparna Bhattacharya and John Paul Chou. Brown group at CERN from...

22

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

23

brown-99.PDF  

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

NCAR/ARM Multiple Antenna Profiler NCAR/ARM Multiple Antenna Profiler W.O.J. Brown, S. A. Cohn, M. E. Susedik, C. L. Martin, G. Maclean, and D. B. Parsons National Center for Atmospheric Research Atmospheric Technology Division Boulder, Colorado Introduction National Center for Atmospheric Research/Atmospheric Technology Division (NCAR/ATD), with the support of the U.S. Department of Energy (DOE) Atmospheric Radiation Measurement (ARM) Program, is developing an advanced wind profiler radar known as Multiple Antenna Profiler Radar (MAPR) (Cohn et al. 1997, 1998). The radar is a highly modified 915-MHz profiler (Radian LAP-3000) and is designed to measure wind and turbulence at a rate considerably faster than traditional wind profilers. The radar has four vertically pointing closely spaced receiving antenna and uses spaced

24

2012 SG Peer Review - Recovery Act: Pacific Northwest Smart Grid Demonstration Project - Ron Melton, Battelle Memorial Institute  

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

Overview Overview Ron Melton, Ph.D., Project Director Don Hammerstrom, Ph.D., Principal Investigator Battelle, Pacific Northwest Division Presented at DOE-OE Smart Grid R&D Peer Review June 8, 2012 PNWD-SA-9876 Pacific Northwest Demonstration Project What: * $178M, ARRA-funded, 5-year demonstration * 60,000 metered customers in 5 states Why: * Quantify costs and benefits * Develop communications protocol * Develop standards * Facilitate integration of wind and other renewables Who: Led by Battelle and partners including BPA, 11 utilities, 2 universities, and 5 vendors 2 Project Basics 3 Transactive Control Operational objectives Manage peak demand Facilitate renewable resources Address constrained resources Improve system reliability and efficiency Select economical

25

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

26

17 Years of Lithium Brown Dwarfs 10/21/12Ringberg Brown Dwarfs 1  

E-Print Network (OSTI)

17 Years of Lithium Brown Dwarfs 10/21/12Ringberg Brown Dwarfs 1 #12;The Keck Search for Lithium 10/21/12Ringberg Brown Dwarfs 2 Lithium was not seen in objects which should have been comfortably into the brown "lithium dating". This adjustment in age meant that the inferred mass of PPl 15 rose to near the substellar

Joergens, Viki

27

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

28

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.

29

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

30

Ron Ross Bio  

Science Conference Proceedings (OSTI)

... Dr. Ross also leads the Joint Task Force Transformation Initiative, a ... Dr. Ross has also received several private sector cyber security awards and ...

2012-10-11T23:59:59.000Z

31

Infrared Debonding Ron Simandl  

Inventors Interests and Experience 2006 Government Use Award winner, SIMWyPES 2007 Government Use Award winner, IR Debonding 2008 R&D 100 Award ...

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

Women @ Energy: Nancy Brown | Department of Energy  

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

Women @ Energy: Nancy Brown Women @ Energy: Nancy Brown Women @ Energy: Nancy Brown March 15, 2013 - 11:00am Addthis Dr. Nancy Jeanne Brown is a Senior Scientist at the Lawrence Berkeley National Laboratory. Dr. Nancy Jeanne Brown is a Senior Scientist at the Lawrence Berkeley National Laboratory. Check out other profiles in the Women @ Energy series and share your favorites on Pinterest. Dr. Nancy Jeanne Brown is a Senior Scientist at the Lawrence Berkeley National Laboratory. Her research interests are atmospheric science, chemical kinetics, air quality and climate modeling, high performance computing, and combustion modeling. She received a B.S. in Chemistry at Virginia Polytechnic Institute, an M.S. in Molecular Physics and Ph.D. in Chemical Physics/Physical chemistry at the University of Maryland. Dr.

34

Fred L. Brown | Department of Energy  

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

Fred L. Brown Fred L. Brown About Us Fred L. Brown - Deputy Director of Office of Hearings & Appeals Fred L. Brown Fred Brown is the Deputy Director of the Office of Hearings and Appeals (OHA) of the U.S. Department of Energy (DOE). OHA is the quasi-judicial arm of DOE that conducts hearings and issues initial Departmental decisions with respect to any adjudicative proceedings which the Secretary may delegate. OHA's jurisdiction includes: deciding Freedom of Information and Privacy Act appeals; conducting administrative hearings and issuing Departmental decisions regarding personnel security clearance eligibility; conducting contractor employee "whistleblower" hearings and investigations; deciding applications for exception from DOE rules and regulations; and performing mediation services for the agency. Mr. Brown

35

PNNL Nanoscale Research Safety Program Brown Bag  

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

PNNL's Nanoscale Research Safety Program Brown Bag Carbon nanotube research is a critical research capability at Pacifi c North- west National Laboratory (Digisource) Do you work...

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

Study on Drying Characteristics of Australian Brown Coal Using ...  

Science Conference Proceedings (OSTI)

Victorian brown coal in Australia has over 60wt% moisture content and, when dried, it becomes highly reactive. Due to the difficulty in transporting it, brown coal

Note: This page contains sample records for the topic "vessel ron brown" 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

brown-pd99.PDF  

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

High-Resolution Model/Measurement Validations High-Resolution Model/Measurement Validations of Solar Direct-Beam Flux P. D. Brown, E. J. Mlawer, and S. A. Clough Atmospheric and Environmental Research, Inc. Cambridge, Massachusetts T. R. Shippert Pacific Northwest National Laboratory Richland, Washington F. J. Murcray and A. W. Dybdahl University of Denver Denver, Colorado L. C. Harrison, P. W. Kiedron, and J. J. Michalsky State University of New York at Albany Albany, New York Introduction A balance between thermal and solar radiation at the top of the atmosphere is necessary for the stability of the earth's climate. To evaluate the behavior of the climate system resulting from a radiative perturbation of this balance, as in a "global warming" scenario, accurate knowledge is needed of the radiative properties of the atmosphere both in the thermal- and solar-dominated spectral regions. A

42

The Structure of Brown Dwarf Circumstellar Disks  

E-Print Network (OSTI)

We present synthetic spectra for circumstellar disks that are heated by radiation from a central brown dwarf. Under the assumption of vertical hydrostatic equilibrium, our models yield scaleheights for brown dwarf disks in excess of three times those derived for classical T Tauri (CTTS) disks. If the near-IR excess emission observed from brown dwarfs is indeed due to circumstellar disks, then the large scaleheights we find could have a significant impact on the optical and near-IR detectability of such systems. Our radiation transfer calculations show that such highly flared disks around brown dwarfs will result in a large fraction of obscured sources due to extinction of direct starlight by the disk over a wide range of sightlines. The obscured fraction for a 'typical' CTTS is less than 20%. We show that the obscured fraction for brown dwarfs may be double that for CTTS, but this depends on stellar and disk mass. We also comment on possible confusion in identifying brown dwarfs via color-magnitude diagrams: edge-on CTTS display similar colors and magnitudes as a face-on brown dwarf plus disk systems.

Christina Walker; Kenneth Wood; C. J. Lada; Thomas Robitaille; J. E. Bjorkman; Barbara Whitney

2004-03-11T23:59:59.000Z

43

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

44

ESS 2012 Peer Review - Flow Battery Solution for Smart Grid Renewable Energy Applications - Sheri Nevins, Raytheon & Ron Moss, EnerVault  

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

2012, Raytheon Proprietary and EnerVault Corporation, All Rights Reserved. 2012, Raytheon Proprietary and EnerVault Corporation, All Rights Reserved. 1 Sheri Nevins Raytheon Ktech Ron Mosso EnerVault Corporation DEMONSTRATION OF ENERGY STORAGE USING A BREAKTHROUGH REDOX FLOW BATTERY TECHNOLOGY v. 1-0 Copyright ©2012, Raytheon Proprietary and EnerVault Corporation, All Rights Reserved. 2 Disclaimer This material is partially based upon work supported by NYSERDA under PON1200 Project 15880 NYSERDA has not reviewed the information contained herein, and the opinions expressed in this report do not necessarily reflect those of NYSERDA or the State of New York. This material is partially based upon work supported by the Department of Energy under Award Number DE-OE0000225. This report was prepared as an account of work sponsored by an agency of the United States

45

FIA-12-0044 - In the Matter of Cynthia Brown  

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

Cynthia Brown filed an Appeal regarding a request filed under the Freedom of Information Act. In March 2012, Ms. Brown filed a request for records regarding her late mother. In a July 2012 determination, the DOEs Office of Health, Safety and Security (HSS) issued a determination in response to Ms. Browns request.

46

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

47

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

48

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

49

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

50

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

51

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...

52

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

53

Brown County Wind | Open Energy Information  

Open Energy Info (EERE)

Brown County Wind Brown County Wind Facility Brown County Wind Sector Wind energy Facility Type Commercial Scale Wind Facility Status In Service Owner Adams Electric Cooperative Developer Adams Electric Cooperative Energy Purchaser Adams Electric Cooperative Location Mt. Sterling IL Coordinates 39.97340387°, -90.69939137° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":39.97340387,"lon":-90.69939137,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

54

Browns Ferry Corrosion Failure Data Assessment  

Science Conference Proceedings (OSTI)

This report provides a summary of the poolside inspection results from an inspection performed in 2011 of GE6 8x8 fuel that operated in Browns Ferry-3 and failed as a result of a corrosion-related mechanism in cycle 8 in 1998. It also provides an assessment of these results relative to prior crud-induced localized corrosion (CILC-) type failures in the early 1980s and subsequent corrosion-related failures from 2002 to 2004 in the same unit and its sister unit Browns Ferry-2. In particular, ...

2012-09-27T23:59:59.000Z

55

FIA-12-0044 - In the Matter of Cynthia Brown  

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

Cynthia Brown filed an Appeal regarding a request filed under the Freedom of Information Act. In March 2012, Ms. Brown filed a request for records regarding her late mother.

56

Mathematical modelling of brown seaweed drying curves  

Science Conference Proceedings (OSTI)

Simple solution on one-term exponential models is used in the analysis of raw data obtained from the drying experiment. The values of the parameters a, n and the constant k for the models are determined using a plot of curve drying models. Three different ... Keywords: brown seaweed, drying curves, mathematical models

Ahmad Fudholi; Mohd Hafidz Ruslan; Lim Chin Haw; Sohif Mat; Mohd Yusof Othman; Azami Zaharim; Kamaruzzaman Sopian

2012-01-01T23:59:59.000Z

57

Edmund G. Brown Jr. LIGHTING CALIFORNIA'S FUTURE  

E-Print Network (OSTI)

Edmund G. Brown Jr. Governor LIGHTING CALIFORNIA'S FUTURE: SMART LIGHT-EMITTING DIODE LIGHTING's Future: Smart LightEmitting Diode Lighting in Residential Fans. California Energy Commission, PIER. For the Smart Light emitting Diode Lighting in Residential Fans Project, the California Lighting Technology

58

David Brown Ethnicized Violence in Indonesia  

E-Print Network (OSTI)

David Brown and Ian Wilson Ethnicized Violence in Indonesia: The Betawi Brotherhood Forum which operates in Jakarta, Indonesia, indicates how both dimensions of violence coexist and interweave fighting which has intensified in Indonesia since the fall of Suharto in 1998. Such violence has become

59

Yang Keller and Brown MM 2012.pdf  

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

Genomics Genomics on Pretreatment Inhibitor Tolerance of Zymomonas mobilis Shihui Yang, Martin Keller, and Steven D. Brown Contents 1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 162 2 Genome Annotation of ZM4 Using Systems Biology Studies . . . . . . . . . . . . . . . . . . . . . . . . . . . . 163 3 Identification of Genes Tolerant to Acetate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 164 3.1 nhaA . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 164 3.2 hfq . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 169 3.3 nhaA and hfq . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 170 3.4 himA . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 170 4 Heterologous

60

The Grizzly and the Big Brown Bears  

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

Grizzly and the Big Brown Bears Grizzly and the Big Brown Bears Nature Bulletin No. 655-A November 12, 1977 Forest Preserve District of Cook County George W. Dunne, President Roland F. Eisenbeis, Supt. of Conservation THE GRIZZLY AND THE BIG BROWN BEARS In the early days, more tall tales were told about "Old Ephraim, " the grizzly bear, than any other animal. It had the reputation of being a bloodthirsty enemy of man and was given the scientific name Ursus horribilis by a taxonomist who had never seen a live one but had heard and read some of those yarns about its terrible ferocity and prodigious strength. The Grizzly is very intelligent and shrewd but, actually, has a rather phlegmatic disposition. It avoids people and will not attack unless provoked. Then, a female with cubs is unpredictable, and big game hunters say that a wounded grizzly is the most dangerous animal on earth. But ordinarily, as Earnest Thompson Seton observed, Ephraim is a peaceful giant who is perfectly satisfied to let you alone if you leave him alone.

Note: This page contains sample records for the topic "vessel ron brown" 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 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

62

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

63

Browning: Email in Response to Smart Grid Request for Information  

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

Email from Stephen Browning explaing the two attachments submitted in response to the Smart Grid Request for Information on Addressing Policy and Logistical Challenges.

64

A Brown Bag Lunch with EETD Communications Support Resource:...  

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

technical writing and editing, and support for large projects such as guidebooks, manuals, and multi-party proposal development. At this informal brown bag lunch,...

65

Light brown apple moths arrival in California worries commodity groups  

E-Print Network (OSTI)

DG. 1991. Integrated control of light brown apple moth, Epi-and Ag- riculture. 2007a. Light brown apple moth host list.6 p. CDFA. 2007b. Light brown apple moth project:

Varela, Lucia G.; Johnson, Marshall W; Strand, Larry; Wilen, Cheryl A; Pickel, Carolyn

2008-01-01T23:59:59.000Z

66

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

67

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

68

Boiler Gold Rush Prof. Johnny Brown (MATH 700)  

E-Print Network (OSTI)

Boiler Gold Rush Prof. Johnny Brown (MATH 700) jeb@math.purdue.edu #12;#12;#12;David McCullough, Jr help Always be prepared #12;Boiler Gold Rush Prof. Johnny Brown (MATH 700) jeb@math.purdue.edu #12;

Brown, Johnny E.

69

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

70

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

71

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

72

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

73

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.

74

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 ...

75

IEEE NANOSCIENCE and TECHNOLOGY BROWN BAG  

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

PLEASE PLEASE JOIN US! NANOSCIENCE and TECHNOLOGY BROWN BAG Friday, 7 November 2008 Noon - 1 pm Columbia River Room (public access available) PNNL, ETB Building (Q Avenue, Richland, WA) speaker Dr. Meyya Meyyappan Chief Scientist for Exploration Technology, NASA Ames Research Center & IEEE Electron Devices Society Distinguished Lecturer presenting Nanotechnology in Chemical and Bio Sensor Systems Abstract: There are strong research programs in nanotechnology related to chemical sensors, electromechanical devices, actuators, biosensors, and other nanodevices in leading laboratories across the world which use nanomaterials and other molecularly-engineered approaches. In many cases, practical systems demand seamless integration of the nanodevice with higher order structures, for example, MEMS. Examples of this using carbon nanotube based chemical and biosensors

76

Brown-J Bacteriol -12.pdf  

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

12):3290. DOI: 10.1128/JB.00473-12. 12):3290. DOI: 10.1128/JB.00473-12. J. Bacteriol. Keller and Edward A. Bayer Zamin Yang, Miriam L. Land, Sagar M. Utturkar, Martin Yuval Shoham, Dawn M. Klingeman, Courtney M. Johnson, Steven D. Brown, Raphael Lamed, Ely Morag, Ilya Borovok, Mutant Strain AD2 Derived Cellulose Adhesion-Defective thermocellum Wild-Type Strain YS and Draft Genome Sequences for Clostridium http://jb.asm.org/content/194/12/3290 Updated information and services can be found at: These include: REFERENCES http://jb.asm.org/content/194/12/3290#ref-list-1 at: This article cites 39 articles, 21 of which can be accessed free CONTENT ALERTS more» articles cite this article), Receive: RSS Feeds, eTOCs, free email alerts (when new http://journals.asm.org/site/misc/reprints.xhtml Information about commercial reprint orders:

77

L. A. Brown, M. C. Higuera  

Office of Scientific and Technical Information (OSTI)

L. L. A. Brown, M. C. Higuera Prepared by Sandia National Laboratories Albuquerque, New Mexico 87185 and L b SANDlA REPORT SAND974017 0 UC-700 Unlimited Release Printed February i 998 Weapon Container Catalog Volumes 1 & 2 -_ Issued by Sandia National Laboratories, operated for the United States Department of Energy by Sandia Corporation. NOTICE: This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Govern- ment nor any agency thereof, nor any of their employees, nor any of their contractors, subcontractors, or their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, prod-

78

Brown Grease to Biodiesel Demonstration Project Report  

Science Conference Proceedings (OSTI)

Municipal wastewater treatment facilities have typically been limited to the role of accepting wastewater, treating it to required levels, and disposing of its treatment residuals. However, a new view is emerging which includes wastewater treatment facilities as regional resource recovery centers. This view is a direct result of increasingly stringent regulations, concerns over energy use, carbon footprint, and worldwide depletion of fossil fuel resources. Resources in wastewater include chemical and thermal energy, as well as nutrients, and water. A waste stream such as residual grease, which concentrates in the drainage from restaurants (referred to as Trap Waste), is a good example of a resource with an energy content that can be recovered for beneficial reuse. If left in wastewater, grease accumulates inside of the wastewater collection system and can lead to increased corrosion and pipe blockages that can cause wastewater overflows. Also, grease in wastewater that arrives at the treatment facility can impair the operation of preliminary treatment equipment and is only partly removed in the primary treatment process. In addition, residual grease increases the demand in treatment materials such as oxygen in the secondary treatment process. When disposed of in landfills, grease is likely to undergo anaerobic decay prior to landfill capping, resulting in the atmospheric release of methane, a greenhouse gas (GHG). This research project was therefore conceptualized and implemented by the San Francisco Public Utilities Commission (SFPUC) to test the feasibility of energy recovery from Trap Waste in the form of Biodiesel or Methane gas. The research goals are given below: ?¢???¢ To validate technology performance; ?¢???¢ To determine the costs and benefits [including economic, socioeconomic, and GHG emissions reduction] associated with co-locating this type of operation at a municipal wastewater treatment plant (WWTP); ?¢???¢ To develop a business case or model for replication of the program by other municipal agencies (as applicable). In order to accomplish the goals of the project, the following steps were performed: 1. Operation of a demonstration facility designed to receive 10,000 to 12,000 gallons of raw Trap Waste each day from private Trap Waste hauling companies. The demonstration facility was designed and built by Pacific Biodiesel Technologies (PBTech). The demonstration facility would also recover 300 gallons of Brown Grease per day from the raw Trap Waste. The recovered Brown Grease was expected to contain no more than 2% Moisture, Insolubles, and Unsaponifiables (MIU) combined. 2. Co-digestion of the side streams (generated during the recovery of 300 gallons of Brown Grease from the raw Trap Waste) with wastewater sludge in the WWTP?¢????s anaerobic digesters. The effects of the side streams on anaerobic digestion were quantified by comparison with baseline data. 3. Production of 240 gallons per day of ASTM D6751-S15 grade Biodiesel fuel via a Biodiesel conversion demonstration facility, with the use of recovered Brown Grease as a feedstock. The demonstration facility was designed and built by Blackgold Biofuels (BGB). Side streams from this process were also co-digested with wastewater sludge. Bench-scale anaerobic digestion testing was conducted on side streams from both demonstration facilities to determine potential toxicity and/or changes in biogas production in the WWTP anaerobic digester. While there is a lot of theoretical data available on the lab-scale production of Biodiesel from grease Trap Waste, this full-scale demonstration project was one of the first of its kind in the United States. The project?¢????s environmental impacts were expected to include: ?¢???¢ Reduction of greenhouse gas emissions by prevention of the release of methane at landfills. Although the combustion product of Biod

San Francisco Public Utilities Commission; URS Corporation; Biofuels, Blackgold; Carollo Engineers

2013-01-30T23:59:59.000Z

79

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

80

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

Note: This page contains sample records for the topic "vessel ron brown" 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

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

82

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

83

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

84

Molecular insights into the niche of harmful brown tides  

E-Print Network (OSTI)

Recurrent brown tide blooms caused by the harmful alga Alureococcus anophagefferens have decimated coastal ecosystems and shellfisheries along the Eastern U.S and South Africa. The exact mechanisms controlling bloom ...

Wurch, Louie L. (Louie Lorne)

2011-01-01T23:59:59.000Z

85

Study shows that 'brown carbon' contributes more to climate change...  

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

Study shows that 'brown carbon' contributes more to climate change than previously believed By Jared Sagoff * February 18, 2013 Tweet EmailPrint Much of the current effort toward...

86

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

87

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

88

Assessment of Browns Ferry 2 Cycle 12 Fuel Corrosion Failures  

Science Conference Proceedings (OSTI)

Boiling water reactor (BWR) fuel rods from 63 bundles of the Reload 10 GE13 (9x9) design developed leaks during Cycle 12 at Browns Ferry 2 (BF-2). Corrosion failures also occurred in Browns Ferry 3 (BF-3) and Vermont Yankee (VY) in a similar time frame. These fuel failures were investigated in the spent fuel pool and in two separate hot cell examination campaigns. This report compiles and assesses the significant findings of the root cause investigation.

2011-11-30T23:59:59.000Z

89

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

90

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...

91

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...

92

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,...

93

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

94

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

95

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

96

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

97

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...

98

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

99

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

100

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

Note: This page contains sample records for the topic "vessel ron brown" 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

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

102

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

103

Brown-Atchison E C A Inc | Open Energy Information  

Open Energy Info (EERE)

Brown-Atchison E C A Inc Brown-Atchison E C A Inc Jump to: navigation, search Name Brown-Atchison E C A Inc Place Kansas Utility Id 2354 Utility Location Yes Ownership C NERC Location SPP NERC SPP Yes Activity Distribution Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png Area Lighting Metered (AL-M) Lighting Area Lighting Unmetered (AL-U) Lighting General Service Large (GSL) Commercial General Service Small (Single Phase GSS-10) Commercial General Service Small (Three Phase GSS-30) Commercial Public Building Service- Single Phase (PB-10) Commercial Public Building Service- Three Phase (PB-30) Commercial

104

DOE - Office of Legacy Management -- Brown University - Metcalf Research  

Office of Legacy Management (LM)

Brown University - Metcalf Research Brown University - Metcalf Research Lab - RI 01 FUSRAP Considered Sites Site: Brown University (Metcalf Research Lab.) (RI.01 ) Eliminated from further consideration under FUSRAP Designated Name: Not Designated Alternate Name: None Location: Providence , Rhode Island RI.01-1 Evaluation Year: 1987 RI.01-1 Site Operations: Research/Development on the preparation of pure halides of heavy metals, Bench Scale Process, and Sample & Analysis. RI.01-1 Site Disposition: Eliminated - Potential for residual radioactive contamination from small quantities of radioactive material is considered remote RI.01-1 Radioactive Materials Handled: Yes Primary Radioactive Materials Handled: Uranium, Thorium RI.01-1 Radiological Survey(s): None Indicated

105

The Harold Brown view: LLNL then and now  

Science Conference Proceedings (OSTI)

Harold Brown was the Laboratory's third Director, serving from 1960 to 1961. He joined the Livermore laboratory in 1952. At Livermore, Brown worked on the Polaris warhead and on Project Plowshare, program designed to apply nuclear explosives to peaceful uses (such as excavating harbors). Brown succeeded Edward Teller as Director of the Livermore Laboratory in July 1960. His tenure as Director was particularly challenging as these were the years of the moratorium on nuclear testing. He was the driving force in expanding the Laboratory's capabilities for simulating nuclear explosions with computers. As part of LLNL's 40th anniversary observances, Brown was invited to lecture on his views of the changing world and the role of the Laboratory. He reminisced about events that occurred in the Laboratory's early years, with an eye to finding lessons for the future. In particular, he cited Project Plowshare and the MX ICBM as examples of projects that were technologically and economically feasible but unacceptable in terms of public perception. Brown also discussed the international security environment and the Laboratory's role in support of the national security goals of the United States. He defined U.S. security as protecting America against external threats to its physical survival, to its democratic form of government, or to the well-being of the people of the United States. By this definition, issues of international trade and market access have a strong bearing on national security. Thus the Laboratory can find much important and interesting work to do under the heading of national security and economic competitiveness. Brown also pointed out, however, that working effectively with the private sector will take a change in culture since the private-sector market is very different from and more competitive than the nuclear weapons world or the government's nondefense market.

Brown, H. (Center for Strategic and International Studies, Washington, DC (United States))

1993-08-01T23:59:59.000Z

106

Intern experience at Brown & Root, Inc.: an internship report  

E-Print Network (OSTI)

To document that the objectives of the internship were met, the report examines the organizational approach at Brown & Root and then describes seven major job assignments that were completed by the author during the internship. The internship report outlines the process by which Brown & Root carries out the design and construction of offshore oil and gas production facilities ... A supplementary presentation of the author's previous experience at an oil company permits a comparison of the viewpoints of engineering and construction contractors and oil companies.

Kibbee, Stephen Edward, 1951-

1979-05-01T23:59:59.000Z

107

Flowing with the Tide:Epiphytic Host-Specificity and Phenotypic Plasticity of the Brown Alga Padina boryana  

E-Print Network (OSTI)

PLASTICITY OF THE BROWN ALGA PADINA BORYANA SIERRA M. FLYNN94720 USA Abstract. Epiphytic algae form complex communitiesmacroalgae hosts. The brown alga Padina boryana acts as a

Flynn, Sierra Michelle

2011-01-01T23:59:59.000Z

108

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

109

Edmund G. Brown, Jr. TEST METHOD FOR CALCULATING  

E-Print Network (OSTI)

-VOLTAGE EXTERNAL AC-DC POWER SUPPLIES PIERFINALREPORT Prepared For: California Energy Commission Public InterestEdmund G. Brown, Jr. Governor TEST METHOD FOR CALCULATING THE ENERGY EFFICIENCY OF SINGLE Energy Research Program Prepared By: Ecos Power Electronics Application Center July 2011 CEC-500

110

Software Reuse in High Performance Computing Shirley Browne  

E-Print Network (OSTI)

Software Reuse in High Performance Computing Shirley Browne University of Tennessee 107 Ayres Hall high performance computing architectures in the form of distributed memorymul- tiprocessors have become of programming applications to run on these machines. Economical use of high performance computing and subsequent

Dongarra, Jack

111

Software Reuse in High Performance Computing Shirley Browne  

E-Print Network (OSTI)

Software Reuse in High Performance Computing Shirley Browne University of Tennessee 107 Ayres Hall high performance computing architectures in the form of distributed memory mul­ tiprocessors have and cost of programming applications to run on these machines. Economical use of high performance computing

Dongarra, Jack

112

Chemical Engineering The George R. Brown School of Engineering  

E-Print Network (OSTI)

110 Chemical Engineering The George R. Brown School of Engineering Chair Kyriacos Zygourakis of study leading to the nonthesis Master of Chemical Engineering (M.Ch.E.) degree. A joint M, and biomedical engineering. #12;Chemical Engineering 111 Degree Requirements for B.S. in Chemical Engineering

Richards-Kortum, Rebecca

113

Chemical Engineering The George R. Brown School of Engineering  

E-Print Network (OSTI)

117 Chemical Engineering The George R. Brown School of Engineering Chair Kyriacos Zygourakis,studentsmayapplyforafifthyearofstudyleadingtothenonthesis Master of Chemical Engineering (M.Ch.E.) degree. A joint M.B.A./M.Ch.E. degree is also available, and biomedical engineering. #12;Chemical Engineering 119118 DEPARTMENTS / Chemical Engineering For CENG 301 Math

Richards-Kortum, Rebecca

114

Chemical Engineering The George R. Brown School of Engineering  

E-Print Network (OSTI)

120 Chemical Engineering The George R. Brown School of Engineering Chair Kyriacos Zygourakis,studentsmayapplyforafifthyearofstudyleadingtothenonthesis Master of Chemical Engineering (M.Ch.E.) degree. A joint M.B.A./M.Ch.E. degree is also available, and biomedical engineering. #12;Chemical Engineering 121 Degree Requirements for B.S. in Chemical Engineering

Richards-Kortum, Rebecca

115

Habitable Planets Eclipsing Brown Dwarfs: Strategies for Detection and Characterization  

E-Print Network (OSTI)

Given the very close proximity of their habitable zones, brown dwarfs represent high-value targets in the search for nearby transiting habitable planets that may be suitable for follow-up occultation spectroscopy. In this paper we develop search strategies to find habitable planets transiting brown dwarfs depending on their maximum habitable orbital period (PHZ out). Habitable planets with PHZ out shorter than the useful duration of a night (e.g. 8-10 hrs) can be screened with 100 percent completeness from a single location and in a single night (near-IR). More luminous brown dwarfs require continuous monitoring for longer duration, e.g. from space or from a longitude-distributed network (one test scheduling achieved - 3 telescopes, 13.5 contiguous hours). Using a simulated survey of the 21 closest known brown dwarfs (within 7 pc) we find that the probability of detecting at least one transiting habitable planet is between 4.5 +5.6-1.4 and 56 +31-13 percent, depending on our assumptions. We calculate that bro...

Belu, Adrian R; Raymond, Sean N; Pall, Enric; Street, Rachel; Sahu, D K; Von Braun, Kaspar; Bolmont, Emeline; Figueira, Pedro; Anupama, G C; Ribas, Ignasi

2013-01-01T23:59:59.000Z

116

BrownMap: enforcing power budget in shared data centers  

Science Conference Proceedings (OSTI)

In this work, we investigate mechanisms to ensure that a shared data center can operate within a power budget, while optimizing a global objective function(e.g., maximize the overall revenue earned by the provider). We present the BrownMap methodology ...

Akshat Verma; Pradipta De; Vijay Mann; Tapan Nayak; Amit Purohit; Gargi Dasgupta; Ravi Kothari

2010-11-01T23:59:59.000Z

117

Edmund G. Brown, Jr. PLUG-IN HYBRID ELECTRIC VEHICLE  

E-Print Network (OSTI)

Edmund G. Brown, Jr. Governor PLUG-IN HYBRID ELECTRIC VEHICLE RESEARCH ROADMAP Davis Plug-In Hybrid Electric Vehicle Research Center June 2011 CEC-500-2010-039 #12; #12; Prepared By: UC Davis Plug-In Hybrid Electric Vehicle Research Center Dr. Thomas Turrentine, University

118

Dynamic Response Calibration of the Nell Brown Conductivity Cell  

Science Conference Proceedings (OSTI)

Dynamic response calibrations and flow visualization studies have been made for the standard, 3 cm long conductivity cell produced by Neil Brown Instrument Systems. This probe is used on wire-lowered CTD's as well as on vehicles that move freely ...

Michael C. Gregg; John C. Schedvin; William C. Hess; Thomas B. Meagher

1982-07-01T23:59:59.000Z

119

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

120

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

Note: This page contains sample records for the topic "vessel ron brown" 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

Infrared Searches for Dark Matter in the Form of Brown Dwarfs  

E-Print Network (OSTI)

Brown dwarfs, stars with insufficient mass to burn hydrogen, could contribute to the dark matter in the Galactic disk, galactic halos or even a background critical density. We consider the detectability of such brown dwarfs in various scenarios, extending previous work by allowing for the possibility that they may have an extended mass spectrum or be clumped into dark clusters. We investigate the constraints placed on such scenarios by the \\iras survey. Whilst an extrapolation of the mass function of visible disk stars makes it unlikely that brown dwarfs comprise all of the proposed disk dark matter, \\iras does not exclude brown dwarfs providing the dark matter in our own halo or a cosmological background. Neither does it improve on existing dynamical constraints on the mass and radius of brown dwarf clusters in our halo. Future satellites such as \\iso and \\sirtf will either detect brown dwarfs or brown dwarf clusters or else severely constrain their contribution to the dark matter.

E. J. Kerins; B. J. Carr

1993-09-02T23:59:59.000Z

122

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

123

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

124

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

125

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

126

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

127

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

128

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

129

Understanding Brown Carbon Aerosols and Their Role in Climate Change  

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

Brown Carbon Aerosols Brown Carbon Aerosols Tiny aerosol particles in the atmosphere are a possible cause of climate change. Among the many contributors to climate change are aerosols in the atmosphere. These tiny particles suspended in the air come from many sources, some natural and some man-made. Some aerosols are organic (containing carbon), while others are inorganic (such as sea salt and sulfates). Most aerosols reflect sunlight, and some also absorb it. Many of these nanoparticles have severe health effects in addition to climate effects. Human activities that produce aerosols include transportation, industry, and agriculture. Black carbon particles (a component of soot) originating from combustion processes have been known for some time to absorb sunlight and warm the

130

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

131

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

132

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

133

Agreement between the California Union of Safety Employees (CAUSE), Bargaining Unit 7 and the State of California, 1999-2001  

E-Print Network (OSTI)

JOSIE HODSON RON BROWN DEE UHLIK California Highway PatrolDIANE NAVARRO California Conservation Corp MARGIE POPOFFI. SAFETY EQUIPMENT - CALIFORNIA SCIENCE CENTER 1. The State

California Union of Safety Employees (CAUSE), Bargaining Unit 7

1999-01-01T23:59:59.000Z

134

On Heat and Quality Ron Zevenhoven  

E-Print Network (OSTI)

and Finland-swedes, about languages, about being a foreigner, about driving a car during winter, about being our skin. Energy is nowadays an important political factor with a price for crude oil that steadily and peat started, followed by oil and natural gas during the last 150 years. For mechanical energy

Zevenhoven, Ron

135

Biosorption of heavy metal ions to brown algae, Macrocystis pyrifera, Kjellmaniella crassiforia, and Undaria pinnatifida  

SciTech Connect

A fundamental study of the application of brown algae to the aqueous-phase separation of toxic heavy metals was carried out. The biosorption characteristics of cadmium and lead ions were determined with brown algae, Macrocystis pyrifera, Kjellmaniella crassiforia, and Undaria pinnatifida. A metal binding model proposed by the authors was used for the description of metal binding data. The results showed that the biosorption of bivalent metal ions to brown algae was due to bivalent binding to carboxylic groups on alginic acid in brown algae.

Seki, Hideshi; Suzuki, Akira [Hokkaido Univ., Hakodate (Japan)

1998-10-01T23:59:59.000Z

136

Front Row (left to right): Bryan Reed, Wayne King, Nigel Browning ...  

DTEM Team Members: Front Row (left to right): Bryan Reed, Wayne King, Nigel Browning, Judy Kim, Michael Armstrong Back Row (left to right): Thomas LaGrange ...

137

Analysis of the Browns Ferry Unit 3 Irradiation Experiments  

Science Conference Proceedings (OSTI)

A technique for calculating neutron radiation in and around LWR pressure vessels proved accurate enough to replace actual measurement in most applications. In the course of validating this technique, researchers developed the SAILOR cross-section library of data on power reactor shielding.

1984-11-01T23:59:59.000Z

138

Hydroliquefaction of Big Brown lignite in supercritical fluids  

E-Print Network (OSTI)

Big Brown lignite was liquefied in a fixed bed tube reactor. Three solvents were used in the liquefaction studies, toluene, cyclohexane and methanol. Two co-solvents, tetralin and water were used with toluene. The effects of the solvents and co-solvents were investigated. Supercritical fluid is the fluid at the temperature and pressure above its critical values. Toluene was the main supercritical fluid used in this study. Tetralin and water as co-solvents can contribute hydrogen to stabilize the free radicals produced during liquefaction reaction. The total conversion of Big Brown lignite and yield of liquid were increased. Water is not as good as tetralin in producing hydrogen, but it can increase the polarity of the solvent, which increases the solvency of supercritical fluids. The liquid product was found to consist primarily of saturated hydrocarbons. It illustrated that the free radicals were saturated by hydrogen during liquefaction. Alkylated aromatics and furans are also common chemical species present in the liquid products. The aromatic species were predominantly alkylated phenols, benzenes, indenes, pyridines and naphthalenes. At the supercritical conditions of this study, temperature and flowrate of the solvent were not important to the conversion of Big Brown lignite and yield of liquid, since supercritical fluids have gas-like viscosities with very high solubilities. To get more liquid products, the main point is to produce more free radicals from coal, inhibit the recombination of these radicals, and prevent the decomposition of these radicals to gas. Tetralin and water are good co-solvents for coal hydroliquefaction. Further research on the mechanism of water as a co-solvent in coal hydroliquefaction was recommended.

Chen, Hui

1996-01-01T23:59:59.000Z

139

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

140

Intern experience at Brown & Root, Incorporated: an internship report  

E-Print Network (OSTI)

This internship report describes the major activities and accomplishments during the author's one-year intership at Brown & Root in Houston, Texas. The report discusses his engineering assignments, and the necessary functions of a project engineer. The author's assignments covered essentially the technical nature and procedures of his work in several areas of fixed offshore platform design. The author presents and discusses the managerial functions of a project engineer whom he observed working in an offshore engineering company. At the end of this report, the author's accomplishments are summarized, and recommendations concerning the internship are presented.

Roengnarong Ratanaprichavej, 1949-

1979-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "vessel ron brown" 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

Engineering internship at Brown & Root, Incorporated: a report  

E-Print Network (OSTI)

An engineering intership at Brown & Root, Incorporated was completed over a period slightly in excess of one year. During his internship, the industrial engineer was assigned tasks related to the organization of a manufacturing department and the pursuit and completion of its projects. Many of his contributions were system-related and involved sales, engineering proposals, engineering economy, contract negotiations, employee merit evaluation, design, and general groundwork. He was also assigned to two engineering projects concerning the design and construction of manufacturing facilities. One of the project assignments required international travel to England and Nigeria, and almost all of the assignments involved some aspect of engineering management.

Gannaway, Randall Joe, 1952-

1977-12-01T23:59:59.000Z

142

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

143

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

144

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...

145

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

146

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

147

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

148

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...

149

Anaerobic Co-digestion of Brown Water and Food Waste for Energy Recovery  

E-Print Network (OSTI)

LIM J.W. Anaerobic Co-digestion of Brown Water and Food Waste for Energy Recovery Jun Wei LIM, Singapore 639798 (E-mail: jwlim3@e.ntu.edu.sg) Abstract The anaerobic digestion of brown water (BW), food in a decentralized reactor via anaerobic digestion. The bio-methane potential of these substrates at different feed

Paris-Sud XI, Université de

150

Preparation of oxygen-containing organic products from bed-oxidized brown coal by ozonation  

Science Conference Proceedings (OSTI)

The possibility of modifying the functional composition of humic acids by gas-phase ozonation of bed-oxidized brown coal was examined. About 90% of the organic matter of brown coal was converted to low-molecular weight soluble oxygen-containing products by stepwise liquid-phase ozonation (in chloroform and acetic acid).

Semenova, S.A.; Patrakov, Y.F.; Batina, M.V. [National Academy of Science Belarus, Minsk (Byelarus)

2009-01-15T23:59:59.000Z

151

Dr. Benjamin L. Brown | U.S. DOE Office of Science (SC)  

Office of Science (SC) Website

Benjamin L. Brown Benjamin L. Brown Deputy Director for Science Programs Deputy Director Home Mission & Functions Deputy Director Biography Organization Staff Presentations & Testimony Federal Advisory Committees Committees of Visitors Contact Information Deputy Director for Science Programs U.S. Department of Energy SC-2/Forrestal Building 1000 Independence Ave., SW Washington, DC 20585 P: (202) 586-5430 F: (202) 586-4120 E: sc.science@science.doe.gov U.S. Department of Energy SC-2/Germantown Building 1000 Independence Ave., SW Washington, DC 20585 P: (301) 903-5316 F: (301) 903-7780 E: sc.science@science.doe.gov Staff Dr. Benjamin L. Brown Print Text Size: A A A RSS Feeds FeedbackShare Page Dr. Benjamin L. Brown Dr. Benjamin L. Brown Senior Science and Technology Advisor Office of the Deputy Director for Science Programs

152

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

153

Rheological properties of water-coal slurries based on brown coal in the presence of sodium lignosulfonates and alkali  

Science Conference Proceedings (OSTI)

The effect of the oxidized surface of brown coal on the structural and rheological properties of water-coal slurries was found. The kinetics of structure formation processes in water-coal slurries based on as-received and oxidized brown coal was studied. The effect of lignosulfonate and alkali additives on the samples of brown coal was considered.

D.P. Savitskii; A.S. Makarov; V.A. Zavgorodnii [National Academy of Sciences of Ukraine, Kiev (Ukraine). Dumanskii Institute of Colloid and Water Chemistry

2009-07-01T23:59:59.000Z

154

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

155

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

156

MEMORANDUM FROM: THOMAS E. BROWN, DIRECTOR OFFICE OF CONTRACT MANAGEMENT  

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

,2008 ,2008 MEMORANDUM FROM: THOMAS E. BROWN, DIRECTOR OFFICE OF CONTRACT MANAGEMENT OFFICE OF PROCUREMENT AND ASSISTANCE MANAGEMENT SUBJECT: Contract Change Order Administration of Department of Energy Prime Contracts The purpose of this memorandum is to highlight the need for good contract administration of Department of Energy (DOE) contracts (non management and operating contracts) including those covered by DOE Order 413.3A, Program and Project Management for the Acquisition of Capital Assets. One of the focus areas of the DOE's efforts to improve contract and project management is the recopition that effectrve contract change order administration is critical to ensuring that contract and project requirements are met. Fundamentally, the award of an appropriate contract type that best

157

Pascal Baron, CEA - France Christine Brown, BNFL - U.K.  

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

- November 2004 - November 2004 Final Report - November 2004 An Evaluation of the Proliferation Resistant Characteristics of Light Water Reactor Fuel with the Potential for Recycle in the United States Pascal Baron, CEA - France Christine Brown, BNFL - U.K. Bruce Kaiser, WGI - U.S.A. Bruce Matthews, LANL - U.S.A. Takehiko Mukaiyama, JAIF- Japan Ronald Omberg, PNNL, U.S.A. Lee Peddicord, Texas A&M - U.S.A., Massimo Salvatores, CEA - France, Alan Waltar, PNNL - U.S.A., Chair Compiled by Alan E. Waltar and Ronald P. Omberg Pacific Northwest National Laboratory Final Report - November 2004 Final Report - November 2004 1 Table of Contents Executive Summary 2 I. Introduction 5 II. Background 5 III. Historical Perspective 7

158

Project title: EMF Remodel Requested By: Scotty Brown  

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

EMF Remodel EMF Remodel Requested By: Scotty Brown Date Submitted: 811112011 Dcscl"iption of the Pl'Ojcct: Purpose and Need Mail Code: N5540 Phone: 916-353-4539 Date Required: 8116/2011 The Elverta Maintenance Facility (EMF), as currently designed and built, has run out of adequate space to accommodate Western's parking needs for maintenance vehicles and overall workshop space for materials and required equipment. An expanded, renovated and remodeled facility, with a larger parking garage and workshop area(s), will enable Western to maintain its vehicle fleet to the required standards and provide additional workshop space to accommodate the equipment, tools, and materials necessary to construct and maintain Western's electrical transmission system and related facilities.

159

Brown County Rural Elec Assn | Open Energy Information  

Open Energy Info (EERE)

Rural Elec Assn Rural Elec Assn Jump to: navigation, search Name Brown County Rural Elec Assn Place Minnesota Utility Id 2316 Utility Location Yes Ownership C NERC Location MRO NERC MRO Yes Activity Distribution Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png General Single Phase Service-Controlled electric Heat Commercial General Single Phase Service Commercial General Single Phase Service(Load Management) Commercial General Three Phase Service Commercial General Three Phase Service(Load Management) Commercial General Three Phase Service- Controlled Electric Heat Commercial

160

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

Note: This page contains sample records for the topic "vessel ron brown" 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

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

162

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

163

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

164

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

165

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

166

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

167

Integrated model shows that atmospheric brown clouds and greenhouse gases have reduced rice harvests in India  

SciTech Connect

Previous studies have found that atmospheric brown clouds partially offset the warming effects of greenhouse gases. This finding suggests a tradeoff between the impacts of reducing emissions of aerosols and greenhouse gases. Results from a statistical model of historical rice harvests in India, coupled with regional climate scenarios from a parallel climate model, indicate that joint reductions in brown clouds and greenhouse gases would in fact have complementary, positive impacts on harvests. The results also imply that adverse climate change due to brown clouds and greenhouse gases contributed to the slowdown in harvest growth that occurred during the past two decades.

Auffhammer, M. [Univ. of California, Berkeley, CA (United States). Dept. of Agricultural and Resource Economics; Ramanathan, V. [Scripps Institution of Oceanography, San Diego, CA (United States); Vincent, J.R. [Univ. of California, San Diego, CA (United States). Graduate School of International Relations and Pacific Studies

2007-12-26T23:59:59.000Z

168

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

169

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

170

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

171

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

172

PAUL SHORT --MENS BROWN file:///Users/bkatten/Desktop/R092812AF.html[9/28/12 4:04:11 PM  

E-Print Network (OSTI)

Sarah J. Girotti '93 ++ Bernard Gitlin '62 '89P '92P ++ John H. Glanville '77 ++ William A. Glaser, Jr Richard F. Boyer '68 ++ Richard R. Bradley '61 Charles J. Brand '74 `77G++ James A. Branegan, Jr. '35 ++ D A. Broscious '55 ++ David B. Brown `12P Harry K. Brown, Jr. `66 Judith S. Brown `12P Linda K. Brown

Royer, Dana

173

Application of lactic acid in combination with melanosis inhibitors to improve shelf life of Texas brown shrimp (Penaeus aztecus)  

E-Print Network (OSTI)

The shelf life of fresh shrimp stored on ice is limited by two factors: melanosis (blackspot) and microbial spoilage. In this study L-lactic acid was tested, alone and in combination with sodium bisulfite and 4-hexylresorcinol, to determine their effectiveness as both melanosis and microbial spoilage inhibitors. Brown shrimp (Penaeus aztecus) were obtained from the Gulf of Mexico on board a commercial fishing vessel. Immediately after harvest, the shrimp were separated from the rest of the catch. The shrimp were then headed, washed, and sorted into six groups that were treated by dipping for I min in the following solutions: (1) Control (sea water), (2) 1.0% L-lactic acid, (3) 1.25% sodium bisulfite, (4) 0.0025% 4-hexylresorcinol, (5) 1.25% sodium bisulfite with 1.0% L-lactic acid, or (6) 0.0025% 4- hexylresorcinol with 1.0% L-lactic acid. Each of the six groups of shrimp was split into 2 subgroups. One subgroup of shrimp was treated immediately after sorting and the other subgroup was treated after a 2-hr delay on deck at ambient temperature to simulate normal practices during peak harvesting times. Each subgroup of shrimp was placed in a nylon mesh bag, completely submerged in the appropriate dip solution for 1 min with moderate up and down agitation, and drained. Each treatment group was stored on ice for 16 days in separate ice chests, and examined over the storage period for aerobic plate count (APC), pH, and degree of melanosis. Overall, this study demonstrated that treatment with L-lactic acid, alone or in combination with 4-hexylresorcinol, had no detectable effect on the microbiological shelf life of brown shrimp (Penaeus aztecus). In addition, 4-hexylresorcinol performed exceptionally well as a melanosis inhibitor, whether alone or in combination with L-lactic acid. However, extensive bacterial growth was demonstrated in the 4-hexylresorcinol dip solution during normal storage on deck, creating the potential for a heavy bacterial inoculation of shrimp during a typical dipping process. Addition of L-lactic acid to the 4-hexylresorcinol dip solution prevented bacterial growth in the dip solution and did not interfere with melanosis inhibition.

Benner, Ronald Allen

1993-01-01T23:59:59.000Z

174

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

175

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

176

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

177

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

178

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

179

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

180

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

Note: This page contains sample records for the topic "vessel ron brown" 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

Reclaiming residual space from elevated transport infrastructure : time, space, and activity under the Chicago Brown Line  

E-Print Network (OSTI)

This thesis studies the non-transport functions of the residual space generated by elevated transport infrastructure and its relationship with abutting neighborhoods The space under the Chicago Brown Line, among all other ...

Su, Jing, S.M. Massachusetts Institute of Technology

2005-01-01T23:59:59.000Z

182

STATE OF CALIFORNIA NATURAL RESOURCES AGENCY EDMUND G. BROWN JR., Governor CALIFORNIA ENERGY COMMISSION  

E-Print Network (OSTI)

STATE OF CALIFORNIA ­ NATURAL RESOURCES AGENCY EDMUND G. BROWN JR., Governor CALIFORNIA ENERGY://opr.ca.gov. The website provides a link to general CEQA information. The best contact for CEQA is the local lead agency

183

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

184

Investigation of Browns Ferry 2 Reactor, Cycle 12 Corrosion Failures: Volume 1: Poolside Examination Results  

Science Conference Proceedings (OSTI)

BWR fuel rods of the GE13 (9x9) design developed leaks during Cycle 12 of the Browns Ferry 2 reactor. This report presents the results of an examination of this fuel and similar, non-leaking assemblies in the storage pool at the Browns Ferry site. The objective was to define the extent of leakage and the conditions associated with the leaking rods.

2004-12-22T23:59:59.000Z

185

HOT METHANE LINE LISTS FOR EXOPLANET AND BROWN DWARF ATMOSPHERES  

SciTech Connect

We present comprehensive experimental line lists of methane (CH{sub 4}) at high temperatures obtained by recording Fourier transform infrared emission spectra. Calibrated line lists are presented for the temperatures 300-1400 Degree-Sign C at twelve 100 Degree-Sign C intervals spanning the 960-5000 cm{sup -1} (2.0-10.4 {mu}m) region of the infrared. This range encompasses the dyad, pentad, and octad regions, i.e., all fundamental vibrational modes along with a number of combination, overtone and hot bands. Using our CH{sub 4} spectra, we have estimated empirical lower state energies (E{sub low} in cm{sup -1}) and our values have been incorporated into the line lists along with line positions ({nu}-bar in cm{sup -1}) and calibrated line intensities (S' in cm molecule{sup -1}). We expect our hot CH{sub 4} line lists to find direct application in the modeling of planetary atmospheres and brown dwarfs.

Hargreaves, Robert J.; Bernath, Peter F. [Department of Chemistry, University of York, Heslington, York YO10 5DD (United Kingdom); Beale, Christopher A.; Michaux, Laurent; Irfan, Melis, E-mail: rjh135@york.ac.uk, E-mail: cbeale@odu.edu, E-mail: lm595@york.ac.uk, E-mail: melis.irfan@postgrad.manchester.ac.uk, E-mail: pbernath@odu.edu [Department of Physics, University of York, Heslington, York YO10 5DD (United Kingdom)

2012-09-20T23:59:59.000Z

186

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....

187

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

188

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

189

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

190

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

191

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

192

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

193

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

194

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

195

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

196

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

197

Harold Brown, 1992 | U.S. DOE Office of Science (SC)  

Office of Science (SC) Website

Harold Brown, 1992 Harold Brown, 1992 The Enrico Fermi Award Fermi Award Home Nomination & Selection Guidelines Award Laureates 2010's 2000's 1990's 1980's 1970's 1960's 1950's Ceremony The Life of Enrico Fermi Contact Information The Enrico Fermi Award U.S. Department of Energy SC-2/Germantown Building 1000 Independence Ave., SW Washington, DC 20585 P: (301) 903-9395 E: fermi.award@science.doe.gov 1990's Harold Brown, 1992 Print Text Size: A A A RSS Feeds FeedbackShare Page Citation For his outstanding contributions to national security; in technical leadership in the development of nuclear weapons, in leadership of Lawrence Livermore National Laboratory in its formative years, in leadership in formulating nuclear deterrence policy during the difficult Cold War period; and for excellent service and continued counsel to the government

198

Governor Brown's Research Priorities in the areas of Clean Energy and  

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

Governor Brown's Research Priorities in the areas of Clean Energy and Governor Brown's Research Priorities in the areas of Clean Energy and Energy Efficiency Speaker(s): Clifford Rechtschaffen Edward Randolph Heather Sanders Laurie ten Hope Date: October 26, 2012 - 12:00pm Location: 90-3122 Seminar Host/Point of Contact: Jodi Bellacicco Karen Salvini The Brown Administration has been pursuing numerous clean energy policies. These include developing 20,000 megawatts of renewable energy, including 12,000 megawatts of distributed renewable generation by 2020, aggressive building and appliance efficiency standards, including aggressive targets for zero net energy homes and businesses, new financing tools to incentivize widespread energy retrofits of existing buildings, development of energy storage to meet peak load demand and to provide

199

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

200

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

Note: This page contains sample records for the topic "vessel ron brown" 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

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

202

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

203

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

204

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

205

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

206

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....

207

STATE OF CALIFORNIA NATURAL RESOURCES AGENCY EDMUND G. BROWN JR., Governor CALIFORNIA ENERGY COMMISSION  

E-Print Network (OSTI)

for Calculating the Energy Efficiency of Single- Voltage External AC-DC and AC-AC Power Supplies", August 11, 2004STATE OF CALIFORNIA ­ NATURAL RESOURCES AGENCY EDMUND G. BROWN JR., Governor CALIFORNIA ENERGY COMMISSION 1516 NINTH STREET SACRAMENTO, CA 95814-5512 www.energy.ca.gov California Appliance Efficiency

208

Heterogeneous reactions in aircraft gas turbine engines R. C. Brown and R. C. Miake-Lye  

E-Print Network (OSTI)

Heterogeneous reactions in aircraft gas turbine engines R. C. Brown and R. C. Miake-Lye Aerodyne to estimate the maximum effect of heterogeneous reactions on trace species evolution in aircraft gas turbines species emissions from gas turbine engines are of interest because of environmental and human health

Waitz, Ian A.

209

STATE OF CALIFORNIA -NATURAL RESOURCES AGENCY EDMUND G. BROWN JR., Governor CALIFORNIA ENERGY COMMISSION  

E-Print Network (OSTI)

." .. I Proceeding History Since July 11, 2012 Adoption, On July 11,2012, the Energy Commission adoptedSTATE OF CALIFORNIA - NATURAL RESOURCES AGENCY EDMUND G. BROWN JR., Governor CALIFORNIA ENERGY COMMISSION 1516 Ninth Street Sacramento, California 95814 Main website: www.energy.ca.gov In the matter of

210

Shutdown Hideout Return Chemistry at Browns Ferry-2 and Hatch-2  

Science Conference Proceedings (OSTI)

This report describes and analyzes the results of augmented hideout return studies conducted at the Browns Ferry 2 and Hatch 2 boiling water reactors (BWRs) during shutdowns in the spring of 2003. The aim was to provide insights into differences in corrosion of similar fuel cladding materials at the two facilities.

2004-03-04T23:59:59.000Z

211

Capping the Brown Energy Consumption of Internet Services at Low Cost  

E-Print Network (OSTI)

energy" (produced via carbon-intensive means) relative to renewable or "green" energy. This paper current efficiency trends, this gigantic amount of energy will have nearly doubled by 2011 for an overall-intensive energy as "brown" energy, in contrast with "green" or renewable energy.) We argue that placing caps

Martonosi, Margaret

212

Hot Dry Rock Geothermal Energy Development in the USA David Duchane and Donald Brown  

E-Print Network (OSTI)

utility options such as pumped storage or compressed air energy storage (CAES) is that the HDR power plant1 Hot Dry Rock Geothermal Energy Development in the USA by David Duchane and Donald Brown Los energy resources lies right beneath our feet in the form of hot dry rock (HDR), the common geologic

213

Thermal dissolution of brown and hard coals with the addition of natural and organosilicon compounds  

Science Conference Proceedings (OSTI)

The addition of activators (natural compounds and their mixtures with organo-silicates) was found to double the yield of liquid products from the thermal solvent extraction of Kansk-Achinsk brown coal, and increase by 20% the yield from Kuzbass bituminous coal. High concentrations of sulphur in the natural additives reduced the extractability of the coal.

Vol-Ehpshtein, A.B.; Gorlov, E.G.; Shataeva, T.A.; Shpil'berg, M.B.

1983-01-01T23:59:59.000Z

214

STATE OF CALIFORNIA --NATURAL RESOURCES AGENCY EDMUND G. BROWN JR., Governor CALIFORNIA ENERGY COMMISSION  

E-Print Network (OSTI)

STATE OF CALIFORNIA -- NATURAL RESOURCES AGENCY EDMUND G. BROWN JR., Governor CALIFORNIA ENERGY COMMISSION 1516 Ninth Street Sacramento, California 95814 Main website: www.energy.ca.gov NOTICE OF POSTPONEMENT OF HEARING FOR CONSIDERATION AND POSSIBLE ADOPTION REVISIONS TO THE CALIFORNIA BUILDING ENERGY

215

STATE OF CALIFORNIA NATURAL RESOURCES AGENCY EDMUND G. BROWN JR., Governor CALIFORNIA ENERGY COMMISSION  

E-Print Network (OSTI)

STATE OF CALIFORNIA ­ NATURAL RESOURCES AGENCY EDMUND G. BROWN JR., Governor CALIFORNIA ENERGY Orr Springs Road, Ukiah, California ­ Off-site, at the County of Mendocino Department of Planning and Building Services, located at 501 Low Gap Road, Ukiah, California ­ Online, at [ http

216

STATE OF CALIFORNIA --NATURAL RESOURCES AGENCY EDMUND G. BROWN JR., Governor CALIFORNIA ENERGY COMMISSION  

E-Print Network (OSTI)

STATE OF CALIFORNIA -- NATURAL RESOURCES AGENCY EDMUND G. BROWN JR., Governor CALIFORNIA ENERGY COMMISSION 1516 Ninth Street Sacramento, California 95814 Main website: www.energy.ca.gov Notice of major energy trends and issues facing California's electricity, natural gas, and transportation fuel

217

STATE OF CALIFORNIA NATURAL RESOURCES AGENCY EDMUND G. BROWN JR., Governor CALIFORNIA ENERGY COMMISSION  

E-Print Network (OSTI)

STATE OF CALIFORNIA ­ NATURAL RESOURCES AGENCY EDMUND G. BROWN JR., Governor CALIFORNIA ENERGY of Information to Third-Party Certifier for Submittal to the California Energy Commission California Appliance Efficiency Program California Code of Regulations, Title 20, Section 1606 This form is used twice in the data

218

STATE OF CALIFORNIA --NATURAL RESOURCES AGENCY EDMUND G. BROWN JR., Governor CALIFORNIA ENERGY COMMISSION  

E-Print Network (OSTI)

STATE OF CALIFORNIA -- NATURAL RESOURCES AGENCY EDMUND G. BROWN JR., Governor CALIFORNIA ENERGY COMMISSION 1516 Ninth Street Sacramento, California 95814 Main website: www.energy.ca.gov Notice of California Natural Gas Stakeholders Working Group Meeting The Natural Gas Stakeholders Working Group

219

STATE OF CALIFORNIA NATURAL RESOURCES AGENCY EDMUND G. BROWN JR., Governor CALIFORNIA ENERGY COMMISSION  

E-Print Network (OSTI)

STATE OF CALIFORNIA ­ NATURAL RESOURCES AGENCY EDMUND G. BROWN JR., Governor CALIFORNIA ENERGY COMMISSION 1516 NINTH STREET SACRAMENTO, CA 95814-5512 www.energy.ca.gov California Appliance Efficiency of California Code of Regulations, federal law, and all other documents applicable to each category for which

220

STATE OF CALIFORNIA NATURAL RESOURCES AGENCY EDMUND G. BROWN JR., Governor CALIFORNIA ENERGY COMMISSION  

E-Print Network (OSTI)

STATE OF CALIFORNIA ­ NATURAL RESOURCES AGENCY EDMUND G. BROWN JR., Governor CALIFORNIA ENERGY, for the purpose of meeting continuing disclosure requirements, at least one of which must be a California State if they are not currently auditing a California State Agency governmental bond issue, but meet the requirement of auditing

Note: This page contains sample records for the topic "vessel ron brown" 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

STATE OF CALIFORNIA NATURAL RESOURCES AGENCY EDMUND G. BROWN JR., Governor CALIFORNIA ENERGY COMMISSION  

E-Print Network (OSTI)

STATE OF CALIFORNIA ­ NATURAL RESOURCES AGENCY EDMUND G. BROWN JR., Governor CALIFORNIA ENERGY to Third-Party Certifier for Submittal to the California Energy Commission California Appliance Efficiency Program California Code of Regulations, Title 20, Section 1606 This form is used twice in the data

222

STATE OF CALIFORNIA --NATURAL RESOURCES AGENCY EDMUND G. BROWN JR., Governor CALIFORNIA ENERGY COMMISSION  

E-Print Network (OSTI)

STATE OF CALIFORNIA -- NATURAL RESOURCES AGENCY EDMUND G. BROWN JR., Governor CALIFORNIA ENERGY COMMISSION 1516 Ninth Street Sacramento, California 95814 Main website: www.energy.ca.gov Bright Schools All publicly funded California K-12 school districts are eligible for assistance from the Bright

223

The First Hundred Brown Dwarfs Discovered by the Wide-field Infrared Survey Explorer (WISE)  

E-Print Network (OSTI)

We present ground-based spectroscopic verification of 6 Y dwarfs (see also Cushing et al.), 89 T dwarfs, 8 L dwarfs, and 1 M dwarf identified by the Wide-field Infrared Survey Explorer (WISE). Eighty of these are cold brown ...

Bochanski, John J.

224

STATE OF CALIFORNIA NATURAL RESOURCES AGENCY EDMUND G. BROWN JR., Governor CALIFORNIA ENERGY COMMISSION  

E-Print Network (OSTI)

Typical PerUnit Energy Savings and Incremental Cost Market Characteristics and Market Share InstalledSTATE OF CALIFORNIA ­ NATURAL RESOURCES AGENCY EDMUND G. BROWN JR., Governor CALIFORNIA ENERGY COMMISSION 1516 NINTH STREET SACRAMENTO, CA 95814-5512 www.energy.ca.gov March 25, 2013 INVITATION

225

STATE OF CALIFORNIA --NATURAL RESOURCES AGENCY EDMUND G. BROWN JR., Governor CALIFORNIA ENERGY COMMISSION  

E-Print Network (OSTI)

STATE OF CALIFORNIA -- NATURAL RESOURCES AGENCY EDMUND G. BROWN JR., Governor CALIFORNIA ENERGY COMMISSION 1516 Ninth Street Sacramento, California 95814 Main website: www.energy.ca.gov Notice of Availability Overall Program Guidebook for the Renewable Energy Program, Fourth Edition Publication No. CEC-300

226

STATE OF CALIFORNIA --NATURAL RESOURCES AGENCY EDMUND G. BROWN JR., Governor CALIFORNIA ENERGY COMMISSION  

E-Print Network (OSTI)

STATE OF CALIFORNIA -- NATURAL RESOURCES AGENCY EDMUND G. BROWN JR., Governor CALIFORNIA ENERGY COMMISSION 1516 Ninth Street Sacramento, California 95814 Main website: www.energy.ca.gov Notice of Availability Developing Renewable Generation on State Property Installing Renewable Energy on State Buildings

227

STATE OF CALIFORNIA --NATURAL RESOURCES AGENCY EDMUND G BROWN, JR., Governor CALIFORNIA ENERGY COMMISSION  

E-Print Network (OSTI)

STATE OF CALIFORNIA -- NATURAL RESOURCES AGENCY EDMUND G BROWN, JR., Governor CALIFORNIA ENERGY COMMISSION 1516 Ninth Street Sacramento, California 95814 Main website: www.energy.ca.gov Notice of Availability 2010 Integrated Energy Policy Report Update Publication No. CEC-100-2010-001-CMF Docket No. 10-IEP

228

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

229

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

230

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

231

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

232

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

233

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

234

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...

235

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

236

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

237

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

238

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

239

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

240

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

Note: This page contains sample records for the topic "vessel ron brown" 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

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,

242

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

243

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

244

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

245

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

246

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

247

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

248

Environmental Assessment for the Partial Funding of a Proposed Life Sciences Building at Brown University, Providence, Rhode Island  

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

Environmental Assessment for the Partial Funding of a Environmental Assessment for the Partial Funding of a Proposed Life Sciences Building at Brown University, Providence, Rhode Island FINAL July 2003 National Aeronautics and Space Administration Washington, D.C. 20546-0001 U.S. Department of Energy, Chicago Operations Office Argonne, Illinois 60439 Environmental Assessment for the Partial Funding of a Proposed Life Sciences Building at Brown University, Providence, Rhode Island Environmental Assessment for the Partial Funding of a Proposed Life Sciences Building at Brown University, Providence, Rhode Island FINAL Lead Agency: National Aeronautics and Space Administration Cooperating Agency: U.S. Department of Energy Proposed Action: Partial funding for a new Life Sciences Building at Brown

249

Microsoft PowerPoint - Brown_Idaho on Renewable Energy.ppt  

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

Policy Options for Policy Options for Renewable Energy Matthew H. Brown Energy Program Director National Conference of State Legislatures matthew.brown@ncsl.org September 2003 Organization The Idaho context Policies for Idaho to consider The Importance of This Committee In general, other bodies of government like the PUC will wait for direction from the legislature on what to do, especially with renewables. The legislature's decisions are critical. Idaho Power Generation Despite the fact that Idaho generation is overwhelmingly hydro, retail power rates have fluctuated considerably in the past five years. This has happened in large part because Idaho utilities have needed to purchase power from more volatile regional power markets. Natural gas prices drive many of these markets.

250

Revisiting the Hanbury Brown-Twiss Setup for Phase Fluctuating Bose Gases  

E-Print Network (OSTI)

The Hanbury Brown-Twiss experiment has proved to be an effective means of measuring two-point correlation function of identical particles. We analyze experimental observation of stripes formation of a phase fluctuating Bose-Einstein condensates in a highly elongated 3D traps [Dettmer {\\em et al.}, Phys. Rev. Lett. {\\bf 87}, 160406 (2001)] by means of axial two-point correlation functions. We also predict that the stripes are present in quasi-1D Bose gas in the mean-field as well as in the hard-core bosons regimes. These stripes can be realized by measuring the axial two-point correlation functions by using the Bragg interferometric method which is similar to the original Hanbury Brown and Twiss experimental setup.

Tarun Kanti Ghosh

2004-06-22T23:59:59.000Z

251

STATE OF CALIFORNIA - THE NATURAL RESOURCES AGENCY EDMUND G. BROWN, JR., Governor  

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

THE NATURAL RESOURCES AGENCY EDMUND G. BROWN, JR., Governor THE NATURAL RESOURCES AGENCY EDMUND G. BROWN, JR., Governor CALIFORNIA ENERGY COMMISSION 1516 Ninth Street, MS 14 Sacramento, California 95814 Main website: www.energy.ca.gov January 12, 2011 United States Department of Energy (DOE) Via e-mail: expartecommunications@hq.doe.gov RE: Ex parte communication of the California Energy Commission Docket No. EERE-2008-BT-STD-0005 To Whom It May Concern, On January 6, 2011, Mike Leaon, Harinder Singh, Ken Rider, and Dennis Beck of the California Energy Commission (CEC) had a telephone conversation with Victor Petrolati of DOE regarding the above referenced proceeding, concerning energy conservation standards for battery chargers and Class A external power supplies. The purpose of the meeting was for CEC and DOE staff to update each other on the

252

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

253

Luminant's Big Brown Plant wins for continuous improvement and safety programs  

SciTech Connect

Staff from Luminant's Big Brown Plant accepted the PRB Coal Users' Group's top honour for innovative improvements to coal-handling systems and a sterling safety record. The numbers reveal their accomplishments: an average EFOR less than 4%, an availability factor averaging 90% for a plant that burns a lignite/PRB mix, and staff who worked more than 2.6 million man-hours since March 2000 without a lost-time injury. 13 photos., 1 tab.

Peltier, R.

2008-07-15T23:59:59.000Z

254

Process Data Network Architecture Plan for the Browns Ferry Nuclear Plants  

Science Conference Proceedings (OSTI)

Computer networks are essential in efficiently managing the large volumes of data used in power plant operation. Nuclear plants, however, have been cautious in applying computer technology because of their unique safety, security, and regulatory requirements. This report describes a strategic plan developed to manage the evolution of the network that processes real-time operating data for Tennessee Valley Authority's Browns Ferry nuclear plants.

1994-01-01T23:59:59.000Z

255

The Kellogg brown & Root Transport Reactor: PSDR Test Results and Economic Evaluation  

Science Conference Proceedings (OSTI)

To be competitive, new coal-based power plants must have low capital costs and use coal in a highly efficient, cost-effective, and environmentally superior manner. One of the most cost-competitive, coal-based power plant technologies is believed to be an air-blown, combined cycle incorporating a partial gasifier and a pressurized char combustor. This report presents preliminary results from the evaluation of one such technology, Kellogg Brown and Root's (KBR) gasification combined cycle (GCC). The report...

1999-12-08T23:59:59.000Z

256

Investigation of Browns Ferry 2 Reactor Cycle 12 Fuel Corrosion Failures  

Science Conference Proceedings (OSTI)

BWR fuel rods from 63 bundles of the Reload 10 GE13 (9x9) design developed leaks during Cycle 12 of the Browns Ferry 2 reactor. Poolside examination subsequently revealed accelerated cladding corrosion as the apparent failure mechanism (EPRI report 1009729). The failure root cause could not be determined from site examinations alone and thus follow-on hot cell examinations were needed to provide additional information that might help to further understand the failure mechanism, the root cause, and linger...

2006-06-19T23:59:59.000Z

257

Investigation of Browns Ferry 2 Reactor Cycle 12 Fuel Corrosion Failures, Volume 3: Assessment of Results  

Science Conference Proceedings (OSTI)

Boiling water reactor (BWR) fuel rods from 63 bundles of the Reload 10 GE13 (9x9) design developed leaks during Cycle 12 of the Browns Ferry 2 reactor. Root cause evaluations, including poolside and hot cell examinations were performed. The details of the investigation are documented in a series of reports and presentations. This report compiles significant findings of the overall investigation and assesses these results with respect to the cause of failure. In addition, new laboratory data to support th...

2007-12-05T23:59:59.000Z

258

Humic substances and nitrogen-containing compounds from low rank brown coals  

SciTech Connect

Coal is one of the sources of nitrogen-containing compounds (NCCs). Recovery of NCCs from brown coals in high yield was carried out from tars of stepwise semicoking of brown coals. Humic acids have been shown to contain many types of nitrogen compounds. Humic acids are thought to be complex aromatic macromolecules with amino acids, amino sugars, peptides, and aliphatic compounds that are involved in the linkages between the aromatic groups. Humic acids extracted from peats, brown coals, and lignites, are characterized using different techniques. Humic substances (HSs) have several known benefits to agriculture. The properties of humic substances vary from source to source, because they are heterogeneous mixtures of biochemical degradation products from plant and animal residues, and synthesis activities of microorganisms. HSs have been considered to be a significant floculant in surface water filtration plants for the production of drinking water as well as the processing of water. HSs are produced from chemical and biological degradation of plant and animal residues and from synthetic activities of microorganisms.

Demirbas, A.; Kar, Y.; Deveci, H. [Selcuk University, Konya (Turkey). Department of Chemical Engineering

2006-03-15T23:59:59.000Z

259

Beyond the T Dwarfs: Theoretical Spectra, Colors, and Detectability of the Coolest Brown Dwarfs  

E-Print Network (OSTI)

We explore the spectral and atmospheric properties of brown dwarfs cooler than the latest known T dwarfs. Our focus is on the yet-to-be-discovered free-floating brown dwarfs in the \\teff range from $\\sim$800 K to $\\sim$130 K and with masses from 25 to 1 \\mj. This study is in anticipation of the new characterization capabilities enabled by the launch of SIRTF and the eventual launch of JWST. We provide spectra from $\\sim$0.4 \\mic to 30 \\mic, highlight the evolution and mass dependence of the dominant H$_2$O, CH$_4$, and NH$_3$ molecular bands, consider the formation and effects of water-ice clouds, and compare our theoretical flux densities with the sensitivities of the instruments on board SIRTF and JWST. The latter can be used to determine the detection ranges from space of cool brown dwarfs. In the process, we determine the reversal point of the blueward trend in the near-infrared colors with decreasing \\teff, the \\teffs at which water and ammonia clouds appear, the strengths of gas-phase ammonia and methan...

Burrows, A; Lunine, J; Burrows, Adam; Sudarsky, David; Lunine, Jonathan

2003-01-01T23:59:59.000Z

260

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

Note: This page contains sample records for the topic "vessel ron brown" 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.


261

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

262

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

263

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

264

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

265

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

266

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

267

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

268

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

269

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

270

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

271

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

272

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

273

Assessing the imprint of space, geography, land cover, and host species on the local abundance of a generalist nest parasite, the Brown-headed Cowbird.  

E-Print Network (OSTI)

??The Brown-headed Cowbird is an obligate nest parasite suspected of causing local population declines in several threatened and endangered passerine species. Much attention has been (more)

Cummings, Katherine Elizabeth Rainey 1982-

2013-01-01T23:59:59.000Z

274

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

275

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

276

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

277

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

278

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

279

"1. Browns Ferry","Nuclear","Tennessee Valley Authority",3309  

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

Alabama" Alabama" "1. Browns Ferry","Nuclear","Tennessee Valley Authority",3309 "2. James H Miller Jr","Coal","Alabama Power Co",2675 "3. Barry","Coal","Alabama Power Co",2575 "4. E C Gaston","Coal","Alabama Power Co",1878 "5. H Allen Franklin Combined Cycle","Gas","Southern Power Co",1815 "6. Joseph M Farley","Nuclear","Alabama Power Co",1734 "7. Widows Creek","Coal","Tennessee Valley Authority",1604 "8. Colbert","Coal","Tennessee Valley Authority",1574 "9. E B Harris Electric Generating Plant","Gas","Southern Power Co",1269

280

Fuel Reliability Program: Browns Ferry Fuel Corrosion Failures Root Cause Investigation  

Science Conference Proceedings (OSTI)

Sixty-three GE13 fuel bundles failed in Browns Ferry Unit 2 (BF2) during Cycle 12; three GE13 assemblies failed in BF Unit 3 (BF3) during Cycle 11. The affected fuel in BF2 was in its second cycle of operation and the fuel in BF3 in its third at the time of failure. Global Nuclear Fuel (GNF), General Electric-Hitachi (GEH), Tennessee Valley Authority (TVA), and the Electric Power Research Institute (EPRI) investigated the cause of the failures. The investigation included evaluations of materials and manu...

2010-09-30T23:59:59.000Z

Note: This page contains sample records for the topic "vessel ron brown" 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.


281

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

282

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

283

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

284

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

285

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

286

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

287

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

288

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

289

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.

290

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

291

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

292

Rich Brown  

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

University. Links applicationpdf icon Resume Complete publications This publications database is an ongoing project, and not all Division publications are represented here...

293

Browne bio  

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

Peter Nanos Director Los Alamos National Laboratory Retired Vice Admiral G. Peter Nanos, named Interim Director of Los Alamos National Laboratory January 6, 2003, was confirmed by...

294

Early maturation processes in coal. Part 2: Reactive dynamics simulations using the ReaxFF reactive force field on Morwell Brown coal structures  

E-Print Network (OSTI)

Early maturation processes in coal. Part 2: Reactive dynamics simulations using the ReaxFF reactive force field on Morwell Brown coal structures Elodie Salmon a , Adri C.T. van Duin b , François Lorant Brown coal using the ReaxFF reactive force field. We find that these reactive MD simulations

Goddard III, William A.

295

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

296

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

297

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

298

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

299

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

300

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

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

O [G] IS A FREE MODULE OVER O[G] KENNETH A. BROWN, IAIN GORDON, AND J. T. STAFFORD  

E-Print Network (OSTI)

O [G] IS A FREE MODULE OVER O[G] KENNETH A. BROWN, IAIN GORDON, AND J. T. STAFFORD Abstract. We GORDON, AND J. T. STAFFORD that UH = {x U : (x) = x 1} = O, that the natural map U O U U H given by x

Gordon, Iain

302

STATE OF CALIFORNIA --THE RESOURCES PROVIDER Edmund G. Brown Jr., Governor CALIFORNIA ENERGY COMMISSION 1516 Ninth Street Sacramento, California 95814  

E-Print Network (OSTI)

electronically, on paper, and orally at Energy Commission hearings. A. A Brief History of the Energy Commission1 STATE OF CALIFORNIA -- THE RESOURCES PROVIDER Edmund G. Brown Jr., Governor CALIFORNIA ENERGY COMMISSION 1516 Ninth Street Sacramento, California 95814 Main website: www.energy.ca.gov INITIAL STATEMENT

303

Speakers: Adam Sieminski, Deutsche Bank Stephen P. A. Brown, Resources for the Future  

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

5: "Energy and the Economy" 5: "Energy and the Economy" Speakers: Adam Sieminski, Deutsche Bank Stephen P. A. Brown, Resources for the Future Donald L. Paul, University of Southern California Energy Institute David Sandalow, DOE Christof Rühl, Group Chief Economist, BP [Note: Recorders did not pick up introduction of panel (see biographies for details on the panelists) or introduction of session.] Adam: Microphone. So, we've lost a little bit of time because of all of the sessions running a bit over, but here is how we're going to make that up. I had about 12 minutes worth of slides that we're going to abandon. Isn't that great? We get to hear from the panelists rather than me. Now, my name is Adam Sieminski. I'm the Chief Energy Economist for Deutsche Bank. Don't let that intimidate you. I'm really a civil

304

STATE OF CALIFORNIA - NATURAL RESOURCES AGENCY EDMUND G. BROWN JR., Governor  

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

NATURAL RESOURCES AGENCY EDMUND G. BROWN JR., Governor CALIFORNIA ENERGY COMMISSION 1516 NINTH STREET SACRAMENTO, CA 95814-5512 WWIN.energy.ca.gov March 28, 2012 Lamont Jackson Office of Electricity Delivery and Energy Reliability Mail Code: OE-20 U.S. Department of Energy 1000 Independence Avenue SW Washington, DC 20585 Lamont.Jackson@hg.doe.gov Dear Mr. Jackson: The California Energy Commission staff thanks you for the opportunity to provide comments on DOE's Request for Information (RFI) on the Rapid Response Team for Transmission Docket No. RRTT-IR-001. The RFI focuses on learning how to make the development times for generation and transmission more commensurate with one another. In the RFI, the DOE highlighted three problems that may arise in the

305

Microsoft PowerPoint - Brown_CBP_Codes_and_CodeIntegration_kgb_final.ppt  

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

Partnership: Partnership: Demonstration of Coupling and Code Integration Kevin G. Brown, Ph.D. PA Community of Practice Technical Exchange Richland, WA 13-14 April 2010 Cementitious Barriers Partnership 13 April 2010 Linking Prototype Cases to Performance Models through System Abstraction and Validated by Laboratory and Field Testing Cementitious Barriers Partnership Sulfate Attack as a "Proof of Principle" for Coupling of Phenomena 13 April 2010 THAMES (NIST) Virtual "micro-probe" of microstructure * Constructs time-dependent 3-D virtual microstructures of a cementitious binder during hydration or degradation * Computes important engineering properties of a concrete made from a binder at prescribed times Planned model improvements * Embed geochemical modeling code (GEMS) into microstructure

306

Field Testing of Activated Carbon Injection Options for Mercury Control at TXU's Big Brown Station  

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

Field TesTing oF AcTivATed cArbon Field TesTing oF AcTivATed cArbon injecTion opTions For Mercury conTrol AT TXu's big brown sTATion Background The 2005 Clean Air Mercury Rule will require significant reductions in mercury emissions from coal-fired power plants. Lignite coal is unique because of its highly variable ash content (rich in alkali and alkaline-earth elements), high moisture levels, low chlorine content, and high calcium content. Unique to Texas lignite coals are relatively high iron and selenium concentrations. When combusting Texas lignite coals, up to 80 percent of the mercury in the flue gas is present as elemental mercury, which is not readily captured by downstream pollution control devices. To better understand the factors that influence mercury control at units firing

307

Genome sequence of the brown Norway rat yields insights into mammalian evolution  

SciTech Connect

The laboratory rat (Rattus norvegicus) is an indispensable tool in experimental medicine and drug development, having made inestimable contributions to human health. We report here the genome sequence of the Brown Norway (BN) rat strain. The sequence represents a high-quality 'draft' covering over 90 percent of the genome. The BN rat sequence is the third complete mammalian genome to be deciphered, and three-way comparisons with the human and mouse genomes resolve details of mammalian evolution. This first comprehensive analysis includes genes and proteins and their relation to human disease, repeated sequences, comparative genome-wide studies of mammalian orthologous chromosomal regions and rearrangement breakpoints, reconstruction of ancestral karyotypes and the events leading to existing species, rates of variation, and lineage-specific and lineage-independent evolutionary events such as expansion of gene families, orthology relations and protein evolution.

Gibbs, Richard A.; Weinstock, George M.; Metzker, Michael L.; Muzny, Donna M.; Sodergren, Erica J.; Scherer, Steven; Scott, Graham; Steffen, David; Worley, Kim C.; Burch, Paula E.; Okwuonu, Geoffrey; Hines, Sandra; Lewis, Lora; DeRamo, Christine; Delgado, Oliver; Dugan-Rocha, Shannon; Miner, George; Morgan, Margaret; Hawes, Alicia; Gill, Rachel; Holt, Robert A.; Adams, Mark D.; Amanatides, Peter G.; Baden-Tillson, Holly; Barnstead, Mary; Chin, Soo; Evans, Cheryl A.; Ferriera, Steven; Fosler, Carl; Glodek, Anna; Gu, Zhiping; Jennings, Don; Kraft, Cheryl L.; Nguyen, Trixie; Pfannkoch, Cynthia M.; Sitter, Cynthia; Sutton, Granger G.; Venter, J. Craig; Woodage, Trevor; Smith, Douglas; Lee, Hong-Maei; Gustafson, Erik; Cahill, Patrick; Kana, Arnold; Doucette-Stamm, Lynn; Weinstock, Keith; Fechtel, Kim; Weiss, Robert B.; Dunn, Diane M.; Green, Eric D.; Blakesley, Robert W.; Bouffard, Gerard G.; de Jong, Pieter J.; Osoegawa, Kazutoyo; Zhu, Baoli; Marra, Marco; Schein, Jacqueline; Bosdet, Ian; Fjell, Chris; Jones, Steven; Krzywinski, Martin; Mathewson, Carrie; Siddiqui, Asim; Wye, Natasja; McPherson, John; Zhao, Shaying; Fraser, Claire M.; Shetty, Jyoti; Shatsman, Sofiya; Geer, Keita; Chen, Yixin; Abramzon, Sofyia; Nierman, William C.; Havlak, Paul H.; Chen, Rui; Durbin, K. James; Egan, Amy; Ren, Yanru; Song, Xing-Zhi; Li, Bingshan; Liu, Yue; Qin, Xiang; Cawley, Simon; Cooney, A.J.; D'Souza, Lisa M.; Martin, Kirt; Wu, Jia Qian; Gonzalez-Garay, Manuel L.; Jackson, Andrew R.; Kalafus, Kenneth J.; McLeod, Michael P.; Milosavljevic, Aleksandar; Virk, Davinder; Volkov, Andrei; Wheeler, David A.; Zhang, Zhengdong; Bailey, Jeffrey A.; Eichler, Evan E.; Tuzun, Eray; Birney, Ewan; Mongin, Emmanuel; Ureta-Vidal, Abel; Woodwark, Cara; Zdobnov, Evgeny; Bork, Peer; Suyama, Mikita; Torrents, David; Alexandersson, Marina; Trask, Barbara J.; Young, Janet M.; et al.

2004-02-02T23:59:59.000Z

308

Annual radiological environmental operating report: Browns Ferry Nuclear Plant, 1992. Operations Services/Technical Programs  

Science Conference Proceedings (OSTI)

This report describes the environmental radiological monitoring program conducted by TVA in the vicinity of Browns Ferry Nuclear Plant (BFN) in 1992. The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples. Samples are taken from stations in the general area of the plant and from areas not influenced by plant operations. Station locations are selected after careful consideration of the weather patterns and projected radiation doses to the various areas around the plant. Material sampled includes air, water, milk, foods, vegetation, soil, fish, sediment, and direct radiation levels. Results from stations near the plant are compared with concentrations from control stations and with preoperational measurements to determine potential impacts of plant operations. Small amounts of Co-60 and Cs-134 were found in sediment samples downstream from the plant. This activity in stream sediment would result in no measurable increase over background in the dose to the general public.

Not Available

1993-04-01T23:59:59.000Z

309

Finding benchmark brown dwarfs to probe the IMF as a function of time  

E-Print Network (OSTI)

Using a simulated disk brown dwarf (BD) population, we find that new large area infrared surveys are expected to identify enough BDs covering wide enough mass--age ranges to potentially measure the mass function down to ~0.03Mo, and the BD formation history out to 10 Gyr, at a level capable of establishing if BD formation follows star formation. We suggest these capabilities are best realised by spectroscopic calibration of BD properties (Teff, g and [M/H]) which, when combined with a measured luminosity and an evolutionary model can give BD mass and age relatively independent of BD atmosphere models. Such calibration requires an empirical understanding of how BD spectra are affected by variations in these properties, and thus the identification and study of "benchmark BDs" whose age and composition can be established independently. We identify the best sources of benchmark BDs as young open cluster members, moving group members, and wide (>1000AU) BD companions to both subgiant stars and high mass white dwarfs (WDs). We have used 2MASS to measure a wide L dwarf companion fraction of 2.7(+0.7/-0.5)%, which equates to a BD companion fraction of 34(+9/-6)% for an alpha~1 companion mass function. Using this value we simulate populations of wide BD binaries, and estimate that 80(+21/-14) subgiant--BD binaries, and 50(+13/-10) benchmark WD--BD binaries could be identified using current and new facilities. The WD--BD binaries should all be identifiable using the Large Area Survey component of UKIDSS combined with Sloan. Discovery of the subgiant--BD binaries will require a NIR imaging campaign around a large (~900) sample of Hipparcos subgiants. If identified, spectral studies of these benchmark brown dwarfs could reveal the spectral sensitivities across the Teff, g and [M/H] space probed by new surveys.

D. J. Pinfield; H. R. A. Jones; P. W. Lucas; T. R. Kendall; S. L. Folkes; A. C. Day-Jones; R. J. Chappelle; I. A. Steele

2006-03-13T23:59:59.000Z

310

Productivity and Quality of Brown Midrib (bmr) Sorghum Varieties to Producers in Central America  

E-Print Network (OSTI)

The improved dry matter digestibility of the brown midrib (bmr) sorghum cultivars is attributed to constitutive deficiencies of the lignin biosynthesis pathways which results in lower lignin concentrations. The lower lignin concentrations are expressed only in a homozygous recessive genotypes and it is phenotypically identified by a brown to tan vascular coloration present in the mid-rib of the leaf blades. Utilizing this trait increases forage consumption and productivity of both dairy and beef production. There is a need to extend this trait into more forage production systems, including those in Central America where forages constitute a major portion of the ruminants diets. To achieve this goal, the bmr12 gene was incorporated via conventional breeding, into 16 lines derived from commonly used Central American sorghum varieties. These experimental lines were tested for agronomic performance during 2010 and 2011 in the Central American region. In addition, grain and biomass composition were estimated using near-infrared reflectance spectroscopy (NIRS) whereas the dry biomass digestibility was evaluated using an in vitro approach. The combined analysis indicated the bmr trait increased in vitro dry matter digestibility and reduced acid detergent lignin and acid detergent fiber levels. This combination results in improved sorghum forage quality. Furthermore, negative traits typically associated with bmr mutants such as plant height reduction, delayed flowering, and lodging problems were not observed and the bmr trait had no effect on grain composition. Additionally, post hoc tests identified CI0947bmr as the best experimental line for dry both biomass and grain yield across multiple environments. Stability analysis, identified CI0947bmr as the most stable genotype for both traits. Finally, the which-won-where biplot analysis graphically identified CI0947bmr as the best bmr inbred for Honduras, Guatemala and Nicaragua across several environments.

Portillo Rodriguez, Ostilio Rolando

2013-05-01T23:59:59.000Z

311

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

312

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

313

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

314

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

315

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...

316

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...

317

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

318

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

319

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

320

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

Note: This page contains sample records for the topic "vessel ron brown" 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.


321

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

322

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

323

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

324

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

325

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

326

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

327

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

328

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

329

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

330

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

331

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

332

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

333

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

334

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

335

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

336

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

SciTech Connect

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

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

2012-09-17T23:59:59.000Z

337

ARM - Campaign Instrument - ronbrown  

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

govInstrumentsronbrown govInstrumentsronbrown Comments? We would love to hear from you! Send us a note below or call us at 1-888-ARM-DATA. Send Campaign Instrument : NOAA Research Vessel Ron Brown (RONBROWN) Instrument Categories Aerosols, 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 Aerosol absorption Liquid water content Particle number concentration Cloud fraction

338

Recent Progress in Retrieving Air Temperature Profiles and Air-Sea Temperature Differences from Infrared and Microwave Scan...  

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

Recent Progress in Retrieving Air Temperature Profiles Recent Progress in Retrieving Air Temperature Profiles and Air-Sea Temperature Differences from Infrared and Microwave Scanning Radiometer Data D. Cimini University of L'Aquila L'Aquila, Italy J. A. Shaw Department of Electrical and Computer Engineering Montana State University Bozeman, Montana E. R. Westwater Cooperative Institute for Research in the Environmental Sciences University of Colorado National Oceanic and Atmospheric Administration Environmental Technology Laboratory Boulder, Colorado Introduction A system of two scanning radiometers has been developed by National Oceanic and Atmospheric Administration (NOAA) Environmental Technology Laboratory (ETL) and deployed on the NOAA Ron H. Brown (RHB) Research Vessel (RV) during the Nauru99 cruise in the Tropical Western Pacific,

339

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

340

Field Testing of Activated Carbon Injection Options for Mercury Control at TXU's Big Brown Station  

Science Conference Proceedings (OSTI)

The primary objective of the project was to evaluate the long-term feasibility of using activated carbon injection (ACI) options to effectively reduce mercury emissions from Texas electric generation plants in which a blend of lignite and subbituminous coal is fired. Field testing of ACI options was performed on one-quarter of Unit 2 at TXU's Big Brown Steam Electric Station. Unit 2 has a design output of 600 MW and burns a blend of 70% Texas Gulf Coast lignite and 30% subbituminous Powder River Basin coal. Big Brown employs a COHPAC configuration, i.e., high air-to-cloth baghouses following cold-side electrostatic precipitators (ESPs), for particulate control. When sorbent injection is added between the ESP and the baghouse, the combined technology is referred to as TOXECON{trademark} and is patented by the Electric Power Research Institute in the United States. Key benefits of the TOXECON configuration include better mass transfer characteristics of a fabric filter compared to an ESP for mercury capture and contamination of only a small percentage of the fly ash with AC. The field testing consisted of a baseline sampling period, a parametric screening of three sorbent injection options, and a month long test with a single mercury control technology. During the baseline sampling, native mercury removal was observed to be less than 10%. Parametric testing was conducted for three sorbent injection options: injection of standard AC alone; injection of an EERC sorbent enhancement additive, SEA4, with ACI; and injection of an EERC enhanced AC. Injection rates were determined for all of the options to achieve the minimum target of 55% mercury removal as well as for higher removals approaching 90%. Some of the higher injection rates were not sustainable because of increased differential pressure across the test baghouse module. After completion of the parametric testing, a month long test was conducted using the enhanced AC at a nominal rate of 1.5 lb/Macf. During the time that enhanced AC was injected, the average mercury removal for the month long test was approximately 74% across the test baghouse module. ACI was interrupted frequently during the month long test because the test baghouse module was bypassed frequently to relieve differential pressure. The high air-to-cloth ratio of operations at this unit results in significant differential pressure, and thus there was little operating margin before encountering differential pressure limits, especially at high loads. This limited the use of sorbent injection as the added material contributes to the overall differential pressure. This finding limits sustainable injection of AC without appropriate modifications to the plant or its operations. Handling and storage issues were observed for the TOXECON ash-AC mixture. Malfunctioning equipment led to baghouse dust hopper plugging, and storage of the stagnant material at flue gas temperatures resulted in self-heating and ignition of the AC in the ash. In the hoppers that worked properly, no such problems were reported. Economics of mercury control at Big Brown were estimated for as-tested scenarios and scenarios incorporating changes to allow sustainable operation. This project was funded under the U.S. Department of Energy National Energy Technology Laboratory project entitled 'Large-Scale Mercury Control Technology Field Testing Program--Phase II'.

John Pavlish; Jeffrey Thompson; Christopher Martin; Mark Musich; Lucinda Hamre

2009-01-07T23:59:59.000Z

Note: This page contains sample records for the topic "vessel ron brown" 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

Effect of prepartum protein restriction on brown adipose tissue thermogenic activity in newborn calves  

E-Print Network (OSTI)

Brown adipose tissue (BAT) thermogenesis was evaluated in Wagyu-sired calves from Angus heifers fed isocaloric diets with adequate (PA, 10%) or restricted (PR, 5.8%) dietary protein levels during the last 150 d of gestation. At 6 h of age, calves were placed in a warm-water indirect-calorimetry system to measure norepinephrine (NE) induced BAT thermogenisis. Calves were infused with NE (20 []g NE/kg BW/min for 10 min), and blood samples collected at birth, and at-5, 0, 20, 40, 60, 80, and 120 min after NE infusion for analysis of NEFA, glucose, urea nitrogen (BUN), cortisol, triiodothyronine (T3), and thyroxine (T4). Brown adipose tissue samples were collected at 12 h of age and analyzed for DNA, protein and lipid content. Protein-adequate heifers were 33% heavier (P < .001) and had higher (P < .001) body condition scores (5.9 vs 2.9) than PR heifers at calving. Protein-adequate heifers had higher (P < .05) BUN concentrations 1, 2, and 3 wks prepartum than PR heifers. Heifer cortisol concentrations were not affected by prepartum protein restriction; however, PR heifers had lower T3 concentrations three weeks prepartum and lower T4 concentrations at parturition than PA heifers. Prepartum protein restriction did not reduce calf birth weights (26.4 kg) or thermoneutral metabolic rates (TMR) which averaged 33.3 cal/kg/min. In support of these findings, visceral organ mass was similar for PA and PR calves. Peak metabolic rates (PMR), which averaged 66.2 cal/kg/min, as well as BAT weight and composition were not affected by prepartum protein restriction. Birth BUN levels were 1-fold higher (P <.01) in PA calves than PR calves. Plasma NEFA concentrations were 19% higher (P <.05) in PR calves 20 min after NE infusion. Average T3 concentrations at 6 h of age were 5 1 % higher (P < . 0 1) in PR compared to PA calves although T4 concentrations were similar. These results indicate that prepartum protein restriction did not affect thermoneutral or BAT thermogenesis in newborn calves. The relatively small birth weights of the calves used in this study may have accounted for the lack of a treatment affect on thermoneutral metabolism.

Taylor, Travis Lyn

1997-01-01T23:59:59.000Z

342

Nonnative Lizards Nile Monitor 4 to 6 ft. Brown/yellow body bands; forked black/blue tongue; long sharp claws  

E-Print Network (OSTI)

Constrictor 6 to 9 ft. Tan oval spots; reddish-brown tail Green Anaconda 13 to 15 ft. Green body; large, round, dark spots; eye stripes Yellow Anaconda 6 to 9 ft. Yellow body; large, dark spots; five dark stripes

Mazzotti, Frank

343

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

344

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

345

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

346

New brown dwarfs in Upper Sco using UKIDSS Galactic Cluster Survey science verification data  

E-Print Network (OSTI)

We present first results from a deep (J = 18.7), wide-field (6.5 square degrees) infrared (ZYJHK) survey in the Upper Sco association conducted within the science verification phase of the UKIRT Infrared Deep Sky Survey Galactic Cluster Survey (GCS). Cluster members define a sequence well separated from field stars in the (Z-J,Z) colour-magnitude diagram. We have selected a total of 164 candidates with J = 10.5-18.7 mag from the (Z-J,Z) and (Y-J,Y) diagrams. We further investigated the location of those candidates in the other colour-magnitude and colour-colour diagrams to weed out contaminants. The cross-correlation of the GCS catalogue with the 2MASS database confirms the membership of 116 photometric candidates down to 20 Jupiter masses as they lie within a 2 sigma circle centred on the association mean motion. The final list of cluster members contains 129 sources with masses between 0.3 and 0.007 Msun. We extracted a dozen new low-mass brown dwarfs below 20 Mjup, the limit of previous surveys in the region. Finally, we have derived the mass function in Upper Sco over the 0.3-0.01 Msun mass range, best fit by a single segment with a slope of index alpha = 0.6+/-0.1, in agreement with previous determination in open clusters.

N. Lodieu; N. C. Hambly; R. F. Jameson; S. T. Hodgkin; G. Carraro; T. R. Kendall

2006-10-05T23:59:59.000Z

347

The biological control of brown soft scale Coccus hesperidum L. (Homoptera: Coccidae) in interior plantscapes  

E-Print Network (OSTI)

Interior plantscape pests consist predominantly of a wide variety of species of Homoptera. Soft scale insects appear to account for one quarter to one third of all significant pest problems associated with interior plantscape environments. Brown soft scale, Coccus hesperidum L., is arguably the most common soft scale pest in these locations. The objective of this research project was to assess the potential for reducing C. hesperidum to non-pest status in interior plantscapes using the techniques of classical biological control. Improved methods for rearing C. hesperidum in the laboratory were developed using All Season" squash and Basalla alba, the Malabar spinach. More than a dozen species of encyrfid and aphelinid parasite species were reared from samples taken from naturally occurring California and Texas populations of C. hesperidum. Emerging parasites were screened for successful reproduction on Texas populations of C. hesperidum, and cultures of the most promising species were initiated. Metaphycus alberti (Howard) was chosen for further experimentation because it was found in low density populations in California, its eggs were not encapsulated by the Texas populations of C. hesperidum, it developed reliably, it was gregarious, it had a simple lifecycle, it had a short developmental time, and it was not present in Texas. Controlled comparison field trials using closed, open, and no sleeve treatments were conducted to measure the effect of release of M. alberti on the population dynamics of C.

Stauffer, Robert Stevens

1996-01-01T23:59:59.000Z

348

Analysis of superconducting magnetic energy storage applications at a proposed wind farm site near Browning, Montana  

DOE Green Energy (OSTI)

A computer program was developed to analyze the viability of integrating superconducting magnetic energy storage (SMES) with proposed wind farm scenarios at a site near Browning, Montana. The program simulated an hour-by-hour account of the charge/discharge history of a SMES unit for a representative wind-speed year. Effects of power output, storage capacity, and power conditioning capability on SMES performance characteristics were analyzed on a seasonal, diurnal, and hourly basis. The SMES unit was assumed to be charged during periods when power output of the wind resource exceeded its average value. Energy was discharged from the SMES unit into the grid during periods of low wind speed to compensate for below-average output of the wind resource. The option of using SMES to provide power continuity for a wind farm supplemented by combustion turbines was also investigated. Levelizing the annual output of large wind energy systems operating in the Blackfeet area of Montana was found to require a storage capacity too large to be economically viable. However, it appears that intermediate-sized SMES economically levelize the wind energy output on a seasonal basis.

Gaustad, K.L.; De Steese, J.G.

1993-07-01T23:59:59.000Z

349

Evaluation of Marine Brown Algae and Sponges from Brazil as Anticoagulant and Antiplatelet Products  

E-Print Network (OSTI)

Abstract: The ischemic disorders, in which platelet aggregation and blood coagulation are involved, represent a major cause of disability and death worldwide. The antithrombotic therapy has unsatisfactory performance and may produce side effects. So, there is a need to seek molecules with antithrombotic properties. Marine organisms produce substances with different well defined ecological functions. Moreover, some of these molecules also exhibit pharmacological properties such as antiviral, anticancer, antiophidic and anticoagulant properties. The aim of this study was to evaluate, through in vitro tests, the effect of two extracts of brown algae and ten marine sponges from Brazil on platelet aggregation and blood coagulation. Our results revealed that most of the extracts were capable of inhibiting platelet aggregation and clotting measured by plasma recalcification tests, prothrombin time, activated partial thromboplastin time, and fibrinogenolytic activity. On the other hand, five of ten species of sponges induced platelet aggregation. Thus, the marine organisms studied here may have molecules with antithrombotic properties, presenting biotechnological potential to antithrombotic therapy. Further chemical investigation shouldMar. Drugs 2011, 9 1347

Laura De Andrade Moura; Fredy Ortiz-ramirez; Diana Negrao Cavalcanti; Suzi Meneses Ribeiro; Guilherme Muricy; Valeria Laneuville Teixeira; Andre Lopes Fuly

2011-01-01T23:59:59.000Z

350

Ionization in Atmospheres of Brown Dwarfs and Extrasolar Planets V: Alfv\\'{e}n Ionization  

E-Print Network (OSTI)

Observations of continuous radio and sporadic X-ray emission from low-mass objects suggest they harbour localized plasmas in their atmospheric environments. For low-mass objects, the degree of thermal ionization is insufficient to qualify the ionized component as a plasma, posing the question: what ionization processes can efficiently produce the required plasma that is the source of the radiation? We propose Alfv\\'{e}n ionization as a mechanism for producing localized pockets of ionized gas in the atmosphere, having sufficient degrees of ionization ($\\geq10^{-7}$) that they constitute plasmas. We outline the criteria required for Alfv\\'{e}n ionization and demonstrate it's applicability in the atmospheres of low-mass objects such as giant gas planets, brown dwarfs and M-dwarfs for both solar and sub-solar metallicities. We find that Alfv\\'{e}n ionization is most efficient at mid to low atmospheric pressures where a seed plasma is easier to magnetize and the pressure gradients needed to drive the required neut...

Stark, Craig R; Diver, Declan A; Rimmer, Paul B

2013-01-01T23:59:59.000Z

351

Small hydrocarbon molecules in cloud-forming Brown Dwarf and giant gas planet atmospheres  

E-Print Network (OSTI)

We study the abundances of complex carbon-bearing molecules in the oxygen-rich dust- forming atmospheres of Brown Dwarfs and giant gas planets. The inner atmospheric re- gions that form the inner boundary for thermochemical gas-phase models are investigated. Results from Drift-phoenix atmosphere simulations, which include the feedback of phase- non-equilibrium dust cloud formation on the atmospheric structure and the gas-phase abun- dances, are utilised. The resulting element depletion leads to a shift in the carbon-to-oxygen ratio such that several hydrocarbon molecules and cyanopolycyanopolyynene molecules can be present. An increase in surface gravity and/or a decrease in metallicity support the increase in the partial pressures of these species. CO, CO2, CH4, and HCN contain the largest fraction of carbon. In the upper atmosphere of low-metallicity objects, more carbon is contained in C4H than in CO, and also CH3 and C2H2 play an increasingly important role as carbon-sink. We determine chemical relaxation...

Bilger, Camille; Helling, Christiane

2013-01-01T23:59:59.000Z

352

NEW BROWN DWARF COMPANIONS TO YOUNG STARS IN SCORPIUS-CENTAURUS  

Science Conference Proceedings (OSTI)

We present the discoveries of three faint companions to young stars in the Scorpius-Centaurus region, imaged with the NICI instrument on Gemini South. We have confirmed all three companions through common proper motion tests. Follow-up spectroscopy has confirmed two of them, HIP 65423 B and HIP 65517 B, to be brown dwarfs, while the third, HIP 72099 B, is more likely a very low mass star just above the hydrogen burning limit. The detection of wide companions in the mass range of {approx}40-100 M{sub jup} complements previous work in the same region, reporting detections of similarly wide companions with lower masses, in the range of {approx}10-30 M{sub jup}. Such low masses near the deuterium burning limit have raised the question of whether those objects formed like planets or stars. The existence of intermediate objects as reported here could represent a bridge between lower-mass companions and stellar companions, but in any case demonstrate that mass alone may not provide a clear-cut distinction for the formation of low-mass companions to stars.

Janson, Markus [Department of Astrophysical Sciences, Princeton University, Princeton, NJ (United States); Jayawardhana, Ray; Bonavita, Mariangela [Department of Astronomy and Astrophysics, University of Toronto, Toronto, ON (Canada); Girard, Julien H. [European Southern Observatory, Santiago (Chile); Lafreniere, David [Department of Physics, University of Montreal, Montreal, QC (Canada); Gizis, John [Department of Physics and Astronomy, University of Delaware, Newark, DE (United States); Brandeker, Alexis, E-mail: janson@astro.princeton.edu [Department of Astronomy, Stockholm University, Stockholm (Sweden)

2012-10-10T23:59:59.000Z

353

Spitzer IRAC mid-infrared photometry of 500-750 brown dwarf  

SciTech Connect

Mid-infrared data, including Spitzer warm-IRAC [3.6] and [4.5] photometry, is critical for understanding the cold population of brown dwarfs now being found, objects which have more in common with planets than stars. As effective temperature (T{sub eff}) drops from 800K to 400K, the fraction of flux emitted beyond 3 {mu}m increases rapidly, from about 40% to > 75%. This rapid increase makes a color like H-[4.5] a very sensitive temperature indicator, and it can be combined with a gravity- and metallicity-sensitive color like H-K to constrain all three of these fundamental properties, which in turn gives us mass and age for these slowly cooling objects. Determination of mid-infrared color trends also allows better exploitation of the WISE mission by the community. We use new Spitzer Cycle 6 IRAC photometry, together with published data, to present trends of color with type for L0 to T10 dwarfs. We also use the atmospheric and evolutionary models of Saumon and Marley to investigate the masses and ages of 13 very late-type T dwarfs, which have H-[4.5] > 3.2 and T{sub eff} {approx} 500K to 750K.

Saumon, Didier [Los Alamos National Laboratory; Leggett, Sandy K [GEMINI OBSERVATORY; Albert, Loic [CFH TELESCOPE; Artigau, Etienne [U OF MONTREAL; Burningham, Ben [HERTFORDSHIRE U; Delfosse, Xavier [OBS. GRENOBLE; Delorme, Philippe [ST. ANDREWS U.; Forveille, Thierry [OBS. GRENOBLE; Lucas, Philip W [HERTFORDSHIRE U; Marley, Mark S [NASA AMES; Pinfield, David J [HERTFORDSHIRE U.; Reyle, Celine [OBS. BESANCON; Smart, Richard L [OSS. ASTRON, TORINO; Warren, Stephen J [IMPERIAL COLLEGE LONDON

2010-10-26T23:59:59.000Z

354

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

355

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

356

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

357

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

358

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

359

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

360

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

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361

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

362

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

363

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

364

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

365

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

366

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

367

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

368

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

369

Supplemental Power for the town of Browning Waste-Water Treatment Facility  

Science Conference Proceedings (OSTI)

This final report is issued for the "Supplemental power for the Town of Browning waste-water treatment facility" under the Field Verification Program for Small Wind Turbines Grant. The grant application was submitted on April 16, 1999 wherein the full description of this project is outlined. The project was initially designed to test the Bergy small wind turbines, 10 kW, applicability to residential and commercial applications. The objectives of the project were the following: 1. To verify the performance of the BWC Excel-S/E model wind turbine in an operational application in the fierce winds and severe weather conditions of the Class V winds of the Blackfeet Indian Reservation of Northern Montana. 2. To open up the Blackfeet reservation and northern Montana, to government sponsored, regionally distributed wind generation programs. 3. To examine the natural partnership of wind/electric with water pumping and water purification applications whose requirements parallel the variably available nature of energy produced by wind. 4. To provide data and hands-on experience to citizens, scientists, political leaders, utility operators and Tribal planners with regard to the potential uses of small-capacity, distributed-array wind turbines on the Blackfeet Reservation and in other areas of northern Montana. This project has not been without a few, which were worked out and at the time of this report continue to be worked on with the installation of two new Trace Technologies invertors and a rebuilt one with new technology inside. For the most part when the system has worked it produced power that was used within the wastewater system as was the purpose of this project.

William Morris; Dennis Fitzpatrick

2005-12-20T23:59:59.000Z

370

Late Paleocene paleoenvironmental gradients in Wilcox Group strata, Big Brown Mine, Texas  

E-Print Network (OSTI)

The Wilcox Group in Texas has been recognized as an important oil and gas reservoir for much of this century, and for the last 30 years has been commercially mined for its extensive shallow lignitic coals. More recently, exploration for coalbed methane in the Gulf Coast has focused in this area. For this new play to become successful, more information on the stratigraphy and depositional environments of the Wilcox Group is needed. The Wilcox Group in the Gulf Coast has been interpreted as primarily fluvial-deltaic in origin; however, since the 1980s, much evidence for tidal control on the deposition of the upper Wilcox (Calvert Bluff Formation) has been compiled. New data from the examination of sediments and fossils contained in the upper Wilcox Calvert Bluff Formation in and near the Texas Utilities' Big Brown Mine confirm that significant marine influence was present at the time of deposition. Most fine-grained sediments contain flaser, rippled, and laminated bedding, and palynological assemblages from non-coal sediments commonly contain Paleocene-Eocene marine dinoflagellates as well as brackish-water indicator palynomorphs. Sand deposits also contain marine dinoflagellates and are in gradational contact with underlying fine-grained sediments. Channel-fill deposits present in the mine area are similar to known examples of tidal flat and estuarine channels. These features indicate that brackish to marine conditions existed during much of the deposition of the upper Wilcox Group in northeastern Texas. The presence of non-fluvial-deltaic deposition in the upper Wilcox Group has implications for the location and extent of the coals, which will aid in the location of coalbed methane reservoirs.

Klein, Jennifer Marie

2000-01-01T23:59:59.000Z

371

Black/brown cooperation and conflict in the education policymaking process  

E-Print Network (OSTI)

The way race works to shape politics is changing as demographic patterns alter the traditional dynamic of race relations throughout the United States. One pattern is the increased tendency of African-Americans and Latinos to reside in the same locality. While popular opinion suggests that such contexts should result in the formation of â??rainbow coalitions,â? several scholars have found evidence that inter-minority relations are characterized by high levels of political competition. One of the policy areas in which competition has been observed most often is education. This dissertation examines the conditions under which African-American/Latino relations are likely to be characterized by cooperation or conflict within the education policymaking process. It utilizes a survey of 1800 school districts, containing 96% of all urban districts in the United States. The results produced by this study, therefore, are applicable to nearly the entire universe of urban educational systems. Another unique aspect of this project is that, rather than focusing on relations at one stage of the policy process, it attempts to trace this dynamic through each stage. Thus, the dissertation begins with a look at the circumstances under which Black/Brown electoral coalitions will form in school board elections. The findings suggest that coalition formation is contingent upon structural contexts, specifically the presence of partisan elections, and upon the citizenship status of the Latino population within a district. The dissertation goes on to trace the cooperative and competitive forces that affect the hiring of African- American and Latino administrators and teachers. Lastly, I use theories of bureaucratic politics and racial context to study the quality of education received by minority students. I find that, controlling for other factors, more diverse school districts have more equitable educational policies. I also find evidence to support the contention that more diverse teaching faculties tend to result in beneficial outcomes for both African- American and Latino students.

Rocha, Rene Rolando

2006-08-01T23:59:59.000Z

372

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

373

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

374

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

375

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

376

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

377

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

378

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

379

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

380

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

Note: This page contains sample records for the topic "vessel ron brown" 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

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

382

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

383

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

384

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

385

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

386

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

387

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

388

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

389

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

390

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

391

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

392

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

393

Fuel Reliability Program: Hot Cell Investigation and Assessment of GE14 Failures in Browns Ferry Unit 3  

Science Conference Proceedings (OSTI)

Browns Ferry 3 Cycle 12 began operation in April 2004, but on July 19, 2004, an off-gas radiation monitor increase and subsequent grab sample confirmed the presence of failures in two second-cycle GE14 (10 x 10) bundles. The failures coincided with power changes during a control rod sequence exchange; however, local rod power and the change in rod power levels were well below design limits and operating experience from another GE14 failure in Hatch Unit 1 (described in Electric Power Research Institute [...

2010-09-01T23:59:59.000Z

394

Fuel Reliability Program: Post-Irradiation Examination and Performance Assessment of ATRIUM-10 BWR Fuel from Browns Ferry-3 Reactor  

Science Conference Proceedings (OSTI)

ATRIUM-10 design (10x10 lattice) fuel was irradiated for one 24-month period during Cycle 12 to 25 MWd/kgU rod-average exposure at Tennessee Valley Authority's Browns Ferry Unit 3 reactor. The project goal was to characterize the behavior of modern boiling water reactor (BWR) fuel at low exposures to assess early-life performance in a well-documented reactor environment. This report includes results from hot cell post-irradiation examinations. In a future Electric Power Research Institute (EPRI) report, ...

2011-06-09T23:59:59.000Z

395

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

396

2MASS J035523.37+113343.7: A YOUNG, DUSTY, NEARBY, ISOLATED BROWN DWARF RESEMBLING A GIANT EXOPLANET  

SciTech Connect

We present parallax and proper motion measurements, near-infrared spectra, and Wide-field Infrared Survey Explorer photometry for the low surface gravity L5{gamma} dwarf 2MASS J035523.37+113343.7 (2M0355). We use these data to evaluate photometric, spectral, and kinematic signatures of youth as 2M0355 is the reddest isolated L dwarf yet classified. We confirm its low-gravity spectral morphology and find a strong resemblance to the sharp triangular shaped H-band spectrum of the {approx}10 Myr planetary-mass object 2M1207b. We find that 2M0355 is underluminous compared to a normal field L5 dwarf in the optical and Mauna Kea Observatory J, H, and K bands and transitions to being overluminous from 3 to 12 {mu}m, indicating that enhanced photospheric dust shifts flux to longer wavelengths for young, low-gravity objects, creating a red spectral energy distribution. Investigating the near-infrared color-magnitude diagram for brown dwarfs confirms that 2M0355 is redder and underluminous compared to the known brown dwarf population, similar to the peculiarities of directly imaged exoplanets 2M1207b and HR8799bcd. We calculate UVW space velocities and find that the motion of 2M0355 is consistent with young disk objects (<2-3 Gyr) and it shows a high likelihood of membership in the AB Doradus association.

Faherty, Jacqueline K. [Department of Astronomy, Universidad de Chile Cerro Calan, Las Condes (Chile); Rice, Emily L.; Cruz, Kelle L.; Nunez, Alejandro [Department of Astrophysics , American Museum of Natural History, Central Park West at 79th Street, New York, NY 10034 (United States); Mamajek, Eric E., E-mail: jfaherty17@gmail.com, E-mail: jfaherty@amnh.org [Cerro Tololo Inter-American Observatory, Casilla 603, La Serena (Chile)

2013-01-01T23:59:59.000Z

397

A Cautionary Tale: MARVELS Brown Dwarf Candidate Reveals Itself To Be A Very Long Period, Highly Eccentric Spectroscopic Stellar Binary  

E-Print Network (OSTI)

We report the discovery of a highly eccentric, double-lined spectroscopic binary star system (TYC 3010-1494-1), comprising two solar-type stars that we had initially identified as a single star with a brown dwarf companion. At the moderate resolving power of the MARVELS spectrograph and the spectrographs used for subsequent radial-velocity (RV) measurements (R ~ <30,000), this particular stellar binary mimics a single-lined binary with an RV signal that would be induced by a brown dwarf companion (Msin(i)~50 M_Jup) to a solar-type primary. At least three properties of this system allow it to masquerade as a single star with a very low-mass companion: its large eccentricity (e~0.8), its relatively long period (P~238 days), and the approximately perpendicular orientation of the semi-major axis with respect to the line of sight (omega~189 degrees). As a result of these properties, for ~95% of the orbit the two sets of stellar spectral lines are completely blended, and the RV measurements based on centroiding ...

Mack, Claude E; Deshpande, Rohit; Wisniewski, John P; Stassun, Keivan G; Gaudi, B Scott; Fleming, Scott W; Mahadevan, Suvrath; De Lee, Nathan; Eastman, Jason; Ghezzi, Luan; Hernandez, Jonay I Gonzalez; Femenia, Bruno; Ferreira, Leticia; de Mello, Gustavo Porto; Crepp, Justin R; Sanchez, Daniel Mata; Agol, Eric; Beatty, Thomas G; Bizyaev, Dmitry; Brewington, Howard; Cargile, Phillip A; da Costa, Luiz N; Esposito, Massimiliano; Ebelke, Garret; Hebb, Leslie; Jiang, Peng; Kane, Stephen R; Lee, Brian; Maia, Marcio A G; Malanushenko, Elena; Malanushenko, Victor; Oravetz, Daniel; Paegert, Martin; Pan, Kaike; Prieto, Carlos Allende; Peper, Joshua; Rebolo, Rafael; Roy, Arpita; Santiago, Basilio X; Schneider, Donald P; Simmons, Audrey; Siverd, Robert J; Snedden, Stephanie; Tofflemire, Benjamin M

2013-01-01T23:59:59.000Z

398

MARVELS-1b: A Short-Period, Brown Dwarf Desert Candidate from the SDSS-III MARVELS Planet Search  

E-Print Network (OSTI)

We present a new short-period brown dwarf candidate around the star TYC 1240-00945-1. This candidate was discovered in the first year of the Multi-object APO Radial Velocity Exoplanets Large-area Survey (MARVELS), which is part of the third phase of the Sloan Digital Sky Survey (SDSS-III), and we designate the brown dwarf as MARVELS-1b. MARVELS uses the technique of dispersed fixed-delay interferometery to simultaneously obtain radial velocity measurements for 60 objects per field using a single, custom-built instrument that is fiber fed from the SDSS 2.5-m telescope. From our 20 radial velocity measurements spread over a ~370 d time baseline, we derive a Keplerian orbital fit with semi-amplitude K=2.533+/-0.025 km/s, period P=5.8953+/-0.0004 d, and eccentricity consistent with circular. Independent follow-up radial velocity data confirm the orbit. Adopting a mass of 1.37+/-0.11 M_Sun for the slightly evolved F9 host star, we infer that the companion has a minimum mass of 28.0+/-1.5 M_Jup, a semimajor axis 0....

Lee, Brian L; Fleming, Scott W; Stassun, Keivan G; Gaudi, B Scott; Barnes, Rory; Mahadevan, Suvrath; Eastman, Jason D; Wright, Jason; Siverd, Robert J; Gary, Bruce; Ghezzi, Luan; Laws, Chris; Wisniewski, John P; de Mello, G F Porto; Ogando, Ricardo L C; Maia, Marcio A G; da Costa, Luiz Nicolaci; Sivarani, Thirupathi; Pepper, Joshua; Nguyen, Duy Cuong; Hebb, Leslie; De Lee, Nathan; Wang, Ji; Wan, Xiaoke; Zhao, Bo; Chang, Liang; Groot, John; Varosi, Frank; Hearty, Fred; Hanna, Kevin; van Eyken, J C; Kane, Stephen R; Agol, Eric; Bizyaev, Dmitry; Bochanski, John J; Brewington, Howard; Chen, Zhiping; Costello, Erin; Dou, Liming; Eisenstein, Daniel J; Fletcher, Adam; Ford, Eric B; Guo, Pengcheng; Holtzman, Jon A; Jiang, Peng; Leger, R French; Liu, Jian; Long, Daniel C; Malanushenko, Elena; Malanushenko, Viktor; Malik, Mohit; Oravetz, Daniel; Pan, Kaike; Rohan, Pais; Schneider, Donald P; Shelden, Alaina; Snedden, Stephanie A; Simmons, Audrey; Weaver, B A; Weinberg, David H; Xie, Ji-Wei

2010-01-01T23:59:59.000Z

399

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

400

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

Note: This page contains sample records for the topic "vessel ron brown" 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

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

402

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

403

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

404

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

405

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

406

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

407

What follows is a reproduced portion of a Marshall Space Flight Center phone book dated September 4, 1960, four  

E-Print Network (OSTI)

Bergman `13P Nancy M. Berman `97H ++ John A. Berseth, Jr. `67 `68G Winifred R. Beverly-Gerhardt `96 Ron Y. Bott `54 `F/S ++ Albert J. Bova, Jr. `76 Mark C. Bovenizer `93 Meghan K. Bowen `11 Michael L. Bowers, Jr. `66 Linda K. Brown `13P Robert L. Brown III `78 ++ Steven M. Brown `13P Peter A. Buckley `92

408

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

409

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

410

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

411

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

412

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

413

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

414

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

415

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

416

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

417

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

418

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

419

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

420

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

Note: This page contains sample records for the topic "vessel ron brown" 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

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)

422

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

423

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

424

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

425

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

426

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

427

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

428

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

429

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

430

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

431

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

432

BWRVIP-86, Revision 1-A: BWR Vessel and Internals Project, Updated BWR Integrated Surveillance Program (ISP) Implementation Plan  

Science Conference Proceedings (OSTI)

This report describes the boiling water reactor (BWR) Integrated Surveillance Program (ISP). Based on recommendations from BWR Vessel and Internals Project (BWRVIP) utilities, it was concluded that combining all separate BWR surveillance programs into a single integrated program would be beneficial. In the integrated program, representative materials chosen for a specific reactor pressure vessel (RPV) can be materials from another plant surveillance program or other source that better represents the ...

2012-10-01T23:59:59.000Z

433

Program on Technology Innovation: Weld Metals and Welding Processes for Fabrication of Advanced Light Water Reactor Pressure Vessels  

Science Conference Proceedings (OSTI)

Light water reactors have traditionally been constructed using roll-formed plates for the reactor pressure vessel (RPV) shells, which were assembled via horizontal and vertical seam welds. Weld filler metals often contained significant quantities of copper, other residual elements such as vanadium, and nonmetallic elements such as phosphorous and sulfur. Low-alloy steel weld filler metals of this chemical composition contributed to the degree of neutron radiation-induced embrittlement of vessel ...

2013-06-26T23:59:59.000Z

434

BWRVIP-99-A: BWR Vessel and Internals Project, Crack Growth Rates in Irradiated Stainless Steels in BWR Internal Components  

Science Conference Proceedings (OSTI)

The BWR Vessel and Internals Project (BWRVIP) has developed methodologies to evaluate crack growth in internal components of stainless steel and nickel-base alloys in the BWR vessel. One BWRVIP reportBWRVIP-14developed an approach to evaluate crack growth by intergranular stress corrosion cracking in austenitic stainless steel core shrouds exposed to a limited amount of neutron irradiation. Subsequently another reportBWRVIP-99was prepared to provide a crack growth methodology applicable to irradiated...

2008-11-24T23:59:59.000Z

435

BWRVIP-41, Revision 3: BWR Vessel and Internals Project, BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines  

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 provides information on potential failure locations in BWR/3-6 jet pump components and recommends an inspection program designed to ensure that the integrity of all jet pump safety functions is maintained. EPRI published a previous version of this report as BWRVIP-41, Revision 2 (EPRI 1019570). This report (EPRI Rep...

2010-09-10T23:59:59.000Z

436

BWRVIP-18, Revision 1-A: BWR Vessel and Internals Project, BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines  

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 BWRVIP report contains generic guidelines that describe locations on the core spray piping and spargers for which inspection is needed, categories of plants for which inspection needs would differ, extent of inspection and reinspection for each location, and flaw evaluation procedures to determine ...

2012-04-09T23:59:59.000Z

437

Biomass-Derived Hydrogen from a Thermally Ballasted Gasifier Robert C. Brown, Glenn Norton, Andy Suby, Jerod Smeenk, Keith Cummer, and Josh Nunez  

E-Print Network (OSTI)

Biomass-Derived Hydrogen from a Thermally Ballasted Gasifier Robert C. Brown, Glenn Norton, Andy fuel cells. We have developed a thermally ballasted gasifier that uses a single reactor for both compared to conventional gasifiers. The carbon monoxide, along with steam used to fluidize the reactor, can

438

High Pressure Coolant Injection (HPCI) System Risk-Based Inspection Guide for Browns Ferry Nuclear Power Station  

Science Conference Proceedings (OSTI)

The High Pressure Coolant Injection (HPCI) system has been examined from a risk perspective. A System Risk-Based Inspection Guide (S-RIG) has been developed as an aid to HPCI system inspections at the Browns Ferry Nuclear Power Plant, Units 1, 2 and 3. The role of. the HPCI system in mitigating accidents is discussed in this S-RIG, along with insights on identified risk-based failure modes which could prevent proper operation of the system. The S-RIG provides a review of industry-wide operating experience, including plant-specific illustrative examples to augment the PRA and operational considerations in identifying a catalogue of basic PRA failure modes for the HPCI system. It is designed to be used as a reference for routine inspections, self-initiated safety system functional inspections (SSFIs), and the evaluation of risk significance of component failures at the nuclear power plant.

Wong, S.; DiBiasio, A.; Gunther, W. [Brookhaven National Lab., Upton, NY (United States)

1993-09-01T23:59:59.000Z

439

Manufacturing Cost Analysis of Novel Steel/Concrete Composite Vessel for Stationary Storage of High-Pressure Hydrogen  

SciTech Connect

A novel, low-cost, high-pressure, steel/concrete composite vessel (SCCV) technology for stationary storage of compressed gaseous hydrogen (CGH2) is currently under development at Oak Ridge National Laboratory (ORNL) sponsored by DOE s Fuel Cell Technologies (FCT) Program. The SCCV technology uses commodity materials including structural steels and concretes for achieving cost, durability and safety requirements. In particular, the hydrogen embrittlement of high-strength low-alloy steels, a major safety and durability issue for current industry-standard pressure vessel technology, is mitigated through the use of a unique layered steel shell structure. This report presents the cost analysis results of the novel SCCV technology. A high-fidelity cost analysis tool is developed, based on a detailed, bottom-up approach which takes into account the material and labor costs involved in each of the vessel manufacturing steps. A thorough cost study is performed to understand the SCCV cost as a function of the key vessel design parameters, including hydrogen pressure, vessel dimensions, and load-carrying ratio. The major conclusions include: The SCCV technology can meet the technical/cost targets set forth by DOE s FCT Program for FY2015 and FY2020 for all three pressure levels (i.e., 160, 430 and 860 bar) relevant to the hydrogen production and delivery infrastructure. Further vessel cost reduction can benefit from the development of advanced vessel fabrication technologies such as the highly automated friction stir welding (FSW). The ORNL-patented multi-layer, multi-pass FSW can not only reduce the amount of labor needed for assembling and welding the layered steel vessel, but also make it possible to use even higher strength steels for further cost reductions and improvement of vessel structural integrity. It is noted the cost analysis results demonstrate the significant cost advantage attainable by the SCCV technology for different pressure levels when compared to the industry-standard pressure vessel technology. The real-world performance data of SCCV under actual operating conditions is imperative for this new technology to be adopted by the hydrogen industry for stationary storage of CGH2. Therefore, the key technology development effort in FY13 and subsequent years will be focused on the fabrication and testing of SCCV mock-ups. The static loading and fatigue data will be generated in rigorous testing of these mock-ups. Successful tests are crucial to enabling the near-term impact of the developed storage technology on the CGH2 storage market, a critical component of the hydrogen production and delivery infrastructure. In particular, the SCCV has high potential for widespread deployment in hydrogen fueling stations.

Feng, Zhili [ORNL; Zhang, Wei [ORNL; Wang, Jy-An John [ORNL; Ren, Fei [ORNL

2012-09-01T23:59:59.000Z

440

Detection and characterization of flaws in segments of light water reactor pressure vessels  

Science Conference Proceedings (OSTI)

Studies have been conducted to determine 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 vessil 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. Both objectives were successfully completed. One significant indication was detected in a Hope Creek seam weld by ultrasonic techniques and characterized by further analyses terminating with destructive correlation. This indication (with a through-wall dimension of approx.6 mm (approx.0.24 in.)) was detected in only 3 m (10 ft) of weldment and offers extremely limited data when compared to the extent of welding even in a single pressure vessel. However, the detection and confirmation of the flaw in the arbitrarily selected sections implies the Marshall report estimates (and others) are nonconservative for such small flaws. No significant indications were detected in the Pilgrim material by ultrasonic techniques. Unfortunately, the Pilgrim segments contained relatively little weldment; thus, we limited our ultrasonic examinations to the cladding and subcladding regions. Fluorescent liquid penetrant inspection of the cladding surfaces for both LWR segments detected no significant indications (i.e., for a total of approximately 6.8 m/sup 2/ (72 ft/sup 2/) of cladding surface).

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

1987-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "vessel ron brown" 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

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

442

Dual shell reactor vessel: A pressure-balanced system for high pressure and temperature reactions  

Science Conference Proceedings (OSTI)

The main purpose of this work was to demonstrate the Dual Shell Pressure Balanced Vessel (DSPBV) as a safe and economical reactor for the hydrothermal water oxidation of hazardous wastes. Experimental tests proved that the pressure balancing piston and the leak detection concept designed for this project will work. The DSPBV was sized to process 10 gal/hr of hazardous waste at up to 399{degree}C (750{degree}F) and 5000 psia (34.5 MPa) with a residence time of 10 min. The first prototype reactor is a certified ASME pressure vessel. It was purchased by Innotek Corporation (licensee) and shipped to Pacific Northwest Laboratory for testing. Supporting equipment and instrumentation were, to a large extent, transported here from Battelle Columbus Division. A special air feed system and liquid pump were purchased to complete the package. The entire integrated demonstration system was assembled at PNL. During the activities conducted for this report, the leak detector design was tested on bench top equipment. Response to low levels of water in oil was considered adequate to ensure safety of the pressure vessel. Shakedown tests with water only were completed to prove the system could operate at 350{degree}C at pressures up to 3300 psia. Two demonstration tests with industrial waste streams were conducted, which showed that the DSPBV could be used for hydrothermal oxidation. In the first test with a metal plating waste, chemical oxygen demand, total organic carbon, and cyanide concentrations were reduced over 90%. In the second test with a munitions waste, the organics were reduced over 90% using H{sub 2}O{sub 2} as the oxidant.

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

1995-03-01T23:59:59.000Z

443

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

Science Conference Proceedings (OSTI)

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

Vinson, Dennis

2010-06-01T23:59:59.000Z

444

Ex-vessel core catcher materials interactions. Annual progress report. [LMFBR  

SciTech Connect

A twelve-month program to investigate ex-vessel core catcher materials interactions has been completed. The investigations, involving depleted uranium dioxide, magnesia brick, stainless steel, and low-carbon steel, were conducted in furnaces and associated facilities existing at Aerospace, which were modified to process molten and solidified radioactive samples. In addition to developing efficient methods for the melting, pouring, and sustained heating of UO/sub 2/, extensive sample characterizations and microanalyses were performed. Theoretical analyses were also made in data interpretation for the purpose of understanding the interaction kinetics.

Swanson, D.G.; Zehms, E.H.; Ang, C.Y.; McClelland, J.D.; Meyer, R.A.; vanPaassen, H.L.L.

1976-10-30T23:59:59.000Z

445

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

446

EXPERIMENTAL RESULTS FOR THE ISOTOPIC EXCHANGE OF A 1600 LITER TITANIUM HYDRIDE STORAGE VESSEL  

Science Conference Proceedings (OSTI)

Titanium is used as a low pressure tritium storage material. The absorption/desorption rates and temperature rise during air passivation have been reported previously for a 4400 gram prototype titanium hydride storage vessel (HSV). A desorption limit of roughly 0.25 Q/M was obtained when heating to 700 C which represents a significant residual tritium process vessel inventory. To prepare an HSV for disposal, batchwise isotopic exchange has been proposed to reduce the tritium content to acceptable levels. A prototype HSV was loaded with deuterium and exchanged with protium to determine the effectiveness of a batch-wise isotopic exchange process. A total of seven exchange cycles were performed. Gas samples were taken nominally at the beginning, middle, and end of each desorption cycle. Sample analyses showed the isotopic exchange process does not follow the standard dilution model commonly reported. Samples taken at the start of the desorption process were lower in deuterium (the gas to be removed) than those taken later in the desorption cycle. The results are explained in terms of incomplete mixing of the exchange gas in the low pressure hydride.

Klein, J.

2010-12-14T23:59:59.000Z

447

Calculation of Eddy Currents In the CTH Vacuum Vessel and Coil Frame  

SciTech Connect

Knowledge of eddy currents in the vacuum vessel walls and nearby conducting support structures can significantly contribute to the accuracy of Magnetohydrodynamics (MHD) equilibrium reconstruction in toroidal plasmas. Moreover, the magnetic fields produced by the eddy currents could generate error fields that may give rise to islands at rational surfaces or cause field lines to become chaotic. In the Compact Toroidal Hybrid (CTH) device (R0 = 0.75 m, a = 0.29 m, B ? 0.7 T), the primary driver of the eddy currents during the plasma discharge is the changing flux of the ohmic heating transformer. Electromagnetic simulations are used to calculate eddy current paths and profile in the vacuum vessel and in the coil frame pieces with known time dependent currents in the ohmic heating coils. MAXWELL and SPARK codes were used for the Electromagnetic modeling and simulation. MAXWELL code was used for detailed 3D finite-element analysis of the eddy currents in the structures. SPARK code was used to calculate the eddy currents in the structures as modeled with shell/surface elements, with each element representing a current loop. In both cases current filaments representing the eddy currents were prepared for input into VMEC code for MHD equilibrium reconstruction of the plasma discharge. __________________________________________________

A. Zolfaghari, A. Brooks, A. Michaels, J. Hanson, and G. Hartwell

2012-09-25T23:59:59.000Z

448

Consequence evaluation of radiation embrittlement of Trojan reactor pressure vessel supports  

SciTech Connect

This report describes a consequence evaluation to address safety concerns raised by the radiation embrittlement of the reactor pressure vessel (RPV) supports for the Trojan nuclear power plant. The study comprises a structural evaluation and an effects evaluation and assumes that all four reactor vessel supports have completely lost the load carrying capability. By demonstrating that the ASME code requirements governing Level D service limits are satisfied, the structural evaluation concludes that the Trojan reactor coolant loop (RCL) piping is capable of transferring loads to the steam generator (SG) supports and the reactor coolant pump (RCP) supports. A subsequent design margins to accommodate additional loads transferred to them through the RCL piping. The effects evaluation, employing a systems analysis approach, investigates initiating events and the reliability of the engineered safeguard systems as the RPV is subject to movements caused by the RPV support failure. The evaluation identifies a number of areas of additional safety concerns, but further investigation of the above safety concerns, however, concludes that a hypothetical failure of the Trojan RPV supports due to radiation embrittlement will not result in consequences of significant safety concerns.

Lu, S.C.; Sommer, S.C.; Johnson, G.L. (Lawrence Livermore National Lab., CA (USA)); Lambert, H.E. (FTA Associates, Oakland, CA (USA))

1990-10-01T23:59:59.000Z

449

Computation of initial stage of RBMK reactor fuel channel vessel rupture  

SciTech Connect

Objective of this work is estimation of temperature and time characteristics for rupture of the zirconium pipe which is the RBMK reactor fuel channel (FC) vessel under emergencies. As an emergency the zirconium pipe temperature rise process is considered which results in loss of pipe material strength properties and pipe rupture under the action of internal pressure P=80MPa. The work was carried out under Task Order 007 of University of California - VNIIEF Subcontract No. 0002P0004-95. The problem formulation is stated in Protocol (Task 3, Appendix 3) of the Russian-American Workshop which was held in December, 1994 in Los Alamos. Physical-mechanical and geometry characteristics of structure elements (FC vessel with graphite ring and graphite slug) are presented by NIKIET. The temperature mode of the structure is taken in conformity with the NIKIET data obtained with the RELAP5/MOD3 code. Numerical simulation of structure element behavior in an emergency is performed using the DRAKON program comlex oriented to solving strength problems for complex spatial structures at intense dynamic loading. The {open_quotes}DRAKON{close_quotes} program complex is described and compared with similar western codes in its capabilities.

Pevnitsky, A.V.; Solovyev, V.P.; Abakumov, A.I. [and others

1995-12-31T23:59:59.000Z

450

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

Science Conference Proceedings (OSTI)

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

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

1996-10-01T23:59:59.000Z

451

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

452

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

453

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

454

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

SciTech Connect

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

Not Available

1984-11-01T23:59:59.000Z

455

An Approach to Understanding Cohesive Slurry Settling, Mobilization, and Hydrogen Gas Retention in Pulsed Jet Mixed Vessels  

DOE Green Energy (OSTI)

The Hanford Waste Treatment and Immobilization Plant (WTP) is being designed and built to pretreat and vitrify a large portion of the waste in Hanfords 177 underground waste storage tanks. Numerous process vessels will hold waste at various stages in the WTP. Some of these vessels have mixing-system requirements to maintain conditions where the accumulation of hydrogen gas stays below acceptable limits, and the mixing within the vessels is sufficient to release hydrogen gas under normal conditions and during off-normal events. Some of the WTP process streams are slurries of solid particles suspended in Newtonian fluids that behave as non-Newtonian slurries, such as Bingham yield-stress fluids. When these slurries are contained in the process vessels, the particles can settle and become progressively more concentrated toward the bottom of the vessels, depending on the effectiveness of the mixing system. One limiting behavior is a settled layer beneath a particle-free liquid layer. The settled layer, or any region with sufficiently high solids concentration, will exhibit non-Newtonian rheology where it is possible for the settled slurry to behave as a soft solid with a yield stress. In this report, these slurries are described as settling cohesive slurries.

Gauglitz, Phillip A.; Wells, Beric E.; Fort, James A.; Meyer, Perry A.

2009-05-22T23:59:59.000Z

456

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

SciTech Connect

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

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

2012-08-29T23:59:59.000Z

457

Documentation of Probabilistic Fracture Mechanics Codes Used for Reactor Pressure Vessels Subjected to Pressurized Thermal Shock Loa ding: Parts 1 and 2  

Science Conference Proceedings (OSTI)

Pressurized thermal shock (PTS) can impact the safety and operability of PWR vessels with significant radiation embrittlement in the vessel walls. This report documents the results of probabilistic fracture mechanics analysis benchmark studies performed to validate the use of several codes for evaluating vessel PTS. Such benchmark studies provide the industry with a standard reference method for verifying probabilistic fracture mechanics codes used in PTS analyses.

1995-08-08T23:59:59.000Z

458

BWRVIP-27-A: BWR Vessel and Internals Project, BWR Standby Liquid Control System / Core Plate Delta-P Inspection and Flaw Evaluation Guidelines  

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 BWRVIP report defines inspection requirements for BWR standby liquid control (SLC) system piping from the vessel nozzle safe-end inward. A previous version of this report was published as BWRVIP-27 (TR-107286). This report (BWRVIP-27-A) incorporates changes proposed by the BWRVIP in response to "U.S. Nucl...

2003-08-04T23:59:59.000Z

459

Facies architecture of the upper Calvert Bluff Formation exposed in the highwall of Big Brown Mine, Fairfield, Texas  

E-Print Network (OSTI)

The facies architecture and geometry of stratigraphic surfaces within a lignite bearing interval of the Paleocene upper Calvert Bluff Formation is mapped on a photomosaic of the 150 ft (50 m) high and 12,000 ft (4km) long â??Câ? area highwall of Big Brown Mine, near Fairfield, Texas. Observed bedding and facies architecture are interpreted in terms of temporal changes, depositional environments and sequence stratigraphic setting. A three dimensional grid of 89 subsurface logs is correlated to this photomosaic to characterize log response patterns of facies. Six facies are observed: 1) lignite, 2) interdistributary bay mud, 3) prograding delta, 4) delta top mud, 5) distributary channels, and 6) incised valley fill. The six facies were defined by a combination of mapped photomosaic observations and subsurface log correlations. The lignite deposit formed in a low depositional energy, low sediment input, high-organic productivity interchannel basin. Overlying mud records overbank flooding followed by avulsion and progradation of delta deposits. Tidal-flat deposits overlying prograding delta deposits record fluctuating energy conditions on the emerging delta top. Channel deposits cutting into the delta top record lateral channel migration across delta top floodplains. These regressive delta deposits are capped by a local incised sequence boundary overlain by fluvial channel deposits inferred to have allowed sediment to bypass further basinward during lowstand. A sheet of channel deposits capping this highwall exposure records more recent erosion, followed by development of modern soil horizons. The Big Brown Mine highwall exposes a relatively complete high-frequency Paleocene stratigraphic sequence developed in an area landward of the shoreline position during maximum transgression, that progresses upsection from: 1) highstand alluvial flood basin coals, 2) a thin condensed maximum flooding interdistributary shale, 3) a thick succession of regressive deltaic strata, and 4) a high-relief, sequence-bounding erosion surface overlain by a lowstand to transgressive fill of channel deposits. Correlations with regional Wilcox Group stratigraphic studies spanning coeval shoreline and shelf strata indicate that this high-frequency sequence is within the transgressive systems tract of a 3rd order stratigraphic sequence. It appears that high-frequency sequences of sub-regional extent control the complex distribution of coal seams within central Texas.

Sturdy, Michael Dale

2006-08-01T23:59:59.000Z

460

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

SciTech Connect

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

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

1983-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "vessel ron brown" 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

Initial observations of cavitation-induced erosion of liquid metal spallation target vessels at the Spallation Neutron Source  

Science Conference Proceedings (OSTI)

During operation of the Spallation Neutron Source (SNS) at Oak Ridge National Laboratory the mechanical properties of the AISI 316L target module are altered by high-energy neutron and proton radiation. The interior surfaces of the target vessel are also damaged by cavitation-induced erosion, which results from repetitive rapid heating of the liquid mercury by high-energy proton beam pulses. Until recently no observations of cavitation-induced erosion were possible for conditions prototypical to the SNS. Post irradiation examination (PIE) of the first and second operational SNS targets was performed to gain insight into the radiation-induced changes in mechanical properties of the 316L target material and the extent of cavitation-induced erosion to the target vessel inner surfaces. Observations of cavitation-induced erosion of the first and second operational SNS target modules are presented here, including images of the target vessel interiors and specimens removed from the target beam-entrance regions.

McClintock, David A [ORNL; Riemer, Bernie [ORNL; Ferguson, Phillip D [ORNL; Carroll, Adam J [ORNL; Dayton, Michael J [ORNL

2012-01-01T23:59:59.000Z

462

A guide for the ASME code for austenitic stainless steel containment vessels for high-level radioactive materials  

Science Conference Proceedings (OSTI)

The design and fabrication criteria recommended by the US Department of Energy (DOE) for high-level radioactive materials containment vessels used in packaging is found in Section III, Division 1, Subsection NB of the ASME Boiler and Pressure Vessel Code. This Code provides material, design, fabrication, examination, and testing specifications for nuclear power plant components. However, many of the requirements listed in the Code are not applicable to containment vessels made from austenitic stainless steel with austenitic or ferritic steel bolting. Most packaging designers, engineers, and fabricators are intimidated by the sheer volume of requirements contained in the Code; consequently, the Code is not always followed and many requirements that do apply are often overlooked during preparation of the Safety Analysis Report for Packaging (SARP) that constitutes the basis to evaluate the packaging for certification.

Raske, D.T.

1995-06-01T23:59:59.000Z

463

Tank vessels of 20,000 dwt or more carrying oil in bulk. proposed design, equipment, and personnel standards  

SciTech Connect

The U.S. Coast Guard (USCG) proposes to add to the rules for tank vessels carrying oil in bulk, standards for segregated ballast tanks, dedicated clean ballast tanks, and crude washing systems, and to withdraw a previous proposal for double bottoms and segregated ballast tanks for certain tank vessels. Adoption of the proposal would reduce the probability of spillage of oil into the navigable waters of the U.S. from vessel accidents, reduce the amount of operational discharges into the oceans by deballasting and tank cleaning, and contribute to the conservation of oil. Written comments must be received by the USCG on or before 4/16/79. Public hearings will be held on 3/21/79 and 3/28/79.

1979-02-12T23:59:59.000Z

464

Materials Reliability Program: Inspection and Evaluation Guidelines for Reactor Vessel Bottom-Mounted Nozzles in U.S. PWR Plants (MR P-206)  

Science Conference Proceedings (OSTI)

This report presents inspection and evaluation guidelines for reactor vessel bottom-mounted nozzles in U.S. pressurized water reactor (PWR) plants.

2009-03-23T23:59:59.000Z

465

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

Science Conference Proceedings (OSTI)

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

Walter, Matthew [Structural Integrity Associates, Inc.; Yin, Shengjun [ORNL; Stevens, Gary [U.S. Nuclear Regulatory Commission; Sommerville, Daniel [Structural Integrity Associates, Inc.; Palm, Nathan [Westinghouse Electric Company, Cranberry Township, PA; Heinecke, Carol [Westinghouse Electric Company, Cranberry Township, PA

2012-01-01T23:59:59.000Z

466

Tumor blood vessel "normalization" improves the therapeutic efficacy of boron neutron capture therapy (BNCT) in experimental oral cancer  

Science Conference Proceedings (OSTI)

We previously demonstrated the efficacy of BNCT mediated by boronophenylalanine (BPA) to treat tumors in a hamster cheek pouch model of oral cancer with no normal tissue radiotoxicity and moderate, albeit reversible, mucositis in precancerous tissue around treated tumors. It is known that boron targeting of the largest possible proportion of tumor cells contributes to the success of BNCT and that tumor blood vessel normalization improves drug delivery to the tumor. Within this context, the aim of the present study was to evaluate the effect of blood vessel normalization on the therapeutic efficacy and potential radiotoxicity of BNCT in the hamster cheek pouch model of oral cancer.

D. W. Nigg

2012-01-01T23:59:59.000Z

467

Vessel Cold-Ironing Using a Barge Mounted PEM Fuel Cell: Project Scoping and Feasibility  

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

3-0501 3-0501 Unlimited Release Printed February 2013 Vessel Cold-Ironing Using a Barge Mounted PEM Fuel Cell: Project Scoping and Feasibility Joseph W. Pratt and Aaron P. Harris Prepared by Sandia National Laboratories Albuquerque, New Mexico 87185 and Livermore, California 94550 Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000. Approved for public release; further dissemination unlimited. 2 Issued by Sandia National Laboratories, operated for the United States Department of Energy by Sandia Corporation. NOTICE: This report was prepared as an account of work sponsored by an agency of the

468

Cells Forming Blood Vessels Send Their Copper to the Edge | Advanced Photon  

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

A Molecular Cause for One Form of Deafness A Molecular Cause for One Form of Deafness Water Theory is Watertight Nanowire Micronetworks from Carbon-Black Nanoparticles A Key Step in Repairing DNA Double-Strand Breaks An X-ray Rainbow Science Highlights Archives: 2013 | 2012 | 2011 | 2010 2009 | 2008 | 2007 | 2006 2005 | 2004 | 2003 | 2002 2001 | 2000 | 1998 | Subscribe to APS Science Highlights rss feed Cells Forming Blood Vessels Send Their Copper to the Edge FEBRUARY 20, 2007 Bookmark and Share Areas at the tips of HMVEC filopodia extensions were scanned by XFM at high resolution. The optical image is shown to the right and metal maps are shown to the left. False color images of P, Cu, and Zn are shown in the red, green and blue images respectively, and their overlay is shown to the lower right, demonstrating a transfer of cellular copper across the cell

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