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Note: This page contains sample records for the topic "boiling point material" 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
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1

CONTINUOUS ANALYZER UTILIZING BOILING POINT DETERMINATION  

DOE Patents (OSTI)

A device is designed for continuously determining the boiling point of a mixture of liquids. The device comprises a distillation chamber for boiling a liquid; outlet conduit means for maintaining the liquid contents of said chamber at a constant level; a reflux condenser mounted above said distillation chamber; means for continuously introducing an incoming liquid sample into said reflux condenser and into intimate contact with vapors refluxing within said condenser; and means for measuring the temperature of the liquid flowing through said distillation chamber. (AEC)

Pappas, W.S.

1963-03-19T23:59:59.000Z

2

2007-No54-BoilingPoint Health and Greenhouse Gas Impacts of Biomass and Fossil Fuel  

E-Print Network (OSTI)

2007-No54-BoilingPoint Theme Health and Greenhouse Gas Impacts of Biomass and Fossil Fuel Energy nations. In sub-Saharan Africa (SSA), biomass provides more than 90% of household energy needs in many nations. The combustion of biomass emits pollutants that currently cause over 1.6 million annual deaths

Kammen, Daniel M.

3

Heating surface material’s effect on subcooled flow boiling heat transfer of R134a  

Science Conference Proceedings (OSTI)

In this study, subcooled flow boiling of R134a on copper (Cu) and stainless steel (SS) heating surfaces was experimentally investigated from both macroscopic and microscopic points of view. By utilizing a high-speed digital camera, bubble growth rate, bubble departure size, and nucleation site density, were able to be observed and analyzed from the microscopic point of view. Macroscopic characteristics of the subcooled flow boiling, such as heat transfer coefficient, were able to be measured as well. Experimental results showed that there are no obvious difference between the copper and the stainless surface with respect to bubble dynamics, such as contact angle, growth rate and departure size. On the contrary, the results clearly showed a trend that the copper surface had a better performance than the stainless steel surface in terms of heat transfer coefficient. It was also observed that wall heat fluxes on both surfaces were found highly correlated with nucleation site density, as bubble hydrodynamics are similar on these two surfaces. The difference between these two surfaces was concluded as results of different surface thermal conductivities.

Ling Zou; Barclay G. Jones

2012-11-01T23:59:59.000Z

4

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

5

Boiling radial flow in fractures of varying wall porosity  

DOE Green Energy (OSTI)

The focus of this report is the coupling of conductive heat transfer and boiling convective heat transfer, with boiling flow in a rock fracture. A series of experiments observed differences in boiling regimes and behavior, and attempted to quantify a boiling convection coefficient. The experimental study involved boiling radial flow in a simulated fracture, bounded by a variety of materials. Nonporous and impermeable aluminum, highly porous and permeable Berea sandstone, and minimally porous and permeable graywacke from The Geysers geothermal field. On nonporous surfaces, the heat flux was not strongly coupled to injection rate into the fracture. However, for porous surfaces, heat flux, and associated values of excess temperature and a boiling convection coefficient exhibited variation with injection rate. Nucleation was shown to occur not upon the visible surface of porous materials, but a distance below the surface, within the matrix. The depth of boiling was a function of injection rate, thermal power supplied to the fracture, and the porosity and permeability of the rock. Although matrix boiling beyond fracture wall may apply only to a finite radius around the point of injection, higher values of heat flux and a boiling convection coefficient may be realized with boiling in a porous, rather than nonporous surface bounded fracture.

Barnitt, Robb Allan

2000-06-01T23:59:59.000Z

6

Atomic Scale Modeling of Point Defects in Materials: Coupling Ab ...  

Science Conference Proceedings (OSTI)

Presentation Title, Atomic Scale Modeling of Point Defects in Materials: Coupling Ab Initio and Elasticity ... Electrochemical Shock of Lithium Battery Materials.

7

Mitigating kinematic locking in the material point method  

Science Conference Proceedings (OSTI)

The material point method exhibits kinematic locking when traditional linear shape functions are used with a rectangular grid. The locking affects both the strain and the stress fields, which can lead to inaccurate results and nonphysical behavior. This ... Keywords: Locking, Material point method, Meshfree methods, Particle methods

C. M. Mast; P. Mackenzie-Helnwein; P. Arduino; G. R. Miller; W. Shin

2012-06-01T23:59:59.000Z

8

Roughness and surface material effects on nucleate boiling heat transfer from cylindrical surfaces to refrigerants R-134a and R-123  

SciTech Connect

This paper presents results of an experimental investigation carried out to determine the effects of the surface roughness of different materials on nucleate boiling heat transfer of refrigerants R-134a and R-123. Experiments have been performed over cylindrical surfaces of copper, brass and stainless steel. Surfaces have been treated by different methods in order to obtain an average roughness, Ra, varying from 0.03 {mu}m to 10.5 {mu}m. Boiling curves at different reduced pressures have been raised as part of the investigation. The obtained results have shown significant effects of the surface material, with brass being the best performing and stainless steel the worst. Polished surfaces seem to present slightly better performance than the sand paper roughened. Boiling on very rough surfaces presents a peculiar behavior characterized by good thermal performance at low heat fluxes, the performance deteriorating at high heat fluxes with respect to smoother surfaces. (author)

Jabardo, Jose M. Saiz [Escuela Politecnica Superior, Universidad de la Coruna, Mendizabal s/n Esteiro, 15403 Ferrol, Coruna (Spain); Ribatski, Gherhardt; Stelute, Elvio [Department of Mechanical Engineering, Escola de Engenharia de Sao Carlos (EESC), University of Sao Paulo (USP), Av. Trabalhador Saocarlense 400 Centro, 13566-590 Sao Carlos, SP (Brazil)

2009-04-15T23:59:59.000Z

9

2011 Radioactive Materials Usage Survey for Unmonitored Point Sources  

SciTech Connect

This report provides the results of the 2011 Radioactive Materials Usage Survey for Unmonitored Point Sources (RMUS), which was updated by the Environmental Protection (ENV) Division's Environmental Stewardship (ES) at Los Alamos National Laboratory (LANL). ES classifies LANL emission sources into one of four Tiers, based on the potential effective dose equivalent (PEDE) calculated for each point source. Detailed descriptions of these tiers are provided in Section 3. The usage survey is conducted annually; in odd-numbered years the survey addresses all monitored and unmonitored point sources and in even-numbered years it addresses all Tier III and various selected other sources. This graded approach was designed to ensure that the appropriate emphasis is placed on point sources that have higher potential emissions to the environment. For calendar year (CY) 2011, ES has divided the usage survey into two distinct reports, one covering the monitored point sources (to be completed later this year) and this report covering all unmonitored point sources. This usage survey includes the following release points: (1) all unmonitored sources identified in the 2010 usage survey, (2) any new release points identified through the new project review (NPR) process, and (3) other release points as designated by the Rad-NESHAP Team Leader. Data for all unmonitored point sources at LANL is stored in the survey files at ES. LANL uses this survey data to help demonstrate compliance with Clean Air Act radioactive air emissions regulations (40 CFR 61, Subpart H). The remainder of this introduction provides a brief description of the information contained in each section. Section 2 of this report describes the methods that were employed for gathering usage survey data and for calculating usage, emissions, and dose for these point sources. It also references the appropriate ES procedures for further information. Section 3 describes the RMUS and explains how the survey results are organized. The RMUS Interview Form with the attached RMUS Process Form(s) provides the radioactive materials survey data by technical area (TA) and building number. The survey data for each release point includes information such as: exhaust stack identification number, room number, radioactive material source type (i.e., potential source or future potential source of air emissions), radionuclide, usage (in curies) and usage basis, physical state (gas, liquid, particulate, solid, or custom), release fraction (from Appendix D to 40 CFR 61, Subpart H), and process descriptions. In addition, the interview form also calculates emissions (in curies), lists mrem/Ci factors, calculates PEDEs, and states the location of the critical receptor for that release point. [The critical receptor is the maximum exposed off-site member of the public, specific to each individual facility.] Each of these data fields is described in this section. The Tier classification of release points, which was first introduced with the 1999 usage survey, is also described in detail in this section. Section 4 includes a brief discussion of the dose estimate methodology, and includes a discussion of several release points of particular interest in the CY 2011 usage survey report. It also includes a table of the calculated PEDEs for each release point at its critical receptor. Section 5 describes ES's approach to Quality Assurance (QA) for the usage survey. Satisfactory completion of the survey requires that team members responsible for Rad-NESHAP (National Emissions Standard for Hazardous Air Pollutants) compliance accurately collect and process several types of information, including radioactive materials usage data, process information, and supporting information. They must also perform and document the QA reviews outlined in Section 5.2.6 (Process Verification and Peer Review) of ES-RN, 'Quality Assurance Project Plan for the Rad-NESHAP Compliance Project' to verify that all information is complete and correct.

Sturgeon, Richard W. [Los Alamos National Laboratory

2012-06-27T23:59:59.000Z

10

2011 Radioactive Materials Usage Survey for Unmonitored Point Sources  

SciTech Connect

This report provides the results of the 2011 Radioactive Materials Usage Survey for Unmonitored Point Sources (RMUS), which was updated by the Environmental Protection (ENV) Division's Environmental Stewardship (ES) at Los Alamos National Laboratory (LANL). ES classifies LANL emission sources into one of four Tiers, based on the potential effective dose equivalent (PEDE) calculated for each point source. Detailed descriptions of these tiers are provided in Section 3. The usage survey is conducted annually; in odd-numbered years the survey addresses all monitored and unmonitored point sources and in even-numbered years it addresses all Tier III and various selected other sources. This graded approach was designed to ensure that the appropriate emphasis is placed on point sources that have higher potential emissions to the environment. For calendar year (CY) 2011, ES has divided the usage survey into two distinct reports, one covering the monitored point sources (to be completed later this year) and this report covering all unmonitored point sources. This usage survey includes the following release points: (1) all unmonitored sources identified in the 2010 usage survey, (2) any new release points identified through the new project review (NPR) process, and (3) other release points as designated by the Rad-NESHAP Team Leader. Data for all unmonitored point sources at LANL is stored in the survey files at ES. LANL uses this survey data to help demonstrate compliance with Clean Air Act radioactive air emissions regulations (40 CFR 61, Subpart H). The remainder of this introduction provides a brief description of the information contained in each section. Section 2 of this report describes the methods that were employed for gathering usage survey data and for calculating usage, emissions, and dose for these point sources. It also references the appropriate ES procedures for further information. Section 3 describes the RMUS and explains how the survey results are organized. The RMUS Interview Form with the attached RMUS Process Form(s) provides the radioactive materials survey data by technical area (TA) and building number. The survey data for each release point includes information such as: exhaust stack identification number, room number, radioactive material source type (i.e., potential source or future potential source of air emissions), radionuclide, usage (in curies) and usage basis, physical state (gas, liquid, particulate, solid, or custom), release fraction (from Appendix D to 40 CFR 61, Subpart H), and process descriptions. In addition, the interview form also calculates emissions (in curies), lists mrem/Ci factors, calculates PEDEs, and states the location of the critical receptor for that release point. [The critical receptor is the maximum exposed off-site member of the public, specific to each individual facility.] Each of these data fields is described in this section. The Tier classification of release points, which was first introduced with the 1999 usage survey, is also described in detail in this section. Section 4 includes a brief discussion of the dose estimate methodology, and includes a discussion of several release points of particular interest in the CY 2011 usage survey report. It also includes a table of the calculated PEDEs for each release point at its critical receptor. Section 5 describes ES's approach to Quality Assurance (QA) for the usage survey. Satisfactory completion of the survey requires that team members responsible for Rad-NESHAP (National Emissions Standard for Hazardous Air Pollutants) compliance accurately collect and process several types of information, including radioactive materials usage data, process information, and supporting information. They must also perform and document the QA reviews outlined in Section 5.2.6 (Process Verification and Peer Review) of ES-RN, 'Quality Assurance Project Plan for the Rad-NESHAP Compliance Project' to verify that all information is complete and correct.

Sturgeon, Richard W. [Los Alamos National Laboratory

2012-06-27T23:59:59.000Z

11

Material-Point Simulation to Cavity Collapse Under Shock  

E-Print Network (OSTI)

The collapse of cavities under shock is a key problem in various fields ranging from erosion of material, ignition of explosive, to sonoluminescence, etc. We study such processes using the material-point-method developed recently in the field of solid physics. The main points of the research include the relations between symmetry of collapsing and the strength of shock, other coexisting interfaces, as well as hydrodynamic and thermal-dynamic behaviors ignored by the pure fluid models. In the case with strong shock, we study the procedure of jet creation in the cavity; in the case with weak shock, we found that the cavity can not be collapsed completely by the shock and the cavity may collapse in a nearly isotropic way. The history of collapsing significantly influences the distribution of "hot spots" in the shocked material. The change in symmetry of collapsing is investigated. Since we use the Mie-Gr% \\"{u}neisen equation of state and the effects of strain rate are not taken into account, the behavior is the same if one magnifies the spatial and temporal scales in the same way.

Aiguo Xu; X. F. Pan; Guangcai Zhang; Jianshi Zhu

2007-06-18T23:59:59.000Z

12

Overcoming a Magnetic Sticking Point - Materials Technology @ TMS  

Science Conference Proceedings (OSTI)

Aug 25, 2009... magnetic effects into a new functional form that could be useful for integration with unconventional materials, according to the researchers.

13

Questions and Answers - What is a material with a freezing point above 0  

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

What's the melting point of steel? What's the melting point of steel? Previous Question (What's the melting point of steel?) Questions and Answers Main Index Next Question (What is a meniscus?) What is a meniscus? What is a material with a freezing point above 0 degrees Celsius? A material exists as a solid when it is below its freezing point. So, we need to find a material that is a solid at some temperature above 0°C. Almost any solid abject around you would fit this description - an aluminum soda can, a candle or a piece of chocolate all have freezing points above 0°C. Keep in mind that a material's freezing point is the same as its melting point. These are just different terms for the same thing, it just depends on whether energy is going into a substance (melting) or if energy is being

14

Advanced Nuclear Technology: EPRI Materials Management Matrix Project—Toshiba Advanced Boiling Water Reactor Materials Managem ent Table Report, Revision 0  

Science Conference Proceedings (OSTI)

Experience gained through years of operating nuclear plants has shown that materials performance issues can be a significant concern related to economic and safe long-term plant operations. Although concerns remain, industry efforts to address materials performance issues at operating plants have led to several important advances in both the underlying scientific understanding of materials degradation and the implementation of practical mitigation and management technologies. The Electric Power Research...

2010-02-09T23:59:59.000Z

15

SUPERHEATING IN A BOILING WATER REACTOR  

DOE Patents (OSTI)

A boiling-water reactor is described in which the steam developed in the reactor is superheated in the reactor. This is accomplished by providing means for separating the steam from the water and passing the steam over a surface of the fissionable material which is not in contact with the water. Specifically water is boiled on the outside of tubular fuel elements and the steam is superheated on the inside of the fuel elements.

Treshow, M.

1960-05-31T23:59:59.000Z

16

Boiling Water in Microwave  

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

Boiling Water in Microwave A 26-year old man decided to have a cup of coffee. He took a cup of water and put it in the microwave to heat it up (something that he had done numerous...

17

Hard boiling eggs  

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

Hard boiling eggs Hard boiling eggs Name: Sandburg J High Age: N/A Location: N/A Country: N/A Date: N/A Question: We have been studying chemical and physical changes in 6th grade science class and we were wondering whether hard boiling an egg would be a chemical or a physical change? Thanks for a reply! Replies: You decide. Here's what's going on: the proteins in the fresh egg are in the shape of tight little balls. When you boil the egg, these proteins unravel ("denature"), like balls of yarn unraveling into loose skeins. The strands of protein then get all tangled up with one another, so much so that they are locked in place and can no longer move. They also lock into place the other liquid components of the egg, forming all together what's called a "gel" instead of the liquid you started off with. The gel acts like a soft, rubbery solid because of the network of protein strands holding it all together. It's certainly true that when the protein denatures some chemical bonds are broken, but the most important effect is the tangling up process.

18

An Introduction to the Material Point Method using a Case Study from Gas Dynamics  

SciTech Connect

The Material Point Method (MPM) developed by Sulsky and colleagues is currently being used to solve many challenging problems involving large deformations and/or fragementations with considerable success as part of the Uintah code created by the CSAFE project. In order to understand the properties of this method an analysis of the considerable computational properties of MPM is undertaken in the context of model problems from gas dynamics. One aspect of the MPM method in the form used here is shown to have first order accuracy. Computational experiments using particle redistribution are described and show that smooth results with first order accuracy may be obtained.

Tran, L. T. [SCI Institute, University of Utah, Salt Lake City, Utah (United States); Kim, J. [School of Computing, University of Utah, Salt Lake City, Utah (United States); Berzins, M. [SCI Institute, University of Utah, Salt Lake City, Utah (United States); School of Computing, University of Utah, Salt Lake City, Utah (United States)

2008-09-01T23:59:59.000Z

19

Performance prediction evaluation of ceramic materials in point-focusing solar receivers  

DOE Green Energy (OSTI)

A Performance Prediction Model was adapted to evaluate the use of ceramic materials in solar receivers for point-focusing distributed applications. TPS system requirements were determined including the receiver operating environment (such as concentrator performance and environment/natural occurrences) and system operating parameters for various engine types. Preliminary receiver designs evolve from these system requirements. Specific receiver designs evaluated in this report to determine material functional requirements include the NRL solchem converter/heat exchanger, MIT/LL ceramic dome. Black and Veatch/EPRI ceramic tube receiver, and the Sanders honeycomb matrix Brayton receiver. Status of the first phase of a continuing task of evaluation and reporting on high temperature ceramics for solar thermal receiver applications is described. Subsequent reports will develop the Performance Prediction Model in more detail and provide data on its use in the several high temperature receiver and reactor designs planned for or under development.

Ewing, J.; Zwissler, J.

1979-06-01T23:59:59.000Z

20

A study of electrowetting-assisted boiling  

E-Print Network (OSTI)

The classical theory of boiling heat transfer based on bubble dynamics is explained and includes a full derivation of the Rohsenow boiling correlation. An alternative, more accurate correlation for determining boiling heat ...

Bralower, Harrison L. (Harrison Louis)

2011-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "boiling point material" 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

Space-radiation-induced point defect formation in optical materials. Ph.D. Thesis  

SciTech Connect

One of the central problems man has faced in his exploration of space is the long and short term effects of the space environment on the performance of spacecraft systems. The results presented in this dissertation represent the first time a definite connection has been made between the space-induced damage of optical systems and the microscopic mechanisms of point defect formation that lead to the damage. Point defect formation was observed in two, and possibly three different optical materials subjected to short-duration space exposure. Three calcium fluoride, two lithium fluoride, and three magnesium fluoride samples were flown on Space Shuttle flight STS-46 as part of the Evaluation of Oxygen Interactions with Materials - Third Phase experiment. Pre-flight and post-flight optical absorption measurements were performed on all of the samples. With the possible exception of the magnesium fluoride samples, every sample clearly showed the formation of F-centers in that section of the sample that was exposed to the low earth orbit environment. Analysis of the flight samples and laboratory experiments on control samples identify solar vacuum ultraviolet radiation as the most probable primary cause of the defect formation.

Allen, J.L.

1994-01-01T23:59:59.000Z

22

HORIZONTAL BOILING REACTOR SYSTEM  

DOE Patents (OSTI)

Reactors of the boiling water type are described wherein water serves both as the moderator and coolant. The reactor system consists essentially of a horizontal pressure vessel divided into two compartments by a weir, a thermal neutronic reactor core having vertical coolant passages and designed to use water as a moderator-coolant posltioned in one compartment, means for removing live steam from the other compartment and means for conveying feed-water and water from the steam compartment to the reactor compartment. The system further includes auxiliary apparatus to utilize the steam for driving a turbine and returning the condensate to the feed-water inlet of the reactor. The entire system is designed so that the reactor is self-regulating and has self-limiting power and self-limiting pressure features.

Treshow, M.

1958-11-18T23:59:59.000Z

23

Generalized Interpolation Material Point Approach to High Melting Explosive with Cavities Under Shock  

E-Print Network (OSTI)

Criterion for contacting is critically important for the Generalized Interpolation Material Point(GIMP) method. We present an improved criterion by adding a switching function. With the method dynamical response of high melting explosive(HMX) with cavities under shock is investigated. The physical model used in the present work is an elastic-to-plastic and thermal-dynamical model with Mie-Gr\\"uneissen equation of state. We mainly concern the influence of various parameters, including the impacting velocity $v$, cavity size $R$, etc, to the dynamical and thermodynamical behaviors of the material. For the colliding of two bodies with a cavity in each, a secondary impacting is observed. Correspondingly, the separation distance $D$ of the two bodies has a maximum value $D_{\\max}$ in between the initial and second impacts. When the initial impacting velocity $v$ is not large enough, the cavity collapses in a nearly symmetric fashion, the maximum separation distance $D_{\\max}$ increases with $v$. When the initial shock wave is strong enough to collapse the cavity asymmetrically along the shock direction, the variation of $D_{\\max}$ with $v$ does not show monotonic behavior. Our numerical results show clear indication that the existence of cavities in explosive helps the creation of ``hot spots''.

X. F. Pan; Aiguo Xu; Guangcai Zhang; Jianshi Zhu

2007-10-11T23:59:59.000Z

24

Subcooled flow boiling of fluorocarbons  

E-Print Network (OSTI)

A study was conducted of heat transfer and hydrodynamic behavior for subcooled flow boiling of Freon-113, one of a group of fluorocarbons suitable for use in cooling of high-power-density electronic components. Problems ...

Murphy, Richard Walter

1971-01-01T23:59:59.000Z

25

Microsoft PowerPoint - Siemens_materials workshop MIT EI_120310.ppt [Compatibility Mode]  

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

Critical Critical Materials and Substitutes Critical Materials and Substitutes Siemens Corporation Dr Madhav D Manjrekar Dr. Madhav D. Manjrekar Green Energy & Power Systems Dr. Thomas Scheiter & Dr. Gotthard Rieger Materials Substitution and Recycling Materials Substitution and Recycling Dr. Martin Zachau & Pamela Horner OSRAM Sylvania y Dr. Henrik Stiesdal Siemens Wind Power ©Siemens Corporation, Corporate Research, 2010. All rights reserved. ©Siemens Corporation, Corporate Research, 2010. All rights reserved. Agenda * Introduction Introduction * Application Requirements * Renewable Generation & Power Electronics * Lighting * Lighting * Discussion Trans-Atlantic Workshop on Rare Earth Elements and Other Critical Materials for a Clean Energy Future Hosted by the MIT Energy Initiative

26

Microsoft PowerPoint - Cathode contact materials PNNL.ppt [Compatibility Mode]  

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

Cathode Cathode Contact Development of Cathode Contact Materials for SOFC J.W. Stevenson, G.G. Xia, Z. Lu, X. Li, Z. Nie, T. Oh, and J.D.Templeton Pacific Northwest National Laboratory Pacific Northwest National Laboratory Richland, WA 99352 July 27-29, 2010 July 27 29, 2010 11 th Annual SECA Workshop Pittsburgh, PA Cathode/Interconnect Contact Materials Cathode/Interconnect Contact Materials Cathode Chromia-forming Protective Coating Contact layer Chromia-forming alloy interconnect 2 Cathode/Interconnect Contact Materials Cathode/Interconnect Contact Materials Requirements: High electrical conductivity to reduce interfacial electrical resistance between cathode and interconnect Contact layer Chemical and structural stability in air at SOFC operating temperature Chemical compatibility with adjacent materials (perovskite cathode,

27

Microsoft PowerPoint - IPRC Crucible and Coating materials [Compatibility Mode]  

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

Historical Historical and Current Crucible Materials and the Effects on Processing Randall Fielding, Ken Marsden, Dr. Ki-Hwan Kim* Idaho National Laboratory * Korean Atomic Energy Research Institute (KAERI) 2012 International Pyroprocessing Research Conference Aug. 26 - Aug. 30, 2012 2012 IPRC Fontana, Wisconsin Aug. 26- Aug. 30, 2012 2 Outline  Introduction  Historical Coatings  Current Coatings in pyroprocessing and fuel fabrication  Conclusions/Future Plans 2012 IPRC Fontana, Wisconsin Aug. 26- Aug. 30, 2012 Introduction  Uranium melts are quite reactive and will react with many commonly used crucible materials  U-Zr melts are more reactive and further react with common crucible materials - Reduces many crucibles (oxides and others) - Dissolves graphite materials  Coatings are used to protect the crucible from interaction and in some cases from wetting

28

CHIMNEY FOR BOILING WATER REACTOR  

DOE Patents (OSTI)

A boiling-water reactor is described which has vertical fuel-containing channels for forming steam from water. Risers above the channels increase the head of water radially outward, whereby water is moved upward through the channels with greater force. The risers are concentric and the radial width of the space between them is somewhat small. There is a relatively low rate of flow of water up through the radially outer fuel-containing channels, with which the space between the risers is in communication. (AE C)

Petrick, M.

1961-08-01T23:59:59.000Z

29

Ecological evaluation of proposed dredged material from Wilmington Harbor and Military Ocean Terminal, Sunny Point, North Carolina  

SciTech Connect

This report is intended to provide information required to address potential ecological effects of the proposed disposal of Wilmington Harbor and Military Ocean Terminal, Sunny Point (MOTSU), North Carolina, sediments in the ocean. The report is divided into five sections. Section 1.0 is the introduction containing a brief overview of the study and the study objectives. Section 2.0 describes the methods and materials used for sample collection, processing, toxicological and bioaccumulation testing, physical/chemical analysis of sediments and tissues, data analysis, and quality assurance procedures. Section 3.0 presents the results of field collections, sediment chemistry, toxicological testing, and tissue chemistry resulting from bioaccumulation exposures. Section 4.0 presents a discussion of the results and summary conclusions concerning the acceptability of the Wilmington Harbor and MOTSU dredged material for ocean disposal. Section 5.0 lists the literature cited in support of this document. A series of appendixes contain detailed data listings.

Ward, J.A.; Pinza, M.R.; Barrows, M.E.; Word, J.Q. [Battelle/Marine Sciences Lab., Sequim, WA (US)

1993-07-01T23:59:59.000Z

30

Boiling point? The skills gap in US manufacturing  

Science Conference Proceedings (OSTI)

... respondents what they considered to be the most serious skill deficiencies in their current employees, inadequate problem-solving skills topped the ...

2013-07-31T23:59:59.000Z

31

Apparatus for pumping liquids at or below the boiling point  

SciTech Connect

A pump comprises a housing having an inlet and an outlet. An impeller assembly mounted for rotation within the housing includes a first impeller piece having a first mating surface thereon and a second impeller piece having a second mating surface therein. The second mating surface of the second impeller piece includes at least one groove therein so that at least one flow channel is defined between the groove and the first mating surface of the first impeller piece. A drive system operatively associated with the impeller assembly rotates the impeller assembly within the housing.

Bingham, Dennis N. (Idaho Falls, ID)

2002-01-01T23:59:59.000Z

32

2010 Inspection and Status Report for the Boiling Nuclear Superheater...  

Office of Legacy Management (LM)

3 Annual Inspection - Boiling Nuclear Superheat (BONUS) Site, Rincn, Puerto Rico October 2013 Page 1 2013 Inspection and Status Report for the Former Boiling Nuclear Superheater...

33

Acoustically Enhanced Boiling Heat Transfer  

E-Print Network (OSTI)

An acoustic field is used to increase the critical heat flux (CHF) of a flat-boiling-heat-transfer surface. The increase is a result of the acoustic effects on the vapor bubbles. Experiments are performed to explore the effects of an acoustic field on vapor bubbles in the vicinity of a rigid-heated wall. Work includes the construction of a novel heater used to produce a single vapor bubble of a prescribed size and at a prescribed location on a flatboiling surface for better study of an individual vapor bubble's reaction to the acoustic field. Work also includes application of the results from the single-bubble heater to a calibrated-copper heater used for quantifying the improvements in CHF.

Z. W. Douglas; M. K. Smith; A. Glezer

2008-01-07T23:59:59.000Z

34

Material Point Methods  

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

change. This brings about the possibility of new simulations enabled at the exascale for a variety of phenomena in high energy multiphysics problems as well as general...

35

Biomedical studies on solvent refined coal (SRC-II) liquefaction materials: a status report  

SciTech Connect

This technical report summarizes the results of biomedical research effort on solvent refined coal (SRC) materials. The samples, described in the text, as well as samples of raw shale oil, crude petroleum, and some SRC-I materials were evaluated for biological activity in several different systems: (1) microbial mutagenesis (Ames assay), coupled to chemical characterization efforts, (2) in vitro mammalian cell toxicity and transformation, (3) epidermal carcinogenesis (skin painting) in mice, (4) acute and subchronic oral toxicity in rats, (5) developmental toxicity in rats, and (6) dosimetry and metabolism in rats. High boiling point materials (identified) showed significant mutagenic activity while lower boiling fractions from both processes were inactive; crude petroleum was also inactive, while raw shale oil showed only a low level of activity. Chemical characterization studies suggested that 3- and 4-ring primary aromatic amines are responsible for a large fraction of the mutagenic activity. Cultured mammalian cell studies showed that materials exhibiting a positive effect in the Ames system also caused mammalian cell transformation. The results of skin carcinogenesis studies in the mouse were generally consistent with those of the cellular studies. Light distillates were found to be moderately toxic after oral administration to rats. Fuel upgrading, process modification, and appropriate occupational/environmental controls may ameliorate some of the biological effects of SRC materials and other coal liquids of high boiling point. Low-boiling SRC liquids appear to have little biological effects in the assays employed. (LTN)

1979-10-01T23:59:59.000Z

36

Numerical Simulations of Boiling Jet Impingement Cooling in Power Electronics  

DOE Green Energy (OSTI)

This paper explores turbulent boiling jet impingement for cooling power electronic components in hybrid electric vehicles.

Narumanchi, S.; Troshko, A.; Hassani, V.; Bharathan, D.

2006-12-01T23:59:59.000Z

37

Pool boiling heat transfer characteristics of nanofluids  

E-Print Network (OSTI)

Nanofluids are engineered colloidal suspensions of nanoparticles in water, and exhibit a very significant enhancement (up to 200%) of the boiling Critical Heat Flux (CHF) at modest nanoparticle concentrations (50.1% by ...

Kim, Sung Joong, Ph. D. Massachusetts Institute of Technology

2007-01-01T23:59:59.000Z

38

Nucleate boiling bubble growth and departure  

E-Print Network (OSTI)

The vapor bubble formation on the heating surface during pool boiling has been studied experimentally. Experiments were made at the atmospheric pressure 28 psi and 40 psi, using degassed distilled water and ethanol. The ...

Staniszewski, Bogumil E.

1959-01-01T23:59:59.000Z

39

Carbon, oxygen and their interaction with intrinsic point defects in solar silicon ribbon material. Annual report, September 1982-September 1983  

DOE Green Energy (OSTI)

This report first provides some background information on intrinsic point defects, and on carbon and oxygen in silicon in so far as it may be relevant for the efficiency of solar cells fabricated from EFG ribbon material. We discuss the co-precipitation of carbon and oxygen and especially of carbon and silicon self interstitials. A simple model for the electrical activity of carbon-self-interstitial agglomerates is presented. We assume that the self-interstitial content of these agglomerates determines their electrical activity and that both compressive stresses (high self-interstitial content) and tensile stresses (low self-interstitial content) give rise to electrical activity of the agglomerates. The self-interstitial content of these carbon-related agglomerates may be reduced by an appropriate high-temperature treatment and enhanced by a supersaturation of self-interstitials generated during formation of the p-n junction of solar cells. It is suggested that oxygen present in supersaturation in carbon-rich silicon may be induced to form SiO/sub 2/ precipitates by self-interstitials generated during phosphorus diffusion. It is proposed that the SiO/sub 2/-Si interface of the precipates gives rise to a continuum of donor states and that these interface states are responsible for at least part of the light-enhancement effects observed in oxygen containing EFG silicon after phosphorus diffusion.

Goesele, U.; Ast, D.G.

1983-10-01T23:59:59.000Z

40

Boiling Springs Geothermal Area | Open Energy Information  

Open Energy Info (EERE)

Boiling Springs Geothermal Area Boiling Springs Geothermal Area Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Geothermal Resource Area: Boiling Springs Geothermal Area Contents 1 Area Overview 2 History and Infrastructure 3 Regulatory and Environmental Issues 4 Exploration History 5 Well Field Description 6 Geology of the Area 7 Geofluid Geochemistry 8 NEPA-Related Analyses (0) 9 Exploration Activities (0) 10 References Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"TERRAIN","zoom":6,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"500px","height":"300px","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":44.3641,"lon":-115.856,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

Note: This page contains sample records for the topic "boiling point material" 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

Boiling characteristics of small multitube bundles  

SciTech Connect

Boiling characteristics of multitube bundles have been investigated experimentally. Small bundles of up to nine rows were used. Void fraction profiles in the test vessel, tube surface temperatures, power input to individual tubes, and critical heat fluxes were measured for different bundle arrangements and boiling conditions. The data were used to study the system hydrodynamics, bundle heat transfer coefficients, and bundle critical heat flux. The data showed that for lower heat fluxes, the heat transfer characteristics are affected by the system hydrodynamics resulting in higher heat transfer coefficients, whereas at higher heat fluxes nucleate boiling is the dominant mechanism. The data also showed that within a tube bundle, the vapor rising from lower tubes enhances the CHF characteristics of the upper tubes.

Chan, A.M.C. (Ontario Hydro Research Div., Toronto (Canada)); Shoukri, M. (McMaster Univ., Hamilton, Ontario (Canada))

1987-08-01T23:59:59.000Z

42

Pool boiling on nano-finned surfaces  

E-Print Network (OSTI)

The effect of nano-structured surfaces on pool boiling heat transfer is explored in this study. Experiments are conducted in a cubical test chamber containing fluoroinert coolant (PF5060, Manufacturer: 3M Co.) as the working fluid. Pool boiling experiments are conducted for saturation and subcooled conditions. Three different types of ordered nano-structured surfaces are fabricated using Step and flash imprint lithography on silicon substrates followed by Reactive Ion Etching (RIE) or Deep Reactive Ion Etching (DRIE). These nano-structures consist of a square array of cylindrical nanofins with a longitudinal pitch of 1 mm, transverse pitch of 0.9 mm and fixed (uniform) heights ranging from 15 nm - 650 nm for each substrate. The contact angle of de-ionized water on the substrates is measured before and after the boiling experiments. The contact-angle is observed to increase with the height of the nano-fins. Contact angle variation is also observed before and after the pool boiling experiments. The pool boiling curves for the nano-structured silicon surfaces are compared with that of atomically smooth single-crystal silicon (bare) surfaces. Data processing is performed to estimate the heat flux through the projected area (plan area) for the nano-patterned zone as well as the heat flux through the total nano-patterned area, which includes the surface area of the fins. Maximum heat flux (MHF) is enhanced by ~120 % for the nanofin surfaces compared to bare (smooth) surfaces, under saturation condition. The pool boiling heat flux data for the three nano-structured surfaces progressively overlap with each other in the vicinity of the MHF condition. Based on the experimental data several micro/nano-scale transport mechanisms responsible for heat flux enhancements are identified, which include: "microlayer" disruption or enhancement, enhancement of active nucleation site density, enlargement of cold spots and enhancement of contact angle which affects the vapor bubble departure frequency.

Sriraman, Sharan Ram

2007-12-01T23:59:59.000Z

43

Pool boiling on nano-finned surfaces  

E-Print Network (OSTI)

The effect of nano-structured surfaces on pool boiling heat transfer is explored in this study. Experiments are conducted in a cubical test chamber containing fluoroinert coolant (PF5060, Manufacturer: 3M Co.) as the working fluid. Pool boiling experiments are conducted for saturation and subcooled conditions. Three different types of ordered nano-structured surfaces are fabricated using Step and flash imprint lithography on silicon substrates followed by Reactive Ion Etching (RIE) or Deep Reactive Ion Etching (DRIE). These nano-structures consist of a square array of cylindrical nanofins with a longitudinal pitch of 1 mm, transverse pitch of 0.9 mm and fixed (uniform) heights ranging from 15 nm – 650 nm for each substrate. The contact angle of de-ionized water on the substrates is measured before and after the boiling experiments. The contact-angle is observed to increase with the height of the nano-fins. Contact angle variation is also observed before and after the pool boiling experiments. The pool boiling curves for the nano-structured silicon surfaces are compared with that of atomically smooth single-crystal silicon (bare) surfaces. Data processing is performed to estimate the heat flux through the projected area (plan area) for the nano-patterned zone as well as the heat flux through the total nano-patterned area, which includes the surface area of the fins. Maximum heat flux (MHF) is enhanced by ~120 % for the nanofin surfaces compared to bare (smooth) surfaces, under saturation condition. The pool boiling heat flux data for the three nano-structured surfaces progressively overlap with each other in the vicinity of the MHF condition. Based on the experimental data several micro/nano-scale transport mechanisms responsible for heat flux enhancements are identified, which include: “microlayer” disruption or enhancement, enhancement of active nucleation site density, enlargement of cold spots and enhancement of contact angle which affects the vapor bubble departure frequency.

Sriraman, Sharan Ram

2007-12-01T23:59:59.000Z

44

Microsoft PowerPoint - 6_Rowe-Future Challenges for Global Fuel Cycle Material Accounting Final_Updated.pptx  

National Nuclear Security Administration (NNSA)

Future Challenges Future Challenges for Global Fuel Cycle Material Accounting Nathan Rowe Chris Pickett Oak Ridge National Laboratory Nuclear Materials Management & Safeguards System Users Annual Training Meeting May 20-23, 2013 St. Louis, Missouri 2 Future Challenges for Global Fuel Cycle Material Accounting Introduction * Changing Nuclear Fuel Cycle Activities * Nuclear Security Challenges * How to Respond? - Additional Protocol - State-Level Concept - Continuity of Knowledge * Conclusion 3 Future Challenges for Global Fuel Cycle Material Accounting Nuclear Fuel Cycle Source: International Atomic Energy Agency (IAEA), Nuclear Fuel Cycle Information System (NFCIS) web site IAEA Safeguards Begins Here 4 Future Challenges for Global Fuel Cycle Material Accounting Nuclear Weapons Cycle Conversion

45

Advanced Light Water Reactor - Boiling Water Reactor Degradation Matrix (ALWR BWR DM), Revision 0  

Science Conference Proceedings (OSTI)

The advanced light water reactor–boiling water reactor degradation matrix (ALWR BWR DM) is an essential piece of the Electric Power Research Institute’s (EPRI’s) Advanced Nuclear Technology (ANT) materials management matrix initiative for advanced LWR designs. The materials management matrix provides a tool to assist the industry in proactive identification and consideration of materials issues as well as mitigation and management opportunities from the design phase, through component fabrication and pla...

2009-08-25T23:59:59.000Z

46

The role of surface conditions in nucleate boiling  

E-Print Network (OSTI)

Nucleation from a single cavity has been stuied indicating that cavity gemtry is aportant in two ways. The mouth diameter determines the superheat nmeded to initiate boiling and its shape determines its stability one boiling ...

Griffith, P.

1958-01-01T23:59:59.000Z

47

Boiling Water Reactor Sampling Summary: 2012 Update  

Science Conference Proceedings (OSTI)

This report documents boiling water reactor (BWR) sampling practices for key reactor water and feedwater parameters. It includes information on analysis methods, sampling frequencies, and compliance with the recommended sampling frequencies in BWRVIP-190: BWR Vessels and Internals Project, BWR Water Chemistry Guidelines – 2008 Revision (EPRI report 1016579).

2013-03-28T23:59:59.000Z

48

Computations of Explosive Boiling in Microgravity  

Science Conference Proceedings (OSTI)

Dynamics of the explosive growth of a vapor bubble in microgravity is investigated by direct numerical simulation. A front tracking/finite difference technique is used to solve for the velocity and the temperature field in both phases and to account ... Keywords: front tracking, liquid/vapor phase change, microgravity, unstable boiling

Asghar Esmaeeli; Grétar Tryggvason

2003-12-01T23:59:59.000Z

49

Transition from film boiling to nucleate boiling in forced convection vertical flow  

E-Print Network (OSTI)

The mechanism of collapse of forced cnnvection annular vertical flow film boiling, with liquid core, is investigated using liquid nitrogen at low pressures. The report includes the effect of heat flux from the buss bar. ...

Iloeje, Onwuamaeze C.

1972-01-01T23:59:59.000Z

50

Mechanism of nucleate pool boiling heat transfer to sodium and the criterion for stable boiling  

E-Print Network (OSTI)

A comparison between liquid metals and other common fluids, like water, is made as regards to the various stages of nucleate pool boiling. It is suggested that for liquid metals the stage of building the thermal layer plays ...

Shai, Isaac

1967-01-01T23:59:59.000Z

51

Film boiling on spheres in single- and two-phase flows.  

SciTech Connect

Film boiling on spheres in single- and two-phase flows was studied experimentally and theoretically with an emphasis on establishing the film boiling heat transfer closure law, which is useful in the analysis of nuclear reactor core melt accidents. Systematic experimentation of film boiling on spheres in single-phase water flows was carried out to investigate the effects of liquid subcooling (from 0 to 40 C), liquid velocity (from 0 to 2 m/s), sphere superheat (from 200 to 900 C), sphere diameter (from 6 to 19 mm), and sphere material (stainless steel and brass) on film boiling heat transfer. Based on the experimental data a general film boiling heat transfer correlation is developed. Utilizing a two-phase laminar boundary-layer model for the unseparated front film region and a turbulent eddy model for the separated rear region, a theoretical model was developed to predict the film boiling heat transfer in all single-phase regimes. The film boiling from a sphere in two-phase flows was investigated both in upward two-phase flows (with void fraction from 0.2 to 0.65, water velocity from 0.6 to 3.2 m/s, and steam velocity from 3.0 to 9.0 m/s) and in downward two-phase flows (with void fraction from 0.7 to 0.95, water velocity from 1.9 to 6.5 m/s, and steam velocity from 1.1 to 9.0 m/s). The saturated single-phase heat transfer correlation was found to be applicable to the two-phase film boiling data by making use of the actual water velocity (water phase velocity), and an adjustment factor of (1 - {alpha}){sup 1/4} (with a being the void fraction) for downward flow case only. Slight adjustments of the Reynolds number exponents in the correlation provided an even better interpretation of the two-phase data. Preliminary experiments were also conducted to address the influences of multi-sphere structure on the film boiling heat transfer in single- and two-phase flows.

Liu, C.; Theofanous, T. G.

2000-08-29T23:59:59.000Z

52

Nucleate boiling pressure drop in an annulus: Book 5  

Science Conference Proceedings (OSTI)

The application of the work described in this report is the production reactors at the Savannah River Site, and the context is nuclear reactor safety. The Loss of Coolant Accident (LOCA) scenario considered involves a double-ended break of a primary coolant pipe in the reactor. During a LOCA, the flow through portions of the reactor may reverse direction or be greatly reduced, depending upon the location of the break. The reduced flow rate of coolant (D{sub 2}O) through the fuel assembly channels of the reactor -- downflow in this situation -- can lead to boiling and to the potential for flow instabilities which may cause some of the fuel assembly channels to overheat and melt. That situation is to be avoided. The experimental approach is to provide a test annulus which simulates geometry, materials, and flow conditions in a Mark-22 fuel assembly (Coolant Channel 3) to the extent possible. The key analysis approaches are: To compare the minima in the measured demand curves with analytical criteria, in particular the Saha-Zuber (1974) model; and to compare the pressure and temperature as a function of length in the annulus with an integral model for flow boiling in a heated channel. Nineteen test series and a total of 178 tests were performed. Testing addressed the effects of: Heat flux; pressure; helium gas; power tilt; ribs; asymmetric heat flux. This document consists solely of the plato file index from 11/87 to 11/90.

Not Available

1992-11-01T23:59:59.000Z

53

Bench-scale screening tests for a boiling sodium-potassium alloy solar receiver  

DOE Green Energy (OSTI)

Bench-scale tests were carried out in support of the design of a second-generation 75-kW{sub t} reflux pool-boiler solar receiver. The receiver will be made from Haynes Alloy 230 and will contain the sodium-potassium alloy NaK-78. The bench-scale tests used quartz-lamp-heated boilers to screen candidate boiling-stabilization materials and methods at temperatures up to 750{degree}C. Candidates that provided stable boiling were tested for hot-restart behavior. Poor stability was obtained with single 1/4-inch diameter patches of powdered metal hot-press-sintered onto the wetted side of the heat-input area. Laser-drilled and electric-discharge-machined cavities in the heated surface also performed poorly. Small additions of xenon, and heated-surface tilt out of the vertical dramatically improved poor boiling stability; additions of helium or oxygen did not. The most stable boiling was obtained when the entire heat-input area was covered by a powdered-metal coating. The effect of heated-area size was assessed for one coating: at low incident fluxes, when even this coating performed poorly, increasing the heated-area size markedly improved boiling stability. Good hot-restart behavior was not observed with any candidate, although results were significantly better with added xenon in a boiler shortened from 3 to 2 feet. In addition to the screening tests, flash-radiography imaging of metal-vapor bubbles during boiling was attempted. Contrary to the Cole-Rohsenow correlation, these bubble-size estimates did not vary with pressure; instead they were constant, consistent with the only other alkali metal measurements, but about 1/2 their size.

Moreno, J.B.; Moss, T.A.

1993-06-01T23:59:59.000Z

54

Boiling Water Reactor Zinc Addition Sourcebook  

Science Conference Proceedings (OSTI)

Boiling water reactors (BWRs) have been injecting zinc into the primary coolant via the feedwater system for over 25 years to control primary system radiation fields. The zinc injection process has evolved since the initial application at the Hope Creek Nuclear Station in 1986. This evolution included transition from natural zinc oxide to depleted zinc oxide and from active zinc injection skids (pumped systems) to passive injection systems (zinc pellet beds).  Also occurring were various ...

2013-11-15T23:59:59.000Z

55

Results of the DF-4 BWR (boiling water reactor) control blade-channel box test  

DOE Green Energy (OSTI)

The DF-4 in-pile fuel damage experiment investigated the behavior of boiling water reactor (BWR) fuel canisters and control blades in the high temperature environment of an unrecovered reactor accident. This experiment, which was carried out in the Annular Core Research Reactor (ACRR) at Sandia National Laboratories, was performed under the USNRC's internationally sponsored severe fuel damage (SFD) program. The DF-4 test is described herein and results from the experiment are presented. Important findings from the DF-4 test include the low temperature melting of the stainless steel control blade caused by reaction with the B{sub 4}C, and the subsequent low temperature attack of the Zr-4 channel box by the relocating molten blade components. Hydrogen generation was found to continue throughout the experiment, diminishing slightly following the relocation of molten oxidizing zircaloy to the lower extreme of the test bundle. A large blockage which was formed from this material continued to oxidize while steam was being fed into the the test bundle. The results of this test have provided information on the initial stages of core melt progression in BWR geometry involving the heatup and cladding oxidation stages of a severe accident and terminating at the point of melting and relocation of the metallic core components. The information is useful in modeling melt progression in BWR core geometry, and provides engineering insight into the key phenomena controlling these processes. 12 refs., 12 figs.

Gauntt, R.O.; Gasser, R.D.

1990-10-01T23:59:59.000Z

56

Critical heat flux and boiling heat transfer to water in a 3-mm-diameter horizontal tube.  

DOE Green Energy (OSTI)

Boiling of the coolant in an engine, by design or by circumstance, is limited by the critical heat flux phenomenon. As a first step in providing relevant engine design information, this study experimentally addressed both rate of boiling heat transfer and conditions at the critical point of water in a horizontal tube of 2.98 mm inside diameter and 0.9144 m heated length. Experiments were performed at system pressure of 203 kPa, mass fluxes in range of 50 to 200 kg/m{sup z}s, and inlet temperatures in range of ambient to 80 C. Experimental results and comparisons with predictive correlations are presented.

Yu, W.; Wambsganss, M. W.; Hull, J. R.; France, D. M.

2000-12-04T23:59:59.000Z

57

SWR 1000: The Innovative Boiling Water Reactor  

SciTech Connect

Framatome ANP has developed the boiling water reactor SWR 1000 in close cooperation with German nuclear utilities and with support from various European partners. This advanced reactor design marks a new era in the successful tradition of boiling water reactor technology and, with a gross electric output of between 1290 and 1330 MW, is aimed at assuring competitive power generating costs compared to gas- and coal-fired stations. At the same time, the SWR 1000 meets the highest safety standards, including control of a core melt accident these objectives are met by supplementing active safety systems with passive safety equipment of diverse design for accident detection and control and by simplifying systems needed for normal plant operation on the basis of past operating experience. The plant is also protected against airplane crash loads. A short construction period, flexible fuel cycle lengths of between 12 and 24 months and a high fuel discharge burn-up all contribute towards meeting economic goals. The SWR 1000 fulfills international nuclear regulatory requirements and has been offered to TVO for the fifth nuclear unit in Finland. (authors)

Brettschuh, Werner [Framatome ANP GmbH, Berlinerstrasse 295, 63067 Offenbach (Germany); Hudson, Greg [Framatome ANP Inc., 400 South Tyron Street, Charlotte, NC 28285 (United States)

2004-07-01T23:59:59.000Z

58

On the hot-spot-controlled critical heat flux mechanism in pool boiling of saturated fluids  

SciTech Connect

In this paper, we further investigate the hypothesis that the critical heat flux (CHF) occurs when some point on the heated surface reaches a high enough temperature that liquid can no longer contact that point, resulting in a gradual but continuous increase in the overall surface temperature. This hypothesis unifies the occurrence of the CHF and the quenching of hot surfaces by relating both to the same concept, i.e., the ability of a liquid to contact a hot surface. We use a two-dimensional transient conduction model to study the boiling phenomenon in the second transition region of saturated pool nucleate boiling on a horizontal surface. The heater surface is assumed to consist of two regions: a dry patch region formed as a result of complete evaporation of the thinner liquid macrolayers and a two-phase macrolayer region formed by numerous vapor stems penetrating relatively thick liquid macrolayers. The constitutive relations used to determine the stem-macrolayer configuration in the two-phase macrolayer region of the boiling surface were reevaluated for Gaertner's clean water and water-nickel/salt solution. 29 refs.

Unal, C.; Sadasivan, P.; Nelson, R.A.

1992-01-01T23:59:59.000Z

59

On the hot-spot-controlled critical heat flux mechanism in pool boiling of saturated fluids  

SciTech Connect

In this paper, we further investigate the hypothesis that the critical heat flux (CHF) occurs when some point on the heated surface reaches a high enough temperature that liquid can no longer contact that point, resulting in a gradual but continuous increase in the overall surface temperature. This hypothesis unifies the occurrence of the CHF and the quenching of hot surfaces by relating both to the same concept, i.e., the ability of a liquid to contact a hot surface. We use a two-dimensional transient conduction model to study the boiling phenomenon in the second transition region of saturated pool nucleate boiling on a horizontal surface. The heater surface is assumed to consist of two regions: a dry patch region formed as a result of complete evaporation of the thinner liquid macrolayers and a two-phase macrolayer region formed by numerous vapor stems penetrating relatively thick liquid macrolayers. The constitutive relations used to determine the stem-macrolayer configuration in the two-phase macrolayer region of the boiling surface were reevaluated for Gaertner`s clean water and water-nickel/salt solution. 29 refs.

Unal, C.; Sadasivan, P.; Nelson, R.A.

1992-05-01T23:59:59.000Z

60

Preliminary results of the US pool-boiling coils from the IFSMTF full-array tests  

SciTech Connect

The Large Coil Task to develop superconducting magnets for fusion reactors, is now in the midst of full-array tests in the International Fusion Superconducting Magnet Test Facility at Oak Ridge National Laboratory. Included in the test array are two pool-boiling coils designed and fabricated by US manufacturers, General Dynamics/Convair Division and General Electric/Union Carbide Corporation. So far, both coils have been energized to full design currents in the single-coil tests, and the General Dynamics coil has reached the design point in the first Standard-I full-array test. Both coils performed well in the charging experiments. Extensive heating tests and the heavy instrumentation of these coils have, however, revealed some generic limitations of large pool-boiling superconducting coils. Details of these results and their analyses are reported.

Lue, J.W.; Dresner, L.; Lubell, M.S.; Luton, J.N.; McManamy, T.J.; Shen, S.S.

1986-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "boiling point material" 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

A method of correlating heat transfer data for surface boiling of liquids  

E-Print Network (OSTI)

A method based an a logical uxplanation of the meani of beat transfer associated with the boiling process is presented for correlating heat transfer data for nucleate boiling of liquids for the case of pool boiling. Tbe ...

Rohsenow, Warren M.

1951-01-01T23:59:59.000Z

62

PRELIMINARY HAZARD SUMMARY REPORT ON THE BOILING EXPERIMENTAL REACTOR (BER)  

SciTech Connect

A preliminary evaluation of the hazards associated with a 20-Mw boiling reactor for the purpose of determining site requirements is presented. The Boiling Experimental Reactor design, safety features, and performance are given and the surroundings of the site at Argonne National Laboratory are described. (T.R.H.)

West, J.M.; Anderson, C.A.; Dietrich, J.R.; Harrer, J.M.; Jameson, A.S.; Untermyer, S.

1954-05-01T23:59:59.000Z

63

Conversion of direct process high-boiling residue to monosilanes  

DOE Patents (OSTI)

A process for the production of monosilanes from the high-boiling residue resulting from the reaction of hydrogen chloride with silicon metalloid in a process typically referred to as the "direct process." The process comprises contacting a high-boiling residue resulting from the reaction of hydrogen chloride and silicon metalloid, with hydrogen gas in the presence of a catalytic amount of aluminum trichloride effective in promoting conversion of the high-boiling residue to monosilanes. The present process results in conversion of the high-boiling residue to monosilanes. At least a portion of the aluminum trichloride catalyst required for conduct of the process may be formed in situ during conduct of the direct process and isolation of the high-boiling residue.

Brinson, Jonathan Ashley (Vale of Glamorgan, GB); Crum, Bruce Robert (Madison, IN); Jarvis, Jr., Robert Frank (Midland, MI)

2000-01-01T23:59:59.000Z

64

Life of Plant Activity Estimates for a Nominal 1000 MWe Pressurized Water Reactor and Boiling Water Reactor  

Science Conference Proceedings (OSTI)

Decommissioning nuclear power plant and disposal site managers must understand the radioactive source term of a nuclear power plant to effectively manage disposition of these materials. This study estimates the radioactive source term from nominal 1000 MWe pressurized water and boiling water reactors to support decisions related to radioactive waste storage, processing, and disposal through decommissioning.BackgroundThis study examines the radionuclide ...

2012-12-05T23:59:59.000Z

65

FEASIBILITY STUDY FOR THE CONCEPTUAL DESIGN OF ADUAL-CORE BOILING SUPERHEAT REACTOR.  

E-Print Network (OSTI)

??For research concerning economical applications of high temperature reactortechnology, a novel approach for creating a Boiling Superheat Reactor (BSR) byaugmenting an Advanced Boiling Water Reactor… (more)

Ross, Jacob

2009-01-01T23:59:59.000Z

66

Exploring the Limits of Boiling and Evaporative Heat Transfer Using Micro/Nano Structures  

E-Print Network (OSTI)

Comparison of various heat transfer coefficient models inpool boiling In summary, high heat transfer coefficientin boiling heat transfer can be generally explained by the

Lu, Ming-Chang

2010-01-01T23:59:59.000Z

67

Analysis of boiling experiment using inverse modeling  

DOE Green Energy (OSTI)

Numerical predictions of geothermal reservoir behavior strongly depend on the assumed steam-water relative permeabilities, which are difficult and time-consuming to measure in the laboratory. This paper describes the esti- mation of the parameters of the relative per- meability and capillary pressure functions by automatically matching simulation results to data from a transient boiling experiment performed on a Berea sandstone. A sensitivity analysis reveals the strong dependence of the observed system behavior on effects such as heat transfer from the heater to the core, as well as heat losses through the insulation. Parameters of three conceptual models were estimated by inverse modeling. Each calibra- tion yields consistent effective steam perme- abilities, but the shape of the liquid relative permeability remains ambiguous.

Finsterle, S.; Guerrero, M.; Satik, C.

1998-05-01T23:59:59.000Z

68

Materials  

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

Materials Materials and methods are available as supplementary materials on Science Online. 16. W. Benz, A. G. W. Cameron, H. J. Melosh, Icarus 81, 113 (1989). 17. S. L. Thompson, H. S. Lauson, Technical Rep. SC-RR-710714, Sandia Nat. Labs (1972). 18. H. J. Melosh, Meteorit. Planet. Sci. 42, 2079 (2007). 19. S. Ida, R. M. Canup, G. R. Stewart, Nature 389, 353 (1997). 20. E. Kokubo, J. Makino, S. Ida, Icarus 148, 419 (2000). 21. M. M. M. Meier, A. Reufer, W. Benz, R. Wieler, Annual Meeting of the Meteoritical Society LXXIV, abstr. 5039 (2011). 22. C. B. Agnor, R. M. Canup, H. F. Levison, Icarus 142, 219 (1999). 23. D. P. O'Brien, A. Morbidelli, H. F. Levison, Icarus 184, 39 (2006). 24. R. M. Canup, Science 307, 546 (2005). 25. J. J. Salmon, R. M. Canup, Lunar Planet. Sci. XLIII, 2540 (2012). Acknowledgments: SPH simulation data are contained in tables S2 to S5 of the supplementary materials. Financial support

69

Material  

DOE Green Energy (OSTI)

Li(Ni{sub 0.4}Co{sub 0.15}Al{sub 0.05}Mn{sub 0.4})O{sub 2} was investigated to understand the effect of replacement of the cobalt by aluminum on the structural and electrochemical properties. In situ X-ray absorption spectroscopy (XAS) was performed, utilizing a novel in situ electrochemical cell, specifically designed for long-term X-ray experiments. The cell was cycled at a moderate rate through a typical Li-ion battery operating voltage range. (1.0-4.7 V) XAS measurements were performed at different states of charge (SOC) during cycling, at the Ni, Co, and the Mn edges, revealing details about the response of the cathode to Li insertion and extraction processes. The extended X-ray absorption fine structure (EXAFS) region of the spectra revealed the changes of bond distance and coordination number of Ni, Co, and Mn absorbers as a function of the SOC of the material. The oxidation states of the transition metals in the system are Ni{sup 2+}, Co{sup 3+}, and Mn{sup 4+} in the as-made material (fully discharged), while during charging the Ni{sup 2+} is oxidized to Ni{sup 4+} through an intermediate stage of Ni{sup 3+}, Co{sup 3+} is oxidized toward Co{sup 4+}, and Mn was found to be electrochemically inactive and remained as Mn{sup 4+}. The EXAFS results during cycling show that the Ni-O changes the most, followed by Co-O, and Mn-O varies the least. These measurements on this cathode material confirmed that the material retains its symmetry and good structural short-range order leading to the superior cycling reported earlier.

Rumble, C.; Conry, T.E.; Doeff, Marca; Cairns, Elton J.; Penner-Hahn, James E.; Deb, Aniruddha

2010-06-14T23:59:59.000Z

70

Effects of Micro/Nano-Scale Surface Characteristics on the Leidenfrost Point Temperature of Water  

E-Print Network (OSTI)

In recent film boiling heat transfer studies with nanofluids, it was reported that deposition of nanoparticles on a surface significantly increases the nominal minimum heat flux (MHF) or Leidenfrost Point (LFP) temperature, ...

Hu, Lin-Wen

71

Fractionally distilled SRC-I, SRC-II, EDS, H-Coal and ITSL direct coal liquefaction process materials: a comparative summary of chemical analysis and biological testing  

DOE Green Energy (OSTI)

This document reports and compares the results compiled from chemical analyses and biological testing of coal liquefaction process materials which were fractionally distilled, after production, into various comparable boiling-point range cuts. Comparative analyses were performed on solvent refined coal (SRC)-I, SRC-II, H-Coal, EDS an integrated two-stage liquefaction (ITSL) distillate materials. Mutagenicity and carcinogenicity assays were conducted in conjunction with chromatographic and mass spectrometric analyses to provide detailed, comparative, chemical and biological assessments. Where possible, results obtained from the distillate cuts are compared to those from coal liquefaction materials with limited boiling ranges. Work reported here was conducted by investigators in the Biology and Chemistry Department at the Pacific Northwest Laboratory (PNL), Richland, WA. 38 refs., 16 figs., 27 tabs.

Wright, C.W.; Later, D.W.; Dauble, D.D.; Wilson, B.W.

1985-07-01T23:59:59.000Z

72

Forced-convection, dispersed-flow film boiling  

E-Print Network (OSTI)

This report presents the latest results of an investigation of the characteristics of dispersed flow film boiling. Heat transfer data are presented for vertical upflow of nitrogen in an electrically heated tube, 0.4 in. ...

Hynek, Scott Josef

1969-01-01T23:59:59.000Z

73

Effects of surface parameters on boiling heat transfer phenomena  

E-Print Network (OSTI)

Nanofluids, engineered colloidal dispersions of nanoparticles in fluid, have been shown to enhance pool and flow boiling CHF. The CHF enhancement was due to nanoparticle deposited on the heater surface, which was verified ...

Truong, Bao H. (Bao Hoai)

2011-01-01T23:59:59.000Z

74

Dryout droplet distribution and dispersed flow film boiling  

E-Print Network (OSTI)

Dispersed flow film boiling is characterized by liquid-phase droplets entrained in a continuous vapor-phase flow. In a previous work at MIT, a model of dispersed flow heat transfer was developed, called the Local Conditions ...

Hill, Wayne S.

1982-01-01T23:59:59.000Z

75

Boiling of nuclear liquid in core-collapse supernova explosions  

E-Print Network (OSTI)

We investigate the possibility of boiling instability of nuclear liquid in the inner core of the proto-neutron star formed in the core collapse of a type II supernova. We derive a simple criterion for boiling to occur. Using this criterion for one of best described equations of state of supernova matter, we find that boiling is quite possible under the conditions realized inside the proto-neutron star. We discuss consequences of this process such as the increase of heat transfer rate and pressure in the boiling region. We expect that taking this effect into account in the conventional neutrino-driven delayed-shock mechanism of type II supernova explosions can increase the explosion energy and reduce the mass of the neutron-star remnant.

Peter Fomin; Dmytro Iakubovskyi; Yuri Shtanov

2007-08-31T23:59:59.000Z

76

Boiling of nuclear liquid in core-collapse supernova explosions  

E-Print Network (OSTI)

We investigate the possibility of boiling instability of nuclear liquid in the inner core of the proto-neutron star formed in the core collapse of a type II supernova. We derive a simple criterion for boiling to occur. Using this criterion for one of best described equations of state of supernova matter, we find that boiling is quite possible under the conditions realized inside the proto-neutron star. We discuss consequences of this process such as the increase of heat transfer rate and pressure in the boiling region. We expect that taking this effect into account in the conventional neutrino-driven delayed-shock mechanism of type II supernova explosions can increase the explosion energy and reduce the mass of the neutron-star remnant.

Fomin, Peter; Shtanov, Yuri

2007-01-01T23:59:59.000Z

77

Enhanced Natural Convection in a Metal Layer Cooled by Boiling Water  

Science Conference Proceedings (OSTI)

An experimental study is performed to investigate the natural convection heat transfer characteristics and the solidification of the molten metal pool concurrently with forced convective boiling of the overlying coolant to simulate a severe accident in a nuclear power plant. The relationship between the Nusselt number (Nu) and the Rayleigh number (Ra) in the molten metal pool region is determined and compared with the correlations in the literature and experimental data with subcooled water. Given the same Ra condition, the present experimental results for Nu of the liquid metal pool with coolant boiling are found to be higher than those predicted by the existing correlations or measured from the experiment with subcooled boiling. To quantify the observed effect of the external cooling on the natural convection heat transfer rate from the molten pool, it is proposed to include an additional dimensionless group characterizing the temperature gradients in the molten pool and in the external coolant region. Starting from the Globe and Dropkin correlation, engineering correlations are developed for the enhancement of heat transfer in the molten metal pool when cooled by an overlying coolant. The new correlations for predicting natural convection heat transfer are applicable to low-Prandtl-number (Pr) materials that are heated from below and solidified by the external coolant above. Results from this study may be used to modify the current model in severe accident analysis codes.

Cho, Jae-Seon [Seoul National University (Korea, Republic of); Suh, Kune Y. [Seoul National University (Korea, Republic of); Chung, Chang-Hyun [Seoul National University (Korea, Republic of); Park, Rae-Joon [Korea Atomic Energy Research Institute (Korea, Republic of); Kim, Sang-Baik [Korea Atomic Energy Research Institute (Korea, Republic of)

2004-12-15T23:59:59.000Z

78

A phenomenological model of the thermal hydraulics of convective boiling during the quenching of hot rod bundles  

SciTech Connect

In this paper, a phenomenological model of the thermal hydraulics of convective boiling in the post-critical-heat-flux (post-CHF) regime is developed and discussed. The model was implemented in the TRAC-PF1/MOD2 computer code (an advanced best-estimate computer program written for the analysis of pressurized water reactor systems). The model was built around the determination of flow regimes downstream of the quench front. The regimes were determined from the flow-regime map suggested by Ishii and his coworkers. Heat transfer in the transition boiling region was formulated as a position-dependent model. The propagation of the CHF point was strongly dependent on the length of the transition boiling region. Wall-to-fluid film boiling heat transfer was considered to consist of two components: first, a wall-to-vapor convective heat-transfer portion and, second, a wall-to-liquid heat transfer representing near-wall effects. Each contribution was considered separately in each of the inverted annular flow (IAF) regimes. The interfacial heat transfer was also formulated as flow-regime dependent. The interfacial drag coefficient model upstream of the CHF point was considered to be similar to flow through a roughened pipe. A free-stream contribution was calculated using Ishii's bubbly flow model for either fully developed subcooled or saturated nucleate boiling. For the drag in the smooth IAF region, a simple smooth-tube correlation for the interfacial friction factor was used. The drag coefficient for the rough-wavy IAF was formulated in the same way as for the smooth IAF model except that the roughness parameter was assumed to be proportional to liquid droplet diameter entrained from the wavy interface. The drag coefficient in the highly dispersed flow regime considered the combined effects of the liquid droplets within the channel and a liquid film on wet unheated walls. 431 refs., 6 figs., 4 tabs.

Nelson, R.A.; Unal, C.

1991-01-01T23:59:59.000Z

79

Thermal Energy Transport in Nanostructured Materials  

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

Thermal Energy Transport in Nanostructured Materials Thermal Energy Transport in Nanostructured Materials Speaker(s): Ravi Prasher Date: August 25, 2008 - 12:00pm Location: 90-3122 Seminar Host/Point of Contact: Ashok Gadgil World energy demand is expected to reach ~30 TW by 2050 from the current demand of ~13 TW. This requires substantial technological innovation. Thermal energy transport and conversion play a very significant role in more than 90% of energy technologies. All four modes of thermal energy transport, conduction, convection, radiation, and phase change (e.g. evaporation/boiling) are important in various energy technologies such as vapor compression power plants, refrigeration, internal combustion engines and building heating/cooling. Similarly thermal transport play a critical role in electronics cooling as the performance and reliability of

80

Confined boiling rates of liquefied petroleum gas on water  

SciTech Connect

Results of a program to measure the rate of boiling of liquefied petroleum gas (LPG) on water surface and to develop an analytical model to describe the phenomena involved are reported. Primary emphasis was placed on liquid propane or LPG mixtures containing small quantities of ethane or butane or both. A few exploratory tests were, however, made with pure liquid ethane, ethylene, and n-butane. The investigation was conducted to provide quantitative data and analytical models to delineate the rate of vaporization, the spread rate and the degree of fractionation, should an LPG tanker suffer an accident leading to a major spill on water. For propane or LPG spills on water, immediately following the contact, violent boiling commenced. Ice quickly formed; in most cases, ice was even thrown onto the sidewalls of the vessel. In some instances sprays of water/ice and propane were ejected from the calorimeter. Within a few seconds, however, the interaction quieted and the surface was covered by a rough ice sheet. The LPG boiled on the surface of this ice, but large gas bubbles occasionally appeared under the ice shield and were trapped. The boiling rate decreased with time with a concomitant increase in the thickness of the ice shield. In the first second or two, very high boiling heat fluxes were experienced. The mass of LPG lost was approximately half that spilled originally. It is estimated that only 5 to 15% could have been ejected as liquid if the water loss is used as a reference. However, since the water surface is very agitated during this period, it is not possible to obtain reliable quantitative values of the boiling flux. Also, as noted, the mass lost in the very early time period was approximately proportional to the original mass of LPG used. It may be inferred that larger spills lead to more mixing and boiling before the ice shield prevents a direct contact between the LPG and the water.

Reid, R.C.; Smith, K.A.

1978-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "boiling point material" 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

Enhanced boiling heat transfer in horizontal test bundles  

Science Conference Proceedings (OSTI)

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

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

1994-08-01T23:59:59.000Z

82

Validation of IVA Computer Code for Flow Boiling Stability Analysis  

SciTech Connect

IVA is a computer code for modeling of transient multiphase, multi-component, non-equilibrium flows in arbitrary geometry including flow boiling in 3D nuclear reactors. This work presents part of the verification procedure of the code. We analyze the stability of flow boiling in natural circulation loop. Experimental results collected on the AREVA/FANP KATHY loop regarding frequencies, mass flows and decay ratio of the oscillations are used for comparison. The comparison demonstrates the capability of the code to successfully simulate such class of processes. (author)

Ivanov Kolev, Nikolay [Framatome-ANP, PO Box 3220, D-91058, Erlangen (Germany)

2006-07-01T23:59:59.000Z

83

Soap Manufacturing TechnologyChapter 9 Semi-Boiled Soap Production Systems  

Science Conference Proceedings (OSTI)

Soap Manufacturing Technology Chapter 9 Semi-Boiled Soap Production Systems Surfactants and Detergents eChapters Surfactants - Detergents Press Downloadable pdf of\tChapter 9 Semi-Boiled Soap Production Systems fr

84

Mechanism and behavior of nucleate boiling heat transfer to the alkalai liquid metals  

E-Print Network (OSTI)

A model of boiling heat transfer to the alkali liquid metals is postulated from an examination of the events and phases of the nucleate boiling cycle. The model includes the important effect of microlayer evaporation which ...

Deane, Charles William

1969-01-01T23:59:59.000Z

85

Forced-convection surface-boiling heat transfer and burnout in tubes of small diameters  

E-Print Network (OSTI)

A basic heat-transfer apparatus was designed and constructed for the study of forced-convection boiling in small channels. The various regions of forced-convection surface boiling were studied experimentally and analytically. ...

Bergles A. E.

1962-01-01T23:59:59.000Z

86

Alumina Nanoparticle Pre-coated Tubing Ehancing Subcooled Flow Boiling Cricital Heat Flux  

E-Print Network (OSTI)

Nanofluids are engineered colloidal dispersions of nano-sized particle in common base fluids. Previous pool boiling studies have shown that nanofluids can improve critical heat flux (CHF) up to 200% for pool boiling and ...

Truong, Bao H.

87

A new approach in signal processing for sodium boiling noise detection by probability density function estimates  

Science Conference Proceedings (OSTI)

The probability density function (pdf) method of noise signal processing has been investigated for its capability and quality in detecting sodium boiling noise. In an attempt to identify proper features of the pdf for sodium boiling noise detection, the segmented areas under the pdf curves have been found sensitive to sodium boiling noise. New approaches have been followed in selecting the feature threshold and achieving the targeted probabilities for false and missed sodium boiling noise detection.

Reddy, C.P.; Singh, O.P.; Vyjayanthi, R.K.; Prabhakar, R.

1988-03-01T23:59:59.000Z

88

Acoustic emission feedback control for control of boiling in a microwave oven  

DOE Patents (OSTI)

An acoustic emission based feedback system for controlling the boiling level of a liquid medium in a microwave oven is provided. The acoustic emissions from the medium correlated with surface boiling is used to generate a feedback control signal proportional to the level of boiling of the medium. This signal is applied to a power controller to automatically and continuoulsly vary the power applied to the oven to control the boiling at a selected level.

White, Terry L. (Oak Ridge, TN)

1991-01-01T23:59:59.000Z

89

Acoustic emission feedback control for control of boiling in a microwave oven  

DOE Patents (OSTI)

An acoustic emission based feedback system for controlling the boiling level of a liquid medium in a microwave oven is provided. The acoustic emissions from the medium correlated with surface boiling is used to generate a feedback control signal proportional to the level of boiling of the medium. This signal is applied to a power controller to automatically and continuously vary the power applied to the oven to control the boiling at a selected level. 2 figs.

White, T.L.

1990-05-02T23:59:59.000Z

90

ADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING  

E-Print Network (OSTI)

The components of a modern Advanced Boiling Water Reactor (ABWR) nuclear power plant are modeled in this thesis) is a single-cycle, forced circulation, light-water nuclear reactor designed by the General Electric Company better control of the nuclear reaction in the fuel core. 2.1 Modifications to the BWR [1] · The reactor

Mitchell, John E.

91

BOILING NUCLEAR SUPERHEATER (BONUS) POWER STATION. Final Summary Design Report  

SciTech Connect

The design and construction of the Boiling Nuclear Superheater (BONUS) Power Station at Punta Higuera on the seacoast at the westernmost tip of Puerto Rico are described. The reactor has an output of 17.5 Mw(e). This report will serve as a source of information for personnel engaged in management, evaluation, and training. (N.W.R.)

1962-05-01T23:59:59.000Z

92

Modeling acid-gas generation from boiling chloride brines  

Science Conference Proceedings (OSTI)

This study investigates the generation of HCl and other acid gases from boiling calcium chloride dominated waters at atmospheric pressure, primarily using numerical modeling. The main focus of this investigation relates to the long-term geologic disposal of nuclear waste at Yucca Mountain, Nevada, where pore waters around waste-emplacement tunnels are expected to undergo boiling and evaporative concentration as a result of the heat released by spent nuclear fuel. Processes that are modeled include boiling of highly concentrated solutions, gas transport, and gas condensation accompanied by the dissociation of acid gases, causing low-pH condensate. Simple calculations are first carried out to evaluate condensate pH as a function of HCl gas fugacity and condensed water fraction for a vapor equilibrated with saturated calcium chloride brine at 50-150 C and 1 bar. The distillation of a calcium-chloride-dominated brine is then simulated with a reactive transport model using a brine composition representative of partially evaporated calcium-rich pore waters at Yucca Mountain. Results show a significant increase in boiling temperature from evaporative concentration, as well as low pH in condensates, particularly for dynamic systems where partial condensation takes place, which result in enrichment of HCl in condensates. These results are in qualitative agreement with experimental data from other studies. The combination of reactive transport with multicomponent brine chemistry to study evaporation, boiling, and the potential for acid gas generation at the proposed Yucca Mountain repository is seen as an improvement relative to previously applied simpler batch evaporation models. This approach allows the evaluation of thermal, hydrological, and chemical (THC) processes in a coupled manner, and modeling of settings much more relevant to actual field conditions than the distillation experiment considered. The actual and modeled distillation experiments do not represent expected conditions in an emplacement drift, but nevertheless illustrate the potential for acid-gas generation at moderate temperatures (<150 C).

Zhang, Guoxiang; Spycher, Nicolas; Sonnenthal, Eric; Steefel, Carl

2009-11-16T23:59:59.000Z

93

Method for controlling boiling point distribution of coal liquefaction oil product  

DOE Patents (OSTI)

The relative ratio of heavy distillate to light distillate produced in a coal liquefaction process is continuously controlled by automatically and continuously controlling the ratio of heavy distillate to light distillate in a liquid solvent used to form the feed slurry to the coal liquefaction zone, and varying the weight ratio of heavy distillate to light distillate in the liquid solvent inversely with respect to the desired weight ratio of heavy distillate to light distillate in the distillate fuel oil product. The concentration of light distillate and heavy distillate in the liquid solvent is controlled by recycling predetermined amounts of light distillate and heavy distillate for admixture with feed coal to the process in accordance with the foregoing relationships. 3 figs.

Anderson, R.P.; Schmalzer, D.K.; Wright, C.H.

1982-12-21T23:59:59.000Z

94

Method for controlling boiling point distribution of coal liquefaction oil product  

SciTech Connect

The relative ratio of heavy distillate to light distillate produced in a coal liquefaction process is continuously controlled by automatically and continuously controlling the ratio of heavy distillate to light distillate in a liquid solvent used to form the feed slurry to the coal liquefaction zone, and varying the weight ratio of heavy distillate to light distillate in the liquid solvent inversely with respect to the desired weight ratio of heavy distillate to light distillate in the distillate fuel oil product. The concentration of light distillate and heavy distillate in the liquid solvent is controlled by recycling predetermined amounts of light distillate and heavy distillate for admixture with feed coal to the process in accordance with the foregoing relationships.

Anderson, Raymond P. (Overland Park, KS); Schmalzer, David K. (Englewood, CO); Wright, Charles H. (Overland Park, KS)

1982-12-21T23:59:59.000Z

95

Talking Points  

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

Talking Points Talking Points NATURAL GAS MARKET INTEGRITY: How EIA Helps Presentation by William F. Hederman Congressional Research Service at EIA 30 th Anniversary Conference April 8, 2008 Washington, DC INTRODUCTION 1. Price levels and volatility cause suspicions. 2. Actual integrity and perceived integrity are both important for markets. 3. EIA was created in response to a crisis of confidence in energy market information. CANDIDATE INTEGRITY CRITERIA 1. Transparency 2. Efficiency (gathering, reporting, monitoring data) v. equity 3. Stability/predictability v. dynamism/volatility 4. Clarity (understanding) "DRAFT" TEN COMMANDMENTS/SUGGESTIONS 1. First presented at World Energy Congress, Rome, Nov. 2007 panel on Energy Market Integrity.

96

Efficiency of a solar collector with internal boiling  

DOE Green Energy (OSTI)

The behavior of a solar collector with a boiling fluid is analyzed to provide a simple algebraic model for future systems simulations, and to provide guidance for testing. The efficiency equation is developed in a form linear in the difference between inlet and saturation (boiling) temperatures, whereas the expression upon which ASHRAE Standard 109P is based utilizes the difference between inlet and ambient temperatures. The coefficient of the revised linear term is a weak function of collector parameters, weather, and subcooling of the working fluid. For a glazed flat-plate collector with metal absorber, the coefficient is effectively constant. Therefore, testing at multiple values of insolation and subcooling, as specified by ASHRAE 109P, should not be necessary for most collectors. The influences of collector properties and operating conditions on efficiency are examined.

Neeper, D.A.

1986-01-01T23:59:59.000Z

97

Efficiency of a solar collector with internal boiling  

DOE Green Energy (OSTI)

The behavior of a solar collector with a boiling fluid is analyzed to provide a simple algebraic model for future systems simulations, and to provide guidance for testing. The efficiency equation is developed in a form linear in the difference between inlet and saturation (boiling) temperatures, whereas the expression upon which ASHRAE Standard 109P is based utilizes the difference between inlet and ambient temperatures. The coefficient of the revised linear term is a week function of collector parameters, weather, and subcooling of the working fluid. For a glazed flat-plate collector with metal absorber, the coefficient is effectively constant. Therefore, testing at multiple values of insolation and subcooling, as specified by ASHRAE 109P, should not be necessary for most collectors. The influences of collector properties and operating conditions on efficiency are examined.

Neeper, D.A.

1986-06-01T23:59:59.000Z

98

Boiling Water Reactor Shutdown Chemistry and Dose Summary: September 2010  

Science Conference Proceedings (OSTI)

This 2010 update provides an annual report of shutdown radiation dose rates at 46 boiling water reactors (BWRs) that participate in the Electric Power Research Institute's (EPRI's) BWR Chemistry Monitoring and Assessment program and supersedes the BWR Radiation Assessment and Control (BRAC) Summary that was issued twice a year. In addition to BRAC dose rates, the report also includes information on operating and shutdown water chemistry and worker outage dose and contamination.

2010-09-23T23:59:59.000Z

99

Fuel Reliability Project: Boiling Water Fuel Performance at Kernkraftwerk Leibstadt  

Science Conference Proceedings (OSTI)

The Kernkraftwerk Leibstadt (KKL) boiling water reactor (BWR), a General Electric BWR/6, performed a lead use assembly (LUA) program with fuel from three fuel suppliers. This program presented a unique opportunity to evaluate fuel performance on advanced 10x10 designs of AREVA, Global Nuclear Fuel (GNF), and Westinghouse Electric Company (Westinghouse). Fuel assemblies from each supplier (vendor) were loaded into the KKL core in 1997 and 1998. A number of fuel inspections have been performed during annua...

2007-05-16T23:59:59.000Z

100

SELF-REGULATING BOILING-WATER NUCLEAR REACTORS  

DOE Patents (OSTI)

A boiling-water reactor was designed which comprises a pressure vessel containing a mass of water, a reactor core submerged within the water, a reflector tank disposed within the reactor, the reflector tank being open at the top to the interior of the pressure vessel, and a surge tank connected to the reflector tank. In operation the reflector level changes as a function of the pressure witoin the reactor so that the reactivity of the reactor is automatically controlled.

Ransohoff, J.A.; Plawchan, J.D.

1960-08-16T23:59:59.000Z

Note: This page contains sample records for the topic "boiling point material" 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

Great Boiling Springs Geothermal Area | Open Energy Information  

Open Energy Info (EERE)

Boiling Springs Geothermal Area Boiling Springs Geothermal Area Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Geothermal Resource Area: Great Boiling Springs Geothermal Area Contents 1 Area Overview 2 History and Infrastructure 3 Regulatory and Environmental Issues 4 Exploration History 5 Well Field Description 6 Geology of the Area 7 Geofluid Geochemistry 8 NEPA-Related Analyses (0) 9 Exploration Activities (0) 10 References Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"TERRAIN","zoom":6,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"500px","height":"300px","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":40.66166667,"lon":-119.3616667,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

102

Dirk Windelberg Nano-point-geometry  

E-Print Network (OSTI)

Dirk Windelberg Nano-point-geometry for use in material science 12. M¨arz 2010, M¨unchen D¨at Hannover #12;D.Windelberg: Nano-point-geometry for use in material science tr1003 e.tex (8. Juli 2010) 1 Nano-point-geometry for use in material science 1 microstructure 2 determination of height of voxels 3

Windelberg, Dirk

103

Investigation of corrosion and stress corrosion cracking in bolting materials on light water reactors  

Science Conference Proceedings (OSTI)

Laboratory experiments performed at BNL have shown that the concentration of boric acid to a moist paste at approximately the boiling point of water can produce corrosion rates of the order of several tenths of an inch per year on bolting and piping materials, which values are consistent with service experience. Other failure evaluation experience has shown that primary coolant/lubricant interaction may lead to stress corrosion cracking (SCC) of steam generator manway studs. An investigation was also performed on eleven lubricants and their effects on A193 B7 and A540 B24 bolting materials. H/sub 2/S generation by the lubricants, coefficient of friction results and transgranular SCC of the bolting materials in steam are discussed. 13 refs.

Czajkowski, C.J.

1985-01-01T23:59:59.000Z

104

THE DETECTION OF BOILING IN A WATER-COOLED NUCLEAR REACTOR  

SciTech Connect

Measurements made at ORNL to study the feasibility of boiling detection in a water-cooled nuclear reactor are described. The methods selected for the detection of boiling include measurement of the acoustical noise produced by the generation of bubbles and measurement of changes in the reactor-power spectral density produced by bubbles. Preliminary results indicating that both methods could detect boiling are shown. (auth)

Colomb, A.L.; Binford, F.T.

1962-08-17T23:59:59.000Z

105

Liquid-vapour phase change : nucleate boiling of pure fluid and nanofluid under different gravity levels.  

E-Print Network (OSTI)

??This research was a step towards the comprehension of the nano-particles interaction with bubbles created during boiling. It was aimed at solving the controversies of… (more)

Diana, Antoine

2014-01-01T23:59:59.000Z

106

The Development of a Non-Equilibrium Dispersed Flow Film Boiling Heat Transfer Modeling Package.  

E-Print Network (OSTI)

??The dispersed flow film boiling (DFFB) heat transfer regime is important to several applications including cryogenics, rocket engines, steam generators, and in the safety analysis… (more)

Meholic, Michael

2011-01-01T23:59:59.000Z

107

Visualization of flow boiling in an annular heat exchanger under reduced gravity conditions.  

E-Print Network (OSTI)

??This work examines the effects of gravitational acceleration on the flow boiling process. A test facility focusing on an annular heat exchanger was designed, built… (more)

Westheimer, David Thomas

2012-01-01T23:59:59.000Z

108

Exploring the Limits of Boiling and Evaporative Heat Transfer Using Micro/Nano Structures.  

E-Print Network (OSTI)

??This dissertation presents a study exploring the limits of phase-change heat transfer with the aim of enhancing critical heat flux (CHF) in pool boiling and… (more)

Lu, Ming-Chang

2010-01-01T23:59:59.000Z

109

DIRECT-CYCLE, BOILING-WATER NUCLEAR REACTOR  

DOE Patents (OSTI)

A direct-cycle boiling-water nuclear reactor is described that employs a closed vessel and a plurality of fuel assemblies, each comprising an outer tube closed at its lower end, an inner tube, fuel rods in the space between the tubes and within the inner tube. A body of water lying within the pressure vessel and outside the fuel assemblies is converted to saturated steam, which enters each fuel assembly at the top and is converted to superheated steam in the fuel assembly while it is passing therethrough first downward through the space between the inner and outer tubes of the fuel assembly and then upward through the inner tube. (AEC)

Harrer, J.M.; Fromm, L.W. Jr.; Kolba, V.M.

1962-08-14T23:59:59.000Z

110

Boiling Water Reactor (BWR) Zinc Injection Strategy Evaluation  

Science Conference Proceedings (OSTI)

All U.S. boiling water reactors (BWRs) inject depleted zinc oxide (DZO) into the reactor feedwater for the purpose of suppressing drywell shutdown radiation dose rates. Current guidance in BWRVIP-190: BWR Vessel and Internals Project, BWR Water Chemistry Guidelines2008 Revision (EPRI report 1016579) is to inject sufficient zinc to achieve a Co-60(s)/Zn(s) ratio of Utility-specific goals may encourage even lower Co-60(s)/Zn(s) levels. This may be in part because BWR e...

2010-11-24T23:59:59.000Z

111

TMS Materials Cyberinfrastructure Portal  

Science Conference Proceedings (OSTI)

The Materials Cyber- infrastructure Portal serves as an online access point to critical tools and resources—including computational models and materials ...

112

Water inventory management in condenser pool of boiling water reactor  

DOE Patents (OSTI)

An improved system for managing the water inventory in the condenser pool of a boiling water reactor has means for raising the level of the upper surface of the condenser pool water without adding water to the isolation pool. A tank filled with water is installed in a chamber of the condenser pool. The water-filled tank contains one or more holes or openings at its lowermost periphery and is connected via piping and a passive-type valve (e.g., squib valve) to a high-pressure gas-charged pneumatic tank of appropriate volume. The valve is normally closed, but can be opened at an appropriate time following a loss-of-coolant accident. When the valve opens, high-pressure gas inside the pneumatic tank is released to flow passively through the piping to pressurize the interior of the water-filled tank. In so doing, the initial water contents of the tank are expelled through the openings, causing the water level in the condenser pool to rise. This increases the volume of water available to be boiled off by heat conducted from the passive containment cooling heat exchangers. 4 figs.

Gluntz, Douglas M. (San Jose, CA)

1996-01-01T23:59:59.000Z

113

Water inventory management in condenser pool of boiling water reactor  

DOE Patents (OSTI)

An improved system for managing the water inventory in the condenser pool of a boiling water reactor has means for raising the level of the upper surface of the condenser pool water without adding water to the isolation pool. A tank filled with water is installed in a chamber of the condenser pool. The water-filled tank contains one or more holes or openings at its lowermost periphery and is connected via piping and a passive-type valve (e.g., squib valve) to a high-pressure gas-charged pneumatic tank of appropriate volume. The valve is normally closed, but can be opened at an appropriate time following a loss-of-coolant accident. When the valve opens, high-pressure gas inside the pneumatic tank is released to flow passively through the piping to pressurize the interior of the water-filled tank. In so doing, the initial water contents of the tank are expelled through the openings, causing the water level in the condenser pool to rise. This increases the volume of water available to be boiled off by heat conducted from the passive containment cooling heat exchangers. 4 figs.

Gluntz, D.M.

1996-03-12T23:59:59.000Z

114

Boiling water neutronic reactor incorporating a process inherent safety design  

DOE Patents (OSTI)

A boiling-water reactor core is positioned within a prestressed concrete reactor vessel of a size which will hold a supply of coolant water sufficient to submerge and cool the reactor core by boiling for a period of at least one week after shutdown. Separate volumes of hot, clean (non-borated) water for cooling during normal operation and cool highly borated water for emergency cooling and reactor shutdown are separated by an insulated wall during normal reactor operation with contact between the two water volumes being maintained at interfaces near the top and bottom ends of the reactor vessel. Means are provided for balancing the pressure of the two volumes at the lower interface zone during normal operation to prevent entry of the cool borated water into the reactor core region, for detecting the onset of excessive power to coolant flow conditions in the reactor core and for detecting low water levels of reactor coolant. Cool borated water is permitted to flow into the reactor core when low reactor coolant levels or excessive power to coolant flow conditions are encountered.

Forsberg, Charles W. (Kingston, TN)

1987-01-01T23:59:59.000Z

115

Boiling water neutronic reactor incorporating a process inherent safety design  

DOE Patents (OSTI)

A boiling-water reactor core is positioned within a prestressed concrete reactor vessel of a size which will hold a supply of coolant water sufficient to submerge and cool the reactor core by boiling for a period of at least one week after shutdown. Separate volumes of hot, clean (nonborated) water for cooling during normal operation and cool highly borated water for emergency cooling and reactor shutdown are separated by an insulated wall during normal reactor operation with contact between the two water volumes being maintained at interfaces near the top and bottom ends of the reactor vessel. Means are provided for balancing the pressure of the two water volumes at the lower interface zone during normal operation to prevent entry of the cool borated water into the reactor core region, for detecting the onset of excessive power to coolant flow conditions in the reactor core and for detecting low water levels of reactor coolant. Cool borated water is permitted to flow into the reactor core when low reactor coolant levels or excessive power to coolant flow conditions are encountered.

Forsberg, C.W.

1985-02-19T23:59:59.000Z

116

Effect of surface conditions on boiling heat transfer of refrigerants in shell-and-tube evaporators  

Science Conference Proceedings (OSTI)

Experimental results are presented for the boiling heat transfer performance of R 22 and R 717 on surfaces with porous metallized coatings. A calculational-theoretical model is given for predicting the heat transfer of refrigerants boiling on a bundle of finned tubes.

Danilova, G.N.; Dyundin, V.A.; Borishanskaya, A.V.; Soloviyov, A.G.; Vol'nykh, Y.A.; Kozyrev, A.A.

1990-01-01T23:59:59.000Z

117

Boiling heat transfer in a hydrofoil-based micro pin fin heat sink  

E-Print Network (OSTI)

-flow boiling over circular tube bundles has been meticulously studied; collected data and correlations for circular tube bundles. For exam- ple, Jensen and Hsu [81] conducted a parametric study of boiling heat transfer in a horizontal tube bundle and reported an increase in local heat transfer coefficient

Peles, Yoav

118

Numerical study of high heat ux pool boiling heat transfer Ying He a,*, Masahiro Shoji b  

E-Print Network (OSTI)

in saturated pool boiling. In this model the analysis of heat conduction within the heater is added on the heater surface itself [10]. Bhat et al. [11] put forward a theoretical model of macrolayer formation to their model and ob- tained the simulated boiling curve of water. In addition, they compared Haramura and Katto

Maruyama, Shigeo

119

BOILING WATER REACTOR WITH FEED WATER INJECTION NOZZLES  

DOE Patents (OSTI)

This patent covers the use of injection nozzles for pumping water into the lower ends of reactor fuel tubes in which water is converted directly to steam. Pumping water through fuel tubes of this type of boiling water reactor increases its power. The injection nozzles decrease the size of pump needed, because the pump handles only the water going through the nozzles, additional water being sucked into the tubes by the nozzles independently of the pump from the exterior body of water in which the fuel tubes are immersed. The resulting movement of exterior water along the tubes holds down steam formation, and thus maintains the moderator effectiveness, of the exterior body of water. (AEC)

Treshow, M.

1963-04-30T23:59:59.000Z

120

Experimental & Numerical Investigation of Pool Boiling on Engineered Surfaces with Integrated Thin-flim Temperature Sensors  

E-Print Network (OSTI)

The objective of this investigation is to measure and analyze surface temperature fluctuations in pool boiling. The surface temperature fluctuations were recorded on silicon surfaces with and without multi-walled carbon nanotubes (MWCNT). Novel Thin Film Thermocouples (TFT) are micro-fabricated on test substrates to measure surface temperatures. A dielectric liquid refrigerant (PF-5060) is used as test fluid. Both nucleate and lm boiling regimes are investigated for the silicon test substrates. Dynamics of nucleate boiling is investigated on the CNT coated substrates. High frequency temperature fluctuation data is analyzed for the presence of determinism using non-linear time series analysis techniques in TISEAN(copyright) software. The impact of subcooling and micro/nano-scale surface texturing using MWCNT coatings on the dynamics of pool boiling is assessed. Dynamic invariants such as correlation dimensions and Lyapunov spectrum are evaluated for the reconstructed attractor. A non-linear noise reduction scheme is employed to reduce the level of noise in the data. Previous investigations in pool boiling chaos, reported in literature were based on temperature measurements underneath the test surface consisting of single or few active nucleation sites. Previous studies have indicated the presence of low-dimensional behavior in nucleate boiling and high-dimensional behavior in CHF and film boiling. Currently, there is no study detailing the effects of multiple nucleation sites, subcooling and surface texturing on pool boiling dynamics. The investigation comprises of four parts: i) in situ micro-machining of Chromelalumel (K-type) TFT, ii) calibration of these sensors, iii) utilizing these sensors in pool boiling experiments iv) analysis of these fluctuations using techniques of nonlinear time series analysis. Ten TFT are fabricated on a rectangular silicon surface within an area of ~ 3.00 cm x 3.00 cm. The sensing junctions of the TFT measure 50 mm in width and 250 nm in depth. Surface temperature fluctuations of the order of i) 0.65-0.93 degrees C are observed near ONB ii) 2.3-6.5 degrees C in FDNB iii) 2.60-5.00 degrees C at CHF and iv) 2.3-3.5 degrees C in film boiling. Investigations show the possible presence of chaotic dynamics near CHF and in film-boiling in saturated and subcooled pool boiling. Fully-developed nucleate boiling (FDNB) is chaotic. No clear assessment of the dynamics could be made in the onset of nucleate boiling (ONB) and partial nucleate boiling (PNB) regimes due to the effects of noise. However, the frequency spectra in these regimes appear to have two independent frequencies and their integral combinations indicating a possible quasiperiodic bifurcation route to chaos. The dimensionality in FDNB, at CHF and in film-boiling is lower in saturated pool boiling as compared to values in corresponding regimes in subcooled pool boiling. Surface temperature fluctuations can damage electronic components and need to be carefully controlled. Understanding the nature of these fluctuations will aid in deciding the modeling approach for surface temperature transients on an electronic chip. Subsequently, the TFT signals can be employed in a suitable feedback control loop to prevent the occurrence of hotspots.

Sathyamurthi, Vijaykumar

2009-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "boiling point material" 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

Fission reactors and materials  

SciTech Connect

The American-designed boiling water reactor and pressurized water reactor dominate the designs currently in use and under construction worldwide. As in all energy systems, materials problems have appeared during service; these include stress-corrosion of stainless steel pipes and heat exchangers and questions regarding crack behavior in pressure vessels. To obtain the maximum potential energy from our limited uranium supplies is is essential to develop the fast breeder reactor. The materials in these reactors are subjected to higher temperatures and neutron fluxes but lower pressures than in the water reactors. The performance required of the fuel elements is more arduous in the breeder than in water reactors. Extensive materials programs are in progress in test reactors and in large test rigs to ensure that materials will be available to meet these conditions.

Frost, B.R.T.

1981-12-01T23:59:59.000Z

122

Study of plutonium disposition using existing GE advanced Boiling Water Reactors  

SciTech Connect

The end of the cold war and the resulting dismantlement of nuclear weapons has resulted in the need for the US to dispose of 50 to 100 metric tons of excess of plutonium in a safe and proliferation resistant manner. A number of studies, including the recently released National Academy of Sciences (NAS) study, have recommended conversion of plutonium into spent nuclear fuel with its high radiation barrier as the best means of providing permanent conversion and long-term diversion resistance to this material. The NAS study ``Management and Disposition of Excess Weapons Plutonium identified Light Water Reactor spent fuel as the most readily achievable and proven form for the disposition of excess weapons plutonium. The study also stressed the need for a US disposition program which would enhance the prospects for a timely reciprocal program agreement with Russia. This summary provides the key findings of a GE study where plutonium is converted into Mixed Oxide (MOX) fuel and a typical 1155 MWe GE Boiling Water Reactor (BWR) is utilized to convert the plutonium to spent fuel. A companion study of the Advanced BWR has recently been submitted. The MOX core design work that was conducted for the ABWR enabled GE to apply comparable fuel design concepts and consequently achieve full MOX core loading which optimize plutonium throughput for existing BWRs.

Not Available

1994-06-01T23:59:59.000Z

123

FUNDAMENTAL INVESTIGATION OF BOILING HEAT TRANSFER AND TWO-PHASE FLOW  

SciTech Connect

Significantly improved theories of two-phase heat transfer and prediction of departure from nucleate boiling have recently been developed which for the first time are not based on empirical relationships. These theories should be critically analyzed in relation to naval reactor work and tested with all existing data from both classified and unclassified sources. Conflicting analyses of two-phase fluid fiow regimes confuse this area, and essentially no data or theories are avsilable for twophase fiow with superimposed boiling. Theories and understanding of two-phase flow with boiling should be developed, starting from proven theories without boiling, and tested against all existing data or new data as necessary. A substantial start hss been made in analysis of the case of upward annular two-phase flow in vertical channels, based upon modern knowledge of boundary layer and vapor condensation principles. (auth)

Grohse, E.W.; Mueller, G.O.; Findlay, J.A.

1958-10-17T23:59:59.000Z

124

Prediction of departure from nucleate boiling in PWR fast power transients  

E-Print Network (OSTI)

An assessment is conducted of the differences in predicted results between use of steady state versus transient Departure from Nucleate Boiling (DNB) models, for fast power transients under forced convective heat exchange ...

Lenci, Giancarlo

2013-01-01T23:59:59.000Z

125

1514 JOURNAL OF MICROELECTROMECHANICAL SYSTEMS, VOL. 15, NO. 6, DECEMBER 2006 Bubble Dynamics During Boiling in  

E-Print Network (OSTI)

. At lower heat fluxes the void fraction increase is insufficient to change the flow pattern to annular, and P. Mercier, "Experimental investigations on boiling of n-pentane across a horizontal tube bundle

Peles, Yoav

126

Evaluation of the economic simplified boiling water reactor human reliability analysis using the SHARP framework  

E-Print Network (OSTI)

General Electric plans to complete a design certification document for the Economic Simplified Boiling Water Reactor to have the new reactor design certified by the United States Nuclear Regulatory Commission. As part of ...

Dawson, Phillip Eng

2007-01-01T23:59:59.000Z

127

Development of a model to predict flow oscillations in low-flow sodium boiling  

E-Print Network (OSTI)

An experimental and analytical program has been carried out in order to better understand the cause and effect of flow oscillations in boiling sodium systems. These oscillations have been noted in previous experiments with ...

Levin, Alan Edward

1980-01-01T23:59:59.000Z

128

Stability analysis of the boiling water reactor : methods and advanced designs  

E-Print Network (OSTI)

Density Wave Oscillations (DWOs) are known to be possible when a coolant undergoes considerable density reduction while passing through a heated channel. In the development of boiling water reactors (BWRs), there has been ...

Hu, Rui, Ph. D. Massachusetts Institute of Technology

2010-01-01T23:59:59.000Z

129

Conceptual design of an annular-fueled superheat boiling water reactor  

E-Print Network (OSTI)

The conceptual design of an annular-fueled superheat boiling water reactor (ASBWR) is outlined. The proposed design, ASBWR, combines the boiler and superheater regions into one fuel assembly. This ensures good neutron ...

Ko, Yu-Chih, Ph. D. Massachusetts Institute of Technology

2011-01-01T23:59:59.000Z

130

Bubble behavior in subcooled flow boiling on surfaces of variable wettability  

E-Print Network (OSTI)

Flow boiling is important in energy conversion and thermal management due to its potential for very high heat fluxes. By improving understanding of the conditions leading to bubble departure, surfaces can be designed that ...

Tow, Emily W

2012-01-01T23:59:59.000Z

131

Film boiling of saturated liquid flowing upward through a heated tube : high vapor quality range  

E-Print Network (OSTI)

Film boiling of saturated liquid flowing upward through a uniformly heated tube has been studied for the case in which pure saturated liquid enters the tube and nearly saturated vapor is discharged. Since a previous study ...

Laverty, W. F.

1964-01-01T23:59:59.000Z

132

Boiling-Water Reactor internals aging degradation study. Phase 1  

SciTech Connect

This report documents the results of an aging assessment study for boiling water reactor (BWR) internals. Major stressors for BWR internals are related to unsteady hydrodynamic forces generated by the primary coolant flow in the reactor vessel. Welding and cold-working, dissolved oxygen and impurities in the coolant, applied loads and exposures to fast neutron fluxes are other important stressors. Based on results of a component failure information survey, stress corrosion cracking (SCC) and fatigue are identified as the two major aging-related degradation mechanisms for BWR internals. Significant reported failures include SCC in jet-pump holddown beams, in-core neutron flux monitor dry tubes and core spray spargers. Fatigue failures were detected in feedwater spargers. The implementation of a plant Hydrogen Water Chemistry (HWC) program is considered as a promising method for controlling SCC problems in BWR. More operating data are needed to evaluate its effectiveness for internal components. Long-term fast neutron irradiation effects and high-cycle fatigue in a corrosive environment are uncertainty factors in the aging assessment process. BWR internals are examined by visual inspections and the method is access limited. The presence of a large water gap and an absence of ex-core neutron flux monitors may handicap the use of advanced inspection methods, such as neutron noise vibration measurements, for BWR.

Luk, K.H. [Oak Ridge National Lab., TN (United States)

1993-09-01T23:59:59.000Z

133

PowerPoint Presentation  

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

Market Monitoring Market Monitoring Tools Bernie Lesieutre - LBNL Bob Thomas - Cornell October 18, 2006 Washington, D.C. OE Visualization and Controls Peer Review Market Monitoring Tools: Overview Approach: Use dispatch, profit, revenue/offer price, withholding sensitivities to identify opportunities for local advantage that give some participants market power potential. 2006 Technical Work: Extend prior results to large, RTO-scale systems. Initiate large-scale analysis with RTO (PJM). Evaluate reactive power effects on energy markets. Publication and presentation of results. Market Power: Substitutability Market power boils down to the issue of substitutability Locational Advantage: "Load Pockets" Physical network constraints limit supply to certain loads, so that the incremental demand

134

Technical Basis for Water Chemistry Control of IGSCC in Boiling ...  

Science Conference Proceedings (OSTI)

... Degradation of Materials in Nuclear Power Systems – Water Reactors ... However, even the utilization of near theoretical conductivity water cannot prevent ...

135

Modeling acid-gas generation from boiling chloride brines  

E-Print Network (OSTI)

first drop" of condensate from superheated geothermal steam.from the steam flowing above the condensate. Incompletecondensate that forms at dew-point temperature through expansion of superheated geothermal steam,

Zhang, Guoxiang

2010-01-01T23:59:59.000Z

136

Study of plutonium disposition using the GE Advanced Boiling Water Reactor (ABWR)  

SciTech Connect

The end of the cold war and the resulting dismantlement of nuclear weapons has resulted in the need for the U.S. to disposition 50 to 100 metric tons of excess of plutonium in parallel with a similar program in Russia. A number of studies, including the recently released National Academy of Sciences (NAS) study, have recommended conversion of plutonium into spent nuclear fuel with its high radiation barrier as the best means of providing long-term diversion resistance to this material. The NAS study {open_quotes}Management and Disposition of Excess Weapons Plutonium{close_quotes} identified light water reactor spent fuel as the most readily achievable and proven form for the disposition of excess weapons plutonium. The study also stressed the need for a U.S. disposition program which would enhance the prospects for a timely reciprocal program agreement with Russia. This summary provides the key findings of a GE study where plutonium is converted into Mixed Oxide (MOX) fuel and a 1350 MWe GE Advanced Boiling Water Reactor (ABWR) is utilized to convert the plutonium to spent fuel. The ABWR represents the integration of over 30 years of experience gained worldwide in the design, construction and operation of BWRs. It incorporates advanced features to enhance reliability and safety, minimize waste and reduce worker exposure. For example, the core is never uncovered nor is any operator action required for 72 hours after any design basis accident. Phase 1 of this study was documented in a GE report dated May 13, 1993. DOE`s Phase 1 evaluations cited the ABWR as a proven technical approach for the disposition of plutonium. This Phase 2 study addresses specific areas which the DOE authorized as appropriate for more in-depth evaluations. A separate report addresses the findings relative to the use of existing BWRs to achieve the same goal.

NONE

1994-04-30T23:59:59.000Z

137

TEMperature Pressure ESTimation of a homogeneous boiling fuel-steel mixture in an LMFBR core. [TEMPEST code  

SciTech Connect

The paper describes TEMPEST, a simple computer program for the temperature and pressure estimation of a boiling fuel-steel pool in an LMFBR core. The time scale of interest of this program is large, of the order of ten seconds. Further, the vigorous boiling in the pool will generate a large contact, and hence a large heat transfer between fuel and steel. The pool is assumed to be a uniform mixture of fuel and steel, and consequently vapor production is also assumed to be uniform throughout the pool. The pool is allowed to expand in volume if there is steel melting at the walls. In this program, the total mass of liquid and vapor fuel is always kept constant, but the total steel mass in the pool may change by steel wall melting. Because of a lack of clear understanding of the physical phenomena associated with the progression of a fuel-steel mixture at high temperature, various input options have been built-in to enable one to perform parametric studies. For example, the heat transfer from the pool to the surrounding steel structure may be controlled by input values for the heat transfer coefficients, or, the heat transfer may be calculated by a correlation obtained from the literature. Similarly, condensation of vapor on the top wall can be specified by input values of the condensation coefficient; the program can otherwise calculate condensation according to the non-equilibrium model predictions. Meltthrough rates of the surrounding steel walls can be specified by a fixed melt-rate or can be determined by a fraction of the heat loss that goes to steel-melting. The melted steel is raised to the pool temperature before it is joined with the pool material. Several applications of this program to various fuel-steel pools in the FFTF and the CRBR cores are discussed.

Pyun, J.J.; Majumdar, D.

1976-11-01T23:59:59.000Z

138

Cool! Nanoparticle Research Points to Energy Savings  

Science Conference Proceedings (OSTI)

... The double-bubble effect enhances boiling heat transfer and, ultimately, could help to boost the energy efficiency of industrial-sized cooling systems ...

2011-05-02T23:59:59.000Z

139

Design and Testing of Vacuum Breaker Check Valve for Simplified Boiling Water Reactor  

Science Conference Proceedings (OSTI)

A new design of the vacuum breaker check valve was developed to replace the mechanical valve in a simplified boiling water reactor. Scaling and design calculations were performed to obtain the geometry of new passive hydraulic vacuum breaker check valve. In order to check the valve performance, a RELAP5 model of the simplified boiling water reactor system with the new valve was developed. The valve was implemented in an integral facility, PUMA and was tested for large break loss of coolant accident. (authors)

Ishii, M.; Xu, Y.; Revankar, S.T. [Purdue University, West Lafayette, IN 47907 (United States)

2002-07-01T23:59:59.000Z

140

Apparatus to measure liquid helium boil-off from low-loss superconducting current leads  

DOE Green Energy (OSTI)

A low-loss liquid helium dewar was constructed to measure the liquid helium boil-off rate from high-temperature superconducting current leads. The dewar has a measured background heat leakage rate of 12 mW. Equations calculating the heat leakage rate from the measured vapor mass flow rate in liquid helium boil-off experiments are derived. Parameters that affect the experiments, such as density ratio, absolute pressure, and rate of pressure variation, are discussed. This study is important as superconducting current leads may be used in superconducting magnetic energy storage systems.

Cha, Y.S.; Niemann, R.C.; Hull, J.R. [Argonne National Lab., IL (United States). Energy Technology Div.

1995-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "boiling point material" 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

Analysis and Measurement of Bubble Dynamics and Associated Flow Field in Subcooled Nucleate Boiling Flows  

SciTech Connect

In recent years, subooled nucleate boiling (SNB) has attrcted expanding research interest owing to the emergence of axial offset anomaly (AOA) or crud-induced power shigt (CIPS) in many operating US PWRs, which is an unexpected deviation in the core axial power distribution from the predicted power curves. Research indicates that the formation of the crud, which directly leads to AOA phenomena, results from the presence of the subcooled nucleate boiling, and is especially realted to bubble motion occurring in the core region.

Barclay G. Jones

2008-10-01T23:59:59.000Z

142

Boiling and condensation processes in the Cerro Prieto beta reservoir under exploitation  

DOE Green Energy (OSTI)

The deep Cerro Prieto (Baja California, Mexico) beta reservoir is offset vertically by the southwest-northeast trending, normal H fault. Under exploitation pressures in the upthrown block have decreased strongly resulting in boiling and high-enthalpy production fluids. Significant differences in fluid chemical and isotopic compositions are observed in the two parts of the reservoir and particularly in an anomalous zone associated with the H fault. These differences result from intense boiling and adiabatic steam condensation, as well as from leakage of overlying cooler water along the fault.

Truesdell, A. (Truesdell (Alfred), Menlo Park, CA (United States)); Manon, A.; Quijano, L. (Comision Federal de Electricidad, Morelia (Mexico)); Coplen, T. (Geological Survey, Reston, VA (United States)); Lippmann, M. (Lawrence Berkeley Lab., CA (United States))

1992-01-01T23:59:59.000Z

143

Program on Technology Innovation: EPRI Materials Management Matrix (MMM) Project  

Science Conference Proceedings (OSTI)

The Economic Simplified Boiling Water Reactor (ESBWR) Risk Priority Evaluation is the third activity supporting development of the ESBWR Materials Management Matrix (MMM). The first phase involved developing a list of in-scope components and materials of construction. The second phase focused on development of an ESBWR-specific Degradation Matrix (DM), which supplies important input into the Risk Priority Evaluation process documented in this report, and can help in understanding the opinions of material...

2008-03-24T23:59:59.000Z

144

Identification of Boiling Two-phase Flow Patterns in Water Wall Tube Based on BP Neural Network  

Science Conference Proceedings (OSTI)

In this paper, the boiling phenomena of steam boiler under atmospheric pressure are simulated by using the UDF program of CFD software. Characteristics including pressure, temperature and vapor fraction respectively for bubble, slug and annular flow ... Keywords: Boiling heat transfer, BP neural network, flow pattern, coefficient of heat transfer

Lei Guo; Shusheng Zhang; Yaqun Chen; Lin Cheng

2010-06-01T23:59:59.000Z

145

Preliminary Feasibility, Design, and Hazard Analysis of a Boiling Water Test Loop Within the Idaho National Laboratory Advanced Test Reactor National Scientific User Facility  

Science Conference Proceedings (OSTI)

The Advanced Test Reactor (ATR) is a pressurized light-water reactor with a design thermal power of 250 MW. The principal function of the ATR is to provide a high neutron flux for testing reactor fuels and other materials. The ATR and its support facilities are located at the Idaho National Laboratory (INL). A Boiling Water Test Loop (BWTL) is being designed for one of the irradiation test positions within the. The objective of the new loop will be to simulate boiling water reactor (BWR) conditions to support clad corrosion and related reactor material testing. Further it will accommodate power ramping tests of candidate high burn-up fuels and fuel pins/rods for the commercial BWR utilities. The BWTL will be much like the pressurized water loops already in service in 5 of the 9 “flux traps” (region of enhanced neutron flux) in the ATR. The loop coolant will be isolated from the primary coolant system so that the loop’s temperature, pressure, flow rate, and water chemistry can be independently controlled. This paper presents the proposed general design of the in-core and auxiliary BWTL systems; the preliminary results of the neutronics and thermal hydraulics analyses; and the preliminary hazard analysis for safe normal and transient BWTL and ATR operation.

Douglas M. Gerstner

2009-05-01T23:59:59.000Z

146

Co-gasification of municipal solid waste and material recovery in a large-scale gasification and melting system  

Science Conference Proceedings (OSTI)

Highlights: Black-Right-Pointing-Pointer This study evaluates the effects of co-gasification of MSW with MSW bottom ash. Black-Right-Pointing-Pointer No significant difference between MSW treatment with and without MSW bottom ash. Black-Right-Pointing-Pointer PCDD/DFs yields are significantly low because of the high carbon conversion ratio. Black-Right-Pointing-Pointer Slag quality is significantly stable and slag contains few hazardous heavy metals. Black-Right-Pointing-Pointer The final landfill amount is reduced and materials are recovered by DMS process. - Abstract: This study evaluates the effects of co-gasification of municipal solid waste with and without the municipal solid waste bottom ash using two large-scale commercial operation plants. From the viewpoint of operation data, there is no significant difference between municipal solid waste treatment with and without the bottom ash. The carbon conversion ratios are as high as 91.7% and 95.3%, respectively and this leads to significantly low PCDD/DFs yields via complete syngas combustion. The gross power generation efficiencies are 18.9% with the bottom ash and 23.0% without municipal solid waste bottom ash, respectively. The effects of the equivalence ratio are also evaluated. With the equivalence ratio increasing, carbon monoxide concentration is decreased, and carbon dioxide and the syngas temperature (top gas temperature) are increased. The carbon conversion ratio is also increased. These tendencies are seen in both modes. Co-gasification using the gasification and melting system (Direct Melting System) has a possibility to recover materials effectively. More than 90% of chlorine is distributed in fly ash. Low-boiling-point heavy metals, such as lead and zinc, are distributed in fly ash at rates of 95.2% and 92.0%, respectively. Most of high-boiling-point heavy metals, such as iron and copper, are distributed in metal. It is also clarified that slag is stable and contains few harmful heavy metals such as lead. Compared with the conventional waste management framework, 85% of the final landfill amount reduction is achieved by co-gasification of municipal solid waste with bottom ash and incombustible residues. These results indicate that the combined production of slag with co-gasification of municipal solid waste with the bottom ash constitutes an ideal approach to environmental conservation and resource recycling.

Tanigaki, Nobuhiro, E-mail: tanigaki.nobuhiro@nsc-eng.co.jp [Nippon Steel Engineering Co., Ltd. (Head Office), Osaki Center Building 1-5-1, Osaki, Shinagawa-ku, Tokyo 141-8604 (Japan); Manako, Kazutaka [Nippon Steel Engineering Co., Ltd., 46-59, Nakabaru, Tobata-ku, Kitakyushu, Fukuoka 804-8505 (Japan); Osada, Morihiro [Nippon Steel Engineering Co., Ltd. (Head Office), Osaki Center Building 1-5-1, Osaki, Shinagawa-ku, Tokyo 141-8604 (Japan)

2012-04-15T23:59:59.000Z

147

PowerPoint Presentation  

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

Energy Materials Energy Materials Advanced Energy Materials Condensed Matter Physics and Materials Science Department, Brookhaven National Laboratory A bird's eye view is provided of superconducting and thermoelectric materials research at the Advanced Energy Materials Group*. We study both the microscopic and macroscopic properties of complex and nano-structured materials and develop their application in energy related technologies. Abstract Abstract Abstract are capable of carrying electrical current without loss, and hence offer powerful opportunities for increasing the capacity and efficiency of the power grid. The superconducting materials program at BNL studies the basic relationships between structure and properties of superconductors to provide understanding of fundamental materials science and physics

148

Minimizing corrosion in coal liquid distillation  

DOE Patents (OSTI)

In an atmospheric distillation tower of a coal liquefaction process, tower materials corrosion is reduced or eliminated by introduction of boiling point differentiated streams to boiling point differentiated tower regions.

Baumert, Kenneth L. (Emmaus, PA); Sagues, Alberto A. (Lexington, KY); Davis, Burtron H. (Georgetown, KY)

1985-01-01T23:59:59.000Z

149

Appendix B - Control Points  

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

B B Control Points B.1 Injector Control Points Qty Type Device 2 Magnet Bend magnet - DL1 bend 9 Magnet Quad magnet 10 Magnet X-Y Corrector Pair 2 Magnet Solenoid 2 Magnet...

150

Performance Evaluation of Advanced LLW Liquid Processing Technology: Boiling Water Reactor Liquid Processing  

Science Conference Proceedings (OSTI)

This report provides condensed information on boiling water reactor (BWR) membrane based liquid radwaste processing systems. The report presents specific details of the technology, including design, configuration, and performance. This information provides nuclear plant personnel with data useful in evaluating the merits of applying advanced processes at their plant.

2001-11-26T23:59:59.000Z

151

DEUTERIUM-HYDROGEN EXCHANGE IN BOEHMITE CORROSION PRODUCT FORMED ON PURE ALUMINUM IN BOILING WATER  

SciTech Connect

Proton-deuteron exchange is rapid in boehmite corrosion product formed on pure aluminum in boiling water. In addition, deuterated boehmite films undergo rapid exchange with the humidity of the atmosphere. This explains the previously reported anomaly in the H-D exchange rate for the growing corrosion product on 1100 aluminum. (auh)

Mori, S.; Draley, J.E.; Bernstein, R.B.

1961-10-31T23:59:59.000Z

152

NUMERICAL SIMULATION OF POOL BOILING FOR STEADY STATE AND TRANSIENT HEATING  

E-Print Network (OSTI)

boiling. The developed model includes the analysis of heat conduction within the heater coupled-dimensional transient heat conduction within the heater coupled with the macrolayer model was considered. Being employed-averaged model from experimental measurements of void fraction close to the heater surface. In the model

Maruyama, Shigeo

153

Simulation of subcooled boiling at low pressure conditions with RELAP5-3D computer program  

E-Print Network (OSTI)

Simulation of subcooled boiling was carried out using RELAP5 thermal hydraulic computer programs. Both one-dimensional and three-dimensional analyses were carried out with one-dimensional RELAP5/MOD3.2 and three-dimensional RELAP5-3D code. Experimental data from the subcooled boiling experiment at low pressure conditions of Bartel, and Zeitoun and Shoukri were simulated. The RELAP5/MOD3.2 was executed to determine the axial void faction distribution. The predictions of void fraction distributions at low-pressure conditions were underestimated. The same model was used to simulate high pressure subcooled boiling data. High pressure subcooled boiling experiments of Bartolomey and Sabotinov were simulated. The axial void fraction distribution results of RELAP5/MOD3.2 were in a good agreement with the experimental data. Two sets of both Bartel's and Zeitoun and Shoukri's experiments were chosen for three-dimensional simulation. Three-dimensional input model resembling the annular test section was constructed. The simulation results using RELAP5-3D program achieved a good agreement with low and high-pressure experimental data. Sensitivity study, with various nodalization schemes, was performed to obtain the optimum simulation parameters.

Reza, S.M. Mohsin

2002-01-01T23:59:59.000Z

154

Advanced Power Plant Modeling with Applications to an Advanced Boiling Water  

E-Print Network (OSTI)

wave fronts. However, in most power plant transient performance models, there are few heat exchangersAdvanced Power Plant Modeling with Applications to an Advanced Boiling Water Reactor and a Heat Introduction This paper presents two advanced modeling methods, and two applications, for power plant

Mitchell, John E.

155

Technical and economic analysis of the thermal performance of a solar boiling concentrator for power generation  

SciTech Connect

A system for power generation using solar energy collected by compound parabolic concentrators (CPC) incorporated into a Rankine cycle system is studied by developing a model to simulate the CPC performance. The power cycle is also modeled under quasi-steady and transient conditions. An economic analysis is performed through a model developed to study the economic viability of the power system. The CPC performance is sensitive to the ratio of diffuse to beam components of the solar incident irradiation. This ratio, along with the concentration ratio, govern the CPC optical efficiency which in turn determine the thermal efficiency. The performance of the CPC working under boiling and superheating conditions is governed by the axial fractional lengths of the non-boiling and the superheating regions. The overall thermal loss coefficient is formulated as a function of the local thermal loss coefficient in the different regions and the length of each region. The thermal efficiency of CPC's and flat plates, whether under non-boiling, boiling or superheating conditions, is evaluated. The CPC working under superheating conditions has a good potential for solar powered Rankine cycles. System efficiencies as high as 11.3% could be obtained at R-11 evaporation temperature of 120/sup 0/C and a condensation temperature of 20/sup 0/ C.

El-Assy, A.Y.

1985-01-01T23:59:59.000Z

156

Nondestructive Evaluation: Boiling Water Reactor Bottom Head Drain Line Examination - Field Trial  

Science Conference Proceedings (OSTI)

This report describes newly developed technology for the examination of the boiling water reactor (BWR) vessel drain line. The technology targets the examination of the elbow and piping section deemed most susceptible to flow-accelerated corrosion (FAC) attack. The technology developed includes a remotely operated sensor manipulator and an ultrasound data acquisition system to perform thickness measurements throughout the affected components.

2007-12-12T23:59:59.000Z

157

Semantic point detector  

Science Conference Proceedings (OSTI)

Local features are the building blocks of many visual systems, and local point detector is usually the first component for local feature extraction. Existing local point detector are designed with target for matching and it may not perform well when ... Keywords: semantic point detector

Kuiyuan Yang; Lei Zhang; Meng Wang; Hong-Jiang Zhang

2011-11-01T23:59:59.000Z

158

Study of Pu consumption in Advanced Light Water Reactors. Evaluation of GE Advanced Boiling Water Reactor plants  

SciTech Connect

Timely disposal of the weapons plutonium is of paramount importance to permanently safeguarding this material. GE`s 1300 MWe Advanced Boiling Water Reactor (ABWR) has been designed to utilize fill] core loading of mixed uranium-plutonium oxide fuel. Because of its large core size, a single ABWR reactor is capable of disposing 100 metric tons of plutonium within 15 years of project inception in the spiking mode. The same amount of material could be disposed of in 25 years after the start of the project as spent fuel, again using a single reactor, while operating at 75 percent capacity factor. In either case, the design permits reuse of the stored spent fuel assemblies for electrical energy generation for the remaining life of the plant for another 40 years. Up to 40 percent of the initial plutonium can also be completely destroyed using ABWRS, without reprocessing, either by utilizing six ABWRs over 25 years or by expanding the disposition time to 60 years, the design life of the plants and using two ABWRS. More complete destruction would require the development and testing of a plutonium-base fuel with a non-fertile matrix for an ABWR or use of an Advanced Liquid Metal Reactor (ALMR). The ABWR, in addition, is fully capable of meeting the tritium target production goals with already developed target technology.

Not Available

1993-05-13T23:59:59.000Z

159

PowerPoint Presentation  

National Nuclear Security Administration (NNSA)

uranium >10% enriched, are to report all source material shipments, receipts, inventory adjustments, inventory and material balance to NMMSS - Licensees have the option to...

160

Method of and apparatus for determining deposition-point temperature  

DOE Patents (OSTI)

Acoustic-wave sensor apparatus and method are disclosed for analyzing a normally liquid petroleum-based composition for monitoring deposition-point temperature. The apparatus includes at least one acoustic-wave device such as SAW, QCM, FPM, TSM or APM type devices in contact with the petroleum-based composition for sensing or detecting the surface temperature at which deposition occurs and/or rate of deposition as a function of temperature by sensing an accompanying change in frequency, phase shift, damping voltage or damping current of an electrical oscillator to a known calibrated condition. The acoustic wave device is actively cooled to monitor the deposition of constituents such as paraffins by determining the point at which solids from the liquid composition begin to form on the acoustic wave device. The acoustic wave device can be heated to melt or boil off the deposits to reset the monitor and the process can be repeated. 5 figs.

Mansure, A.J.; Spates, J.J.; Martin, S.J.

1998-10-27T23:59:59.000Z

Note: This page contains sample records for the topic "boiling point material" 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

Method of and apparatus for determining deposition-point temperature  

DOE Patents (OSTI)

Acoustic-wave sensor apparatus and method for analyzing a normally liquid petroleum-based composition for monitoring deposition-point temperature. The apparatus includes at least one acoustic-wave device such as SAW, QCM, FPM, TSM or APM type devices in contact with the petroleum-based composition for sensing or detecting the surface temperature at which deposition occurs and/or rate of deposition as a function of temperature by sensing an accompanying change in frequency, phase shift, damping voltage or damping current of an electrical oscillator to a known calibrated condition. The acoustic wave device is actively cooled to monitor the deposition of constituents such as paraffins by determining the point at which solids from the liquid composition begin to form on the acoustic wave device. The acoustic wave device can be heated to melt or boil off the deposits to reset the monitor and the process can be repeated.

Mansure, Arthur J. (Albuquerque, NM); Spates, James J. (Albuquerque, NM); Martin, Stephen J. (Albuquerque, NM)

1998-01-01T23:59:59.000Z

162

Simultaneous boiling and spreading of liquefied petroleum gas on water. Final report, December 12, 1978-March 31, 1981  

SciTech Connect

An experimental and theoretical investigation was carried out to study the boiling and spreading of liquid nitrogen, liquid methane and liquefied petroleum gas (LPG) on water in a one-dimensional configuration. Primary emphasis was placed on the LPG studies. Experimental work involved the design and construction of a spill/spread/boil apparatus which permitted the measurement of spreading and local boil-off rates. With the equations of continuity and momentum transfer, a mathematical model was developed to describe the boiling-spreading phenomena of cryogens spilled on water. The model accounted for a decrease in the density of the cryogenic liquid due to bubble formation. The boiling and spreading rates of LPG were found to be the same as those of pure propane. An LPG spill was characterized by the very rapid and violent boiling initially and highly irregular ice formation on the water surface. The measured local boil-off rates of LPG agreed reasonably well with theoretical predictions from a moving boundary heat transfer model. The spreading velocity of an LPG spill was found to be constant and determined by the size of the distributor opening. The maximum spreading distance was found to be unaffected by the spilling rate. These observations can be explained by assuming that the ice formation on the water surface controls the spreading of LPG spills. While the mathematical model did not predict the spreading front adequately, it predicted the maximum spreading distance reasonably well.

Chang, H.R.; Reid, R.C.

1981-04-01T23:59:59.000Z

163

PowerPoint Presentation  

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

Construction Services Solid Waste Management Operations Nuclear Materials Decontamination & Decommissioning Environmental Management Operations Lessons Learned Construction...

164

Letter Report: Progress in developing EQ3/6 for modeling boiling processes  

DOE Green Energy (OSTI)

EQ3/6 is a software package for geochemical modeling of aqueous systems, such as water/rock or waste/water rock. It is being developed for a variety of applications in geochemical studies for the Yucca Mountain Site Characterization Project. The present focus is on development of capabilities to be used in studies of geochemical processes which will take place in the near-field environment and the altered zone of the potential repository. We have completed the first year of a planned two-year effort to develop capabilities for modeling boiling processes. These capabilities will interface with other existing and future modeling capabilities to provide a means of integrating the effects of various kinds of geochemical processes in complex systems. This year, the software has been modified to allow the formation of a generalized gas phase in a closed system for which the temperature and pressure are known (but not necessarily constant). The gas phase forms when its formation is thermodynamically favored; that is, when the system pressure is equal to the sum of the partial pressures of the gas species as computed from their equilibrium fugacities. It disappears when this sum falls below that pressure. `Boiling` is the special case in which the gas phase which forms consists mostly of water vapor. The reverse process is then `condensation.` To support calculations of boiling and condensation, we have added a capability to calculate the fugacity coefficients of gas species in the system H{sub 2}O-CO{sub 2}-CH{sub 4}-H{sub 2},-Awe{sub 2}-N{sub 2},-H{sub 2}S-NH3. This capability at present is accurate only at relatively low pressures, but is adequate for all likely repository boiling conditions. We have also modified the software to calculate changes in enthalpy (heat) and volume functions. Next year we will be extending the boiling capability to calculate the pressure or the temperature at known enthalpy. We will also add an option for open system boiling.

Wolery, T. J., LLNL

1995-08-28T23:59:59.000Z

165

EAMidnightPointMahogany  

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

Environmental Assessment Midnight Point and Mahogany Geothermal Exploration Projects, Glass Buttes, Oregon April 2013 Prepared By Bureau of Land Management - Prineville and Burns...

166

PowerPoint Presentation  

National Nuclear Security Administration (NNSA)

y x Main crack surface Dislocation loops Crack initiation point Crack branching (BLJ + thermal motion) Crack embryo 3D view of surface particles Developed crack Crack development...

167

PowerPoint Presentation  

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

37, p.325, 2012 17 Advanced Manufacturing 18 Permanent magnets and batteries o Molten salt electrolysis process * Use Mg to reduce the melting points of heavy rare...

168

Pressure drop, heat transfer, critical heat flux, and flow stability of two-phase flow boiling of water and ethylene glycol/water mixtures - final report for project "Efficent cooling in engines with nucleate boiling."  

SciTech Connect

Because of its order-of-magnitude higher heat transfer rates, there is interest in using controllable two-phase nucleate boiling instead of conventional single-phase forced convection in vehicular cooling systems to remove ever increasing heat loads and to eliminate potential hot spots in engines. However, the fundamental understanding of flow boiling mechanisms of a 50/50 ethylene glycol/water mixture under engineering application conditions is still limited. In addition, it is impractical to precisely maintain the volume concentration ratio of the ethylene glycol/water mixture coolant at 50/50. Therefore, any investigation into engine coolant characteristics should include a range of volume concentration ratios around the nominal 50/50 mark. In this study, the forced convective boiling heat transfer of distilled water and ethylene glycol/water mixtures with volume concentration ratios of 40/60, 50/50, and 60/40 in a 2.98-mm-inner-diameter circular tube has been investigated in both the horizontal flow and the vertical flow. The two-phase pressure drop, the forced convective boiling heat transfer coefficient, and the critical heat flux of the test fluids were determined experimentally over a range of the mass flux, the vapor mass quality, and the inlet subcooling through a new boiling data reduction procedure that allowed the analytical calculation of the fluid boiling temperatures along the experimental test section by applying the ideal mixture assumption and the equilibrium assumption along with Raoult's law. Based on the experimental data, predictive methods for the two-phase pressure drop, the forced convective boiling heat transfer coefficient, and the critical heat flux under engine application conditions were developed. The results summarized in this final project report provide the necessary information for designing and implementing nucleate-boiling vehicular cooling systems.

Yu, W.; France, D. M.; Routbort, J. L. (Energy Systems)

2011-01-19T23:59:59.000Z

169

Point-Based Graphics  

Science Conference Proceedings (OSTI)

The polygon-mesh approach to 3D modeling was a huge advance, but today its limitations are clear. Longer render times for increasingly complex images effectively cap image complexity, or else stretch budgets and schedules to the breaking point. Point-based ... Keywords: Computer Graphics, Computers

Markus Gross; Hanspeter Pfister

2007-06-01T23:59:59.000Z

170

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

SciTech Connect

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

Lund, A.L.

1997-11-01T23:59:59.000Z

171

Project plan for the decontamination and decommissioning of the Argonne National Laboratory Experimental Boiling Water Reactor  

SciTech Connect

In 1956, the Experimental Boiling Water Reactor (EBWR) Facility was first operated at Argonne National Laboratory (ANL) as a test reactor to demonstrate the feasibility of operating an integrated power plant using a direct cycle boiling water reactor as a heat source. In 1967, ANL permanently shut down the EBWR and placed it in dry lay-up. This project plan presents the schedule and organization for the decontamination and decommissioning of the EBWR Facility which will allow it to be reused by other ANL scientific research programs. The project total estimated cost is $14.3M and is projected to generate 22,000 cubic feet of low-level radioactive waste which will be disposed of at an approved DOE burial ground. 18 figs., 3 tabs.

Boing, L.E.

1989-12-01T23:59:59.000Z

172

Two dimensional, two fluid model for sodium boiling in LMFBR fuel assemblies  

Science Conference Proceedings (OSTI)

A two dimensional numerical model for the simulation of sodium boiling transient was developed using the two fluid set of conservation equations. A semiimplicit numerical differencing scheme capable of handling the problems associated with the ill-posedness implied by the complex characteristic roots of the two fluid problems was used, which took advantage of the dumping effect of the exchange terms. Of particular interest in the development of the model was the identification of the numerical problems caused by the strong disparity between the axial and radial dimensions of fuel assemblies. A solution to this problem was found which uses the particular geometry of fuel assemblies to accelerate the convergence of the iterative technique used in the model. Three sodium boiling experiments were simulated with the model, with good agreement between the experimental results and the model predictions.

Granziera, M.R.; Kazimi, M.S.

1980-05-01T23:59:59.000Z

173

Effect of surfactant additive on pool boiling of concentrated lithium bromide solution  

SciTech Connect

The measurements of nucleate pool boiling heat transfer rate and surface tension were made for pure water and 50 wt.% lithium bromide solution with various amounts of n-octanol. Regardless of low concentration, n-octanol additive depresses considerably the surface tension of the liquids. The pool boiling data, however, reveal that the addition of surfactant results in insignificant enhancement of heat transfer for both pure water and the concentrated LiBr solution. With the results of this work, the performance improvement received from using n-octanol additive in working liquid of an absorption heat pump (AHP) is consequently due to the enhancement of heat and mass transfer in the absorber (but not generator) by the induced interfacial turbulence.

Wu, W.T.; Yang, Y.M.; Maa, J.R. [National Cheng Kung Univ., Tainan (Taiwan, Province of China). Dept. of Chemical Engineering] [National Cheng Kung Univ., Tainan (Taiwan, Province of China). Dept. of Chemical Engineering

1998-11-01T23:59:59.000Z

174

Subcooled and saturated water flow boiling pressure drop in small diameter helical coils at low pressure  

SciTech Connect

Experimental pressure drop results on boiling water flow through three helical coils of tube inner diameter of 4.03 mm and 4.98 mm and coil diameter to tube diameter ratio of 26.1, 64.1 and 93.3 are presented. Both subcooled and saturated flow boiling are investigated, covering operating pressures from 120 to 660 kPa, mass fluxes from 290 to 690 kg m{sup -2} s{sup -1} and heat fluxes from 50 to 440 kW m{sup -2}. Existing correlations for subcooled flow pressure drop are found not capable to fit the present subcooled database, while the measurements in saturated flow conditions are successfully reproduced by existing correlations for both straight and coiled pipe two-phase flow. The experimental database is included in tabular form. (author)

Cioncolini, Andrea; Santini, Lorenzo; Ricotti, Marco E. [Department of Nuclear Engineering, Politecnico di Milano, via Ponzio 34/3, 20133 Milano (Italy)

2008-05-15T23:59:59.000Z

175

Subcooled flow boiling heat transfer and critical heat flux in water-based nanofluids at low pressure  

E-Print Network (OSTI)

A nanofluid is a colloidal suspension of nano-scale particles in water, or other base fluids. Previous pool boiling studies have shown that nanofluids can improve the critical heat flux (CHF) by as much as 200%. In this ...

Kim, Sung Joong, Ph. D. Massachusetts Institute of Technology

2009-01-01T23:59:59.000Z

176

A four-equation two-phase flow model for sodium boiling simulation of LMFBR fuel assemblies  

E-Print Network (OSTI)

A three-dimensional numerical model for the simulation of sodium boiling transients has been developed. The model uses mixture mass and energy equations, while employing a separate momentum equation for each phase. Thermal ...

Schor, Andrei L.

1982-01-01T23:59:59.000Z

177

Survey of Optimization of Reactor Coolant Cleanup Systems: For Boiling Water Reactors and Pressurized Water Reactors  

Science Conference Proceedings (OSTI)

Optimization of the reactor coolant cleanup systems in the boiling water reactor (BWR) and pressurized water reactor (PWR) environment is important for controlling the transport of corrosion products (metals and activated metals), fission products, and coolant impurities (soluble and insoluble) throughout the reactor coolant loop, and this optimization contributes to reducing primary system radiation fields. The removal of radionuclides and corrosion products is just one of many functions (both ...

2013-09-27T23:59:59.000Z

178

Corrosion Product Transport during Boiling Water Reactor and Pressurized Water Reactor Startups  

Science Conference Proceedings (OSTI)

Corrosion product transport to Pressurized Water Reactor (PWR) steam generators and to the Boiling Water Reactor (BWR) reactor vessel during startups is of increased interest due to reductions in feedwater transport rates during normal operation and the recent emphasis on minimizing total transport during the cycle. Reductions in transport will reduce deposition on the fuel and the tendency for hot spot formation in BWRs and reduce surface fouling and the tendency for formation of aggressive chemical sol...

2010-12-17T23:59:59.000Z

179

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

180

Impact of Chemical Injections on Boiling Water Reactor Dose Rates: Interim Report  

Science Conference Proceedings (OSTI)

This report investigates the effects of Boiling Water Reactor (BWR) chemistry parameters on radiation field generation, with a focus on the higher reactor water Co-60 activity levels observed at plants using On-line NobleChem™ (OLNC) injections. Correlation and response curves were developed to relate reactor water and feedwater chemistry to dose rates, with the goal of improving reactor recirculation system (RRS) piping shutdown dose rate ...

2012-12-21T23:59:59.000Z

Note: This page contains sample records for the topic "boiling point material" 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

BWRVIP-167NP, Rev. 3: Boiling Water Reactor Issue Management Tables  

Science Conference Proceedings (OSTI)

Nuclear utilities continue to face a number of 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) gaps and BWR Vessel and Internals Project (BWRVIP) requirements. The BWR Issue Management Tables in the report are living documents that ...

2013-08-23T23:59:59.000Z

182

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

183

Condensate Polishing Guidelines for Pressurized Water Reactor and Boiling Water Reactor Plants - 2004 Revision  

Science Conference Proceedings (OSTI)

Successful condensate polishing allows more reliable operation of nuclear units by maintaining control of ionic and particulate impurity transport to the pressurized water reactor (PWR) steam generators and the boiling water reactor (BWR) and recirculation system. This report presents revisions of EPRI's 1997 nuclear industry consensus guidelines for the design and operation of deep bed and filter demineralizer condensate polishers. These guidelines are consistent with the 2000 revisions of EPRI's "BWR W...

2004-03-16T23:59:59.000Z

184

COST STUDY OF A 100-Mw(e) DIRECT-CYCLE BOILING WATER REACTOR PLANT  

SciTech Connect

A technical and economic evaluation is presented of a direct-cycle light- water boiling reactor designed for natural circulation and internal steam-water separation. The reference lOO-Mw(e) reactor power plant design evolved from the study should have the best chance (compared to similar plants) of approaching the 8 to 9 mill/kwh total power-cost level. (W.D.M.)

Bullinger, C.F.; Harrer, J.M.

1960-07-01T23:59:59.000Z

185

Early Hydrogen Water Chemistry Injection in Boiling Water Reactors: Impact on Fuel Performance and Reliability  

Science Conference Proceedings (OSTI)

Early injection of hydrogen during plant startup has been proposed to further mitigate intergranular stress corrosion cracking (IGSCC) in boiling water reactors (BWRs). To assess the effectiveness of early hydrogen water chemistry (EHWC), laboratory tests were performed under simulated BWR startup conditions at 200-400°F in the absence of radiation with pre-oxidized stainless steel specimens treated with noble metals to simulate plant surfaces. The ...

2012-12-13T23:59:59.000Z

186

Microscale flow visualization of nucleate boiling in small channels: Mechanisms influencing heat transfer  

SciTech Connect

This paper describes the use of a new test apparatus employing flow visualization via ultra-high-speed video and microscope optics to study microscale nucleate boiling in a small, rectangular, heated channel. The results presented are for water. Because of confinement effects produced by the channel cross section being of the same nominal size as the individual vapor bubbles nucleating at discrete wall sites, flow regimes and heat transfer mechanisms that occur in small channels are shown to be considerably different than those in large channels. Flow visualization data are presented depicting discrete bubble/bubble and bubble/wall interactions for moderate and high heat flux. Quantitative data are also presented on nucleate bubble growth behavior for a single nucleation site in the form of growth rates, bubble sizes, and frequency of generation in the presence and absence of a thin wall liquid layer. Mechanistic boiling behavior and trends are observed which support the use of this type of research as a powerful means to gain fundamental insights into why, under some conditions, nucleate boiling heat transfer coefficients are considerably larger in small channels than in large channels.

Kasza, K.E.; Didascalou, T.; Wambsganss, M.W.

1997-07-01T23:59:59.000Z

187

Bubble confinement in flow boiling of FC-72 in a ''rectangular'' microchannel of high aspect ratio  

SciTech Connect

Boiling in microchannels remains elusive due to the lack of full understanding of the mechanisms involved. A powerful tool in achieving better comprehension of the mechanisms is detailed imaging and analysis of the two-phase flow at a fundamental level. Boiling is induced in a single microchannel geometry (hydraulic diameter 727 {mu}m), using a refrigerant FC-72, to investigate the effect of channel confinement on bubble growth. A transparent, metallic, conductive deposit has been developed on the exterior of the rectangular microchannel, allowing simultaneous uniform heating and visualisation to be achieved. The data presented in this paper is for a particular case with a uniform heat flux applied to the microchannel and inlet liquid mass flowrate held constant. In conjunction with obtaining high-speed images and videos, sensitive pressure sensors are used to record the pressure drop across the microchannel over time. Bubble nucleation and growth, as well as periodic slug flow, are observed in the microchannel test section. The periodic pressure fluctuations evidenced across the microchannel are caused by the bubble dynamics and instances of vapour blockage during confined bubble growth in the channel. The variation of the aspect ratio and the interface velocities of the growing vapour slug over time, are all observed and analysed. We follow visually the nucleation and subsequent both 'free' and 'confined' growth of a vapour bubble during flow boiling of FC-72 in a microchannel, from analysis of our results, images and video sequences with the corresponding pressure data obtained. (author)

Barber, Jacqueline [School of Engineering, University of Edinburgh, The King's Buildings, Mayfield Road, Edinburgh, EH9 3JL (United Kingdom); Aix-Marseille Universite (UI, UII) - CNRS Laboratoire IUSTI, UMR 6595, 5 Rue Enrico Fermi, Marseille 13453 (France); Brutin, David; Tadrist, Lounes [Aix-Marseille Universite (UI, UII) - CNRS Laboratoire IUSTI, UMR 6595, 5 Rue Enrico Fermi, Marseille 13453 (France); Sefiane, Khellil [School of Engineering, University of Edinburgh, The King's Buildings, Mayfield Road, Edinburgh, EH9 3JL (United Kingdom)

2010-11-15T23:59:59.000Z

188

Meeting the Need for Safe Drinking Water in Rural Mexico through Point-of-Use Treatment  

E-Print Network (OSTI)

are boiling and adding chlorine in the form of tablets orto water quality problems. Chlorine pills and bleach requireassociated with boiling, chlorine tablets, and bleach. Two

Lang, Micah; Kaser, Forrest; Reygadas, Fermin; Nelson, Kara; Kammen, Daniel M.

2006-01-01T23:59:59.000Z

189

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

190

Definition: Point To Point Transmission Service | Open Energy...  

Open Energy Info (EERE)

non-firm basis from the Point(s) of Receipt to the Point(s) of Delivery.1 Related Terms transmission lines, transmission line References Glossary of Terms Used in Reliability...

191

Dew Point and Dogs  

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

hounds for hunting. I recently had a situation where the temperature was 68 degrees, humidity was 54% and dew point was 62 degrees. My dogs were not able to perform as well as...

192

ARM - Point Reyes News  

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

Takes Off in July June 30, 2005 Guest Instruments to Collect Aerosol Data During Coastal Field Campaign June 15, 2005 Mobile Facility Arrives Safe and Sound in Point Reyes...

193

Team Sand Point (SP)  

E-Print Network (OSTI)

The purpose of this flight report is to summarize the field activities of the ShoreZone aerial video imaging (AVI) survey conducted out of Sand Point and Cold Bay in

Team Cold Bay (cb

2011-01-01T23:59:59.000Z

194

Nanotexturing of surfaces to reduce melting point.  

DOE Green Energy (OSTI)

This investigation examined the use of nano-patterned structures on Silicon-on-Insulator (SOI) material to reduce the bulk material melting point (1414 C). It has been found that sharp-tipped and other similar structures have a propensity to move to the lower energy states of spherical structures and as a result exhibit lower melting points than the bulk material. Such a reduction of the melting point would offer a number of interesting opportunities for bonding in microsystems packaging applications. Nano patterning process capabilities were developed to create the required structures for the investigation. One of the technical challenges of the project was understanding and creating the specialized conditions required to observe the melting and reshaping phenomena. Through systematic experimentation and review of the literature these conditions were determined and used to conduct phase change experiments. Melting temperatures as low as 1030 C were observed.

Garcia, Ernest J.; Zubia, David (University of Texas at El Paso El Paso, TX); Mireles, Jose (Universidad Aut%C3%94onoma de Ciudad Ju%C3%94arez Ciudad Ju%C3%94arez, Mexico); Marquez, Noel (University of Texas at El Paso El Paso, TX); Quinones, Stella (University of Texas at El Paso El Paso, TX)

2011-11-01T23:59:59.000Z

195

PowerPoint Presentation  

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

3 NATIONAL TRANSPORTATION STAKEHOLDERS FORUM 3 NATIONAL TRANSPORTATION STAKEHOLDERS FORUM Buffalo, NY - May 15, 2013 2 NRC Actions Since September 11, 2001 * Interim solution - enhance existing regulations through Security Orders * Objectives of the Orders are enhanced control of material to - Prevent unauthorized access - Prevent malevolent use of material - Mitigate consequences * Orders were issued to licensees that transport: - Spent Nuclear Fuel - IAEA Code of Conduct Category 1 and 2 quantities of radioactive material Security Rulemakings 3 NRC Ongoing Activities * Orders are an interim measure * Long-term approach is to enhance transport security through public rulemaking * Rulemaking has been finalized for - SNF Transportation Security - Physical Protection of Category 1 and 2 radioactive material (both

196

PowerPoint Presentation  

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

DIOXIDE CAPTURE Kris Rangan, Humcha Hariprakasha, Tirumali Sudarshan Materials Modification, Inc. 2809-K Merrilee Drive, Fairfax. VA 22031 I ABSTRACT DOE's Carbon...

197

PowerPoint-Präsentation  

Science Conference Proceedings (OSTI)

... 23. Scales in Batteries. 10 µm: membrane, current collector. ... 100 µm: cell, dendrite. 1 mm: battery. ... 25. Li deintercalation from Si-anode material. ...

2012-10-04T23:59:59.000Z

198

PowerPoint Presentation  

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

* Product penalties * Success stories * Projects for individuals * Educational material * Energy incentives * NEPA calls to action * Social Media shareables * ContestsChallenge s...

199

PowerPoint Presentation  

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

facility. Understand long term effects of the coal gasifier environment on the metallurgy of the membrane components. 7 Centre for Applied Materials Science How Palladium...

200

PowerPoint Presentation  

National Nuclear Security Administration (NNSA)

or Thorium) * 1 kilogram or more of "foreign obligated" source material, - report the inventory to NMMSS * Enrichment, MOX fuel fabrication or downblending uranium >10% enriched, -...

Note: This page contains sample records for the topic "boiling point material" from the National Library of EnergyBeta (NLEBeta).
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they are not comprehensive nor are they the most current set.
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201

PowerPoint Presentation  

National Nuclear Security Administration (NNSA)

Evolutions: Spiral 1 Authority Reference Spiral 2 Transaction processing Spiral 3 Inventory Spiral 4 Material Balance Spiral 5 IAEA Reporting Spiral 6 Reports Spiral 7 SAMS...

202

PowerPoint Presentation  

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

programs with ORNL * Shared research and joint appointments * Joint institutes in advanced materials, biological sciences, computational sciences, neutron sciences, and nuclear...

203

PowerPoint Presentation  

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

by Science Categories 0109-043008 Lattice Gauge Theory Materials Sciences Fusion Energy Chemistry Climate Research Astrophysics Accelerator Physics Combustion Other...

204

Strategic Focus Points  

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

Focus Points Focus Points June 2011 1. Establish the human capital and organizational foundation to create a high-performing organization. 2. Implement a cyber risk-management and incident response program that ensures effective security of Federal and M&O networks, provides appropriate flexibility, and meets legal requirements and OMB expectations. 3. Improve IT Services (EITS) into a best-in-class provider from both a technical and business perspective. 4. Implement and institutionalize a reformed, integrated information management governance process that respects the goal to treat M&Os distinctively different than true Federal entities. 5. Transition to 5-year planning and programming, using the NNSA Planning, Programming, Budgeting and Evaluation (PPBE) process as a starting point to include resource and requirements validation.

205

Improving Floating Point Compression  

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

Improving Improving Floating Point Compression through Binary Masks Leonardo A. Bautista Gomez Argonne National Laboratory Franck Cappello Argonne National Laboratory Abstract-Modern scientific technology such as particle accel- erators, telescopes and supercomputers are producing extremely large amounts of data. That scientific data needs to be processed using systems with high computational capabilities such as supercomputers. Given that the scientific data is increasing in size at an exponential rate, storing and accessing the data is becoming expensive in both, time and space. Most of this scientific data is stored using floating point representation. Scientific applications executed in supercomputers spend a large amount of CPU cycles reading and writing floating point values, making data compression techniques an interesting way to increase computing efficiency.

206

PowerPoint Presentation  

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

and Validating Ternary Pd Alloys and Validating Ternary Pd Alloys Designing and Validating Ternary Pd Alloys for Optimum Sulfur/Carbon Resistance for Optimum Sulfur/Carbon Resistance in Hydrogen Separation in Hydrogen Separation and Carbon Capture Membrane Systems and Carbon Capture Membrane Systems Using High Using High - - Throughput Combinatorial Methods Throughput Combinatorial Methods Dan Henkel Rick kleiner November 12, 2009 This presentation does not contain any proprietary or confidential information 2 Participating Organizations Pall Corporation Pall Cortland Research and Development (PRDC) Cornell University Cornell Center for Materials Research (CCMR) Georgia Institute of Technology Dept. of Materials Science and Engineering Oak Ridge National Laboratory High Temperature Materials Lab (HTML)

207

PowerPoint Presentation  

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

Crone, Director Crone, Director Research Reactors Division Oak Ridge National Laboratory UT-Battelle, LLC September 20, 2012 - Bethesda, MD High Flux Isotope Reactor Spallation Neutron Source Oak Ridge National Laboratory - Main Campus Materials Irradiation Testing * Fusion Energy - provides best available neutron spectrum for radiation damage testing on fusion components; collaboration between U.S. and Japan for over thirty years * Fission Energy - research supporting next-generation commercial power reactors including accident tolerant fuel and reactor materials * National Security - Neutron Activation Analysis supporting IAEA non-proliferation monitoring 1,021 Materials and NAA Irradiations in FY2011 Reliable Source of Unique Isotopes * Californium-252 - HFIR supplies 80% of the world

208

PowerPoint Presentation  

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

Background and Introduction Background and Introduction Acknowledgments This research was supported in part by the Department of Energy (DOE) Office of Energy Efficiency and Renewable Energy (EERE) Postdoctoral Research Awards under the EERE Fuel Cell Technologies Program administered by the Oak Ridge Institute for Science and Education (ORISE) for the DOE. ORISE is managed by the Oak Ridge Associated Universities (ORAU) under DOE contract number DE-AC05-06OR23100. Modified Physisorption-Based Materials for the Ambient Temperature Storage of Molecular H 2 Impact This project aims to synthesize, characterize and evaluate a new class of materials, namely metal- and cluster-modified ultra-high area diamond network materials. If fully successful, these materials are potentially capable of satisfying, and even exceeding, the U.S. DOE's 2015 excess gravimetric and

209

PowerPoint Presentation  

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

Radiation-induced Ductility Radiation-induced Ductility Enhancement in Amorphous Fe and Al2O3+TiO2 Nano-structured Coatings under Fast Neutrons Nick Simos, BNL Co-PIs: Dr. Simerjeet Gill, BNL Prof. T. Tsakalakos and Dr. K. Akdogan Nano Structured Materials Group Nano Structured Materials Group Department of Materials Science & Engineering Department of Materials Science & Engineering Rutgers University Webinar - August 20, 2013 Project Description  Explore the protective performance of Fe-based amorphous and ceramic (Al 2 O 3 and Al 2 O 3 +TiO 2 ) nanostructured coatings under extreme temperatures, neutron irradiation and aggressively corrosive environments  Study the effects of fast neutrons  Study resistance to ductility loss of the composite structures (coating + substrate) and

210

PowerPoint Presentation  

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

comprehensive comprehensive strategy to prevent nuclear terrorism; and  The key organization responsible for implementing the U.S. HEU minimization policy. GTRI MISSION Reduce and protect vulnerable nuclear and radiological material located at civilian sites worldwide. DOE STRATEGIC GOAL 2.2 Prevent the acquisition of nuclear and radiological materials for use in weapons of mass destruction and other acts of terrorism Protect high priority nuclear and radiological materials from theft and sabotage These efforts result in threat reduction by improving security on the bomb material remaining at civilian sites - each vulnerable building that is protected reduces the risk until a permanent threat reduction solution can be implemented. Protect Remove and dispose of

211

PowerPoint Presentation  

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

nd nd Energy & Innovation Conference November 28-29, 2012 Partnering for Innovation: Critical Materials Roe-Hoan Yoon, Lead Paul King, Business Development Critical Materials Strategic Growth Area NETL-Regional University Allience 2 o Critical: * Intrinsically rare, low grade, or currently unavailable in the United States. o Energy Critical Elements: * Chemical elements that are essential for the deployment of transformative energy technologies. Critical Materials-Definition 3 Application of Critical Materials 3 4  Short Term (present t - 2015) Criticality Matrix Your Logo  Mid Term (2015 - 2025) 5  Essential for the U.S. leading the 6 th wave of technology innovation o Renewable energy development o High-tech industry o Sustainability

212

Verification of physics parameters for BWR (boiling water reaction) one-dimensional transient analysis  

SciTech Connect

A data-processing method was developed to generate physics parameters for use with the one-dimensional kinetics model of the RETRAN-02/MOD3 code. The physics parameters were verified to assure the consistency in collapsing procedures and to identify the need for further improvements. In the present study, calculations were performed during the boiling water reactor-4 Chinshan-1 cycle-7 (CS1CY7) end-of-cycle (EOC) Hailing condition, CS2CY6 middle-of-cycle (MOC), and CS1CY1 beginning-of-cycle (BOC) rated conditions. This paper describes the results of verification and their implications for plant transient analyses.

Chou, H.P. (National Tsing-Hua Univ., Hsinchu (Taiwan)); Chen, Y.J. (Institute of Nuclear Energy Research, Lung-Tan (Taiwan))

1989-11-01T23:59:59.000Z

213

Numerical modeling of boiling due to production in a fractured reservoir and its field application  

Science Conference Proceedings (OSTI)

Numerical simulations were carried out to characterize the behaviors of fractured reservoirs under production which causes in-situ boiling. A radial flow model with a single production well, and a two-dimensional geothermal reservoir model with several production and injection wells were used to study the two-phase reservoir behavior. The behavior can be characterized mainly by the parameters such as the fracture spacing and matrix permeability. However, heterogeneous distribution of the steam saturation in the fracture and matrix regions brings about another complicated feature to problems of fractured two-phase reservoirs.

Yusaku Yano; Tsuneo Ishido

1995-01-26T23:59:59.000Z

214

Forced-convection boiling tests performed in parallel simulated LMR fuel assemblies  

SciTech Connect

Forced-convection tests have been carried out using parallel simulated Liquid Metal Reactor fuel assemblies in an engineering-scale sodium loop, the Thermal-Hydraulic Out-of-Reactor Safety facility. The tests, performed under single- and two-phase conditions, have shown that for low forced-convection flow there is significant flow augmentation by thermal convection, an important phenomenon under degraded shutdown heat removal conditions in an LMR. The power and flows required for boiling and dryout to occur are much higher than decay heat levels. The experimental evidence supports analytical results that heat removal from an LMR is possible with a degraded shutdown heat removal system.

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

1985-04-21T23:59:59.000Z

215

Some investigations on the enhancement of boiling heat transfer from planer surface embedded with continuous open tunnels  

Science Conference Proceedings (OSTI)

Boiling heat transfer from a flat surface can be enhanced if continuous open tunnel type structures are embedded in it. Further, improvement of boiling heat transfer from such surfaces has been tried by two separate avenues. At first, inclined tunnels are embedded over the solid surface and an effort is made to optimize the tunnel inclination for boiling heat transfer. Surfaces are manufactured in house with four different inclinations of the tunnels with or without a reentrant circular pocket at the end of the tunnel. Experiments conducted in the nucleate boiling regime showed that 45 deg inclination of the tunnels for both with and without base geometry provides the highest heat transfer coefficient. Next, active fluid rotation was imposed to enhance the heat transfer from tunnel type surfaces with and without the base geometry. Rotational speed imparted by mechanical stirrer was varied over a wide range. It was observed that fluid rotation enhances the heat transfer coefficient only up to a certain value of stirrer speed. Rotational speed values, beyond this limit, reduce the boiling heat transfer severely. A comparison shows that embedding continuous tunnel turns out to be a better option for the increase of heat transfer coefficient compared to the imposition of fluid rotation. But the behavior of inclined tunnels under the action of fluid rotation is yet to be established and can be treated as a future scope of the work. (author)

Das, A.K.; Das, P.K.; Saha, P. [Department of Mechanical Engineering, Indian Institute of Technology, Kharagpur 721 302 (India)

2010-11-15T23:59:59.000Z

216

Resistivity During Boiling in the SB-15-D Core from the Geysers Geothermal Field: The Effects of Capillarity  

DOE Green Energy (OSTI)

In a laboratory study of cores from borehole SB-15-D in The Geysers geothermal area, we measured the electrical resistivity of metashale with and without pore-pressure control, with confining pressures up to 100 bars and temperatures between 20 and 150 C, to determine how the pore-size distribution and capillarity affected boiling. We observed a gradual increase in resistivity when the downstream pore pressure or confining pressure decreased below the phase boundary of free water. For the conditions of this experiment, boiling, as indicated by an increase in resistivity, is initiated at pore pressures of approximately 0.5 to 1 bar (0.05 to 0.1 MPa) below the free-water boiling curve, and it continues to increase gradually as pressure is lowered to atmospheric. A simple model of the effects of capillarity suggests that at 145 C, less than 15% of the pore water can boil in these rocks. If subsequent experiments bear out these preliminary observations, then boiling within a geothermal reservoir is controlled not just by pressure and temperature but also by pore-size distribution. Thus, it may be possible to determine reservoir characteristics by monitoring changes in electrical resistivity as reservoir conditions change.

Roberts, J.; Duba, A.; Bonner, B.; Kasameyer, P.

1997-01-01T23:59:59.000Z

217

Materials Science  

Science Conference Proceedings (OSTI)

Materials Science. Summary: ... Description: Group focus in materials science (inkjet metrology, micro-macro, advanced characterizations). ...

2012-10-02T23:59:59.000Z

218

Program on Technology Innovation: Prediction and Evaluation of Environmentally Assisted Cracking in LWR Structural Materials  

Science Conference Proceedings (OSTI)

This report describes the final results of Phase III of a three-year joint research program sponsored by EPRI in collaboration with Fracture & Reliability Research Institute (FRRI) at Tohoku University, Japanese utilities, vendors, and international organizations. The program addressed environmentally assisted cracking (EAC) of light water reactor (LWR) structural materials in pressurized water reactor (PWR) and boiling water reactor (BWR) environments.

2007-11-20T23:59:59.000Z

219

DIY TIMBER DECKS CHECKLIST POINTS TO CONSIDER  

E-Print Network (OSTI)

DIY TIMBER DECKS CHECKLIST POINTS TO CONSIDER · Local council regulations. · Special regulations and materials you will be using. #12;DIY TIMBER DECKS CHECKLIST LOCATION · Direction of sun. · Best views. #12;DIY TIMBER DECKS CHECKLIST CONSTRUCTION 1. THEBASICSARE: · Stumps/posts or brackets set

Peters, Richard

220

PowerPoint Presentation  

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

Commercialization of the SuperOPF Commercialization of the SuperOPF Framework: Phase III (Theme: Co- optimization Stochastic SuperOPF- renewables) Performers: PSERC: Hsiao-Dong Chiang - LEAD Cornell University: Ray Zimmerman Bigwood Systems, Inc.: Patrick Causgrove, Bin Wang Phase I: 1.(support industrial model) A commercial-grade core SuperOPF software supporting various industrial-grade power system models such as (i) CIM-compliance; and (ii) PSS/E data format 2. A multi-stage OPF solver with adaptive homotopy-based Interior Point Method for large- scale power systems (PJM: 14,000-bus data) Bigwood Systems Inc., 2013 3 Results: Efficiency and Robustness (Analytical Jacobian matrices) Loading Conditions One-Staged Interior Point Method Multi-Staged Scheme 1 Succeeded Succeeded

Note: This page contains sample records for the topic "boiling point material" 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

PowerPoint Presentation  

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

Coupling Between Oceanic Upwelling and Cloud Coupling Between Oceanic Upwelling and Cloud Coupling Between Oceanic Upwelling and Cloud - - Aerosol Properties Aerosol Properties at the AMF Point Reyes Site at the AMF Point Reyes Site Maureen Dunn , Mike Jensen , Pavlos Kollias , Mark Miller , Peter Daum Mary Jane Bartholomew , David Turner , Elisabeth Andrews and Anne Jefferson Introduction Ground based observations from the MASRAD, Pt. Reyes AMF July 1-Sept 15, 2005 indicate a relationship between coastal marine stratus cloud properties, boundary layer cloud condensation nuclei and the upwelling of cool oceanic waters measured at an offshore NOAA buoy. Cloud Drizzle to CCN Atmosphere to Cloud Upwelling SST to Atmosphere Conclusion Coastal marine stratus clouds increase in thickness as the underlying sea surface

222

EAMidnightPointMahogany  

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

Assessment Assessment Midnight Point and Mahogany Geothermal Exploration Projects, Glass Buttes, Oregon April 2013 Prepared By Bureau of Land Management - Prineville and Burns Districts DOI-BLM-OR-P040-2011-0021-EA DOE/EA-1925 Environmental Assessment Midnight Point and Mahogany Geothermal Exploration Projects, Glass Buttes, Oregon April 2013 Lead Agency United States Department of the Interior Bureau of Land Management Prineville District 3050 N.E. 3rd Street, Prineville, OR 97754 Tel: 541 416 6700 Burns District 28910 Hwy 20 West, Hines, OR 97738 Tel: 541 573 4400 Cooperating Agency United States Department of Energy Golden Field Office Golden, Colorado 80401 Tel: 720-356-1563 Fax: 720-356-1560 April 2013 Environmental Assessment Table of Contents 1

223

Evaluating Point Forecasts  

E-Print Network (OSTI)

Typically, point forecasting methods are compared and assessed by means of an error measure or scoring function, such as the absolute error or the squared error. The individual scores are then averaged over forecast cases, to result in a summary measure of the predictive performance, such as the mean absolute error or the (root) mean squared error. I demonstrate that this common practice can lead to grossly misguided inferences, unless the scoring function and the forecasting task are carefully matched. Effective point forecasting requires that the scoring function be specified ex ante, or that the forecaster receives a directive in the form of a statistical functional, such as the mean or a quantile of the predictive distribution. If the scoring function is specified ex ante, the forecaster can issue the optimal point forecast, namely, the Bayes rule. If the forecaster receives a directive in the form of a functional, it is critical that the scoring function be consistent for it, in the sense that the expect...

Gneiting, Tilmann

2009-01-01T23:59:59.000Z

224

PowerPoint Presentation  

National Nuclear Security Administration (NNSA)

Russia Conference on Advances in Materials Science, Russia Conference on Advances in Materials Science, 31.08-03.09.2009, Prague 1 Cluster Dynamics Method Cluster Dynamics Method for Simulation of Dynamic Processes for Simulation of Dynamic Processes of Continuum Mechanics of Continuum Mechanics I.А.Davydov, V.N.Piskunov, R.А.Veselov, B.L.Voronin, D.А.Demin, V.V.Rudenko, Yu.V.Yanilkin, V.N.Sofronov Russian Federal Nuclear Center - All-Russia Institute of Experimental Physics I.A.Davydov@vniief.ru Piskunov@vniief.ru Joint U.S.Russia Conference on Advances in Materials Science, 31.08-03.09.2009, Prague 2 Contents: Introduction Cluster dynamics method (CDM) Cluster interaction potentials CDM application to certain problems Analogues and software implementation Conclusions Cluster Dynamics Method Cluster Dynamics Method

225

PowerPoint Presentation  

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

Tolerance and Mechanical Properties of Tolerance and Mechanical Properties of Nanostructured Ceramic/Metal Composites Michael Nastasi Nebraska Center for Energy Sciences Research and Mechanical and Materials Engineering University of Nebraska-Lincoln Collaborators : UNL: Juan Colon Santana MIT: Mike Demkowicz , R. E. Baumer, Kan-Ju Lin TAMU: Lin Shao, Lloyd Price Work supported by DOE, NE, Nuclear Energy Enabling Technologies Presented at: Materials-Cross-Cut NEET Webinar August 20 th , 2013 Vacancies Interstitials Atomic defects produced by irradiation Embrittlement Defects that do NOT recombine aggregate into vacancy or interstitial clusters D.L. Porter and F. A. Garner, J. Nuclear Materials, 159, p. 114 (1988) D.J. Bacon and Y.N. Osetsky, Int. Mater. Rev., 47, p. 233 (2002).

226

PowerPoint Presentation  

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

First Principles Materials and Nanoscience First Principles Materials and Nanoscience Codes to Thousands of Processors (and Thousands of Atoms) (Plane-wave, DFT codes) Andrew Canning and Lin-Wang Wang Computational Research Division LBNL Nanostructures as a new material Definition: Nanostructure is an assembly of nanometer scale "building blocks". Why nanometer scale: This is the scale when the properties of these "building blocks" become different from bulk. size Electron Wavefunction Nanostructure Both are in nanometers Example: Quantum Dots (QD) CdSe *Band gap increase CdSe quantum dot (size) *Single electron effects on transport (Coulomb blockade). *Mechanical properties, surface effects and no dislocations Computational challenges (larger nanostructures) *Ab initio method PARATEC

227

Gas processing/The boiling behavior of LPG and liquid ethane, ethylene, propane, and n-butane spilled on water  

SciTech Connect

Boiling-rate calorimeter studies showed that unlike liquid nitrogen, methane, and LNG, LPG (84.7% propane, 6.0% ethane, and 9.3% n-butane; 442/sup 0/C bp), or pure propane, when rapidly spilled on water, reacted violently, ejecting water and ice into the vapor space; but in 1-2 sec, a coherent ice layer was formed and further boiloff was quiet and well predicted by a simple one-dimensional, moving-boundary-value, heat transfer model with a growing ice shield. Increasing the content of ethane and butane in LPG to 20% and 10%, respectively, had almost no effect on the LPG boiling, indicating that boiling may be modeled by using pure propane. Ethane, ethylene, and n-butane behaved quite differently from LPG. In spills of pure liquid propane on solid ice, the boiloff rate was almost identical to that predicted by the moving-boundary model.

Reid, R.C.; Smith, K.A.

1978-04-01T23:59:59.000Z

228

PowerPoint Presentation  

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

Department of Energy Department of Energy Department of Energy Environmental Management Environmental Management Transportation Transportation Update Update Dennis Ashworth Dennis Ashworth Director, EM Office of Transportation Director, EM Office of Transportation 2 2 Environmental Management Office of Transportation Protecting the Public and the Environment in all aspects of our Transportation Operations Transportation, Logistics and Waste Disposition are Transportation, Logistics and Waste Disposition are Key Contributors to the EM Project Key Contributors to the EM Project Ensuring disposition paths are identified for Ensuring disposition paths are identified for all EM waste and materials all EM waste and materials Providing and coordinating disposition Providing and coordinating disposition

229

Pool boiling of R-114/oil mixtures from single tubes and tube bundles. Master's thesis  

Science Conference Proceedings (OSTI)

An apparatus was designed, fabricated, and operated for the testing of horizontal tube bundles for boiling of R-114 with various concentrations of oil. Preliminary data were taken on the top tube in the bundle, with and without the other tubes in operation. Results showed up to a 37% increase in the boiling heat-transfer coefficient as a result of the favorable bundle effect. In a separate single-tube apparatus, three enhanced tubes were tested at a saturation temperature of 2.2 C with oil mass concentrations of 0, 1, 2, 3, 6 and 10%. The tubes were: 1) a finned tube with 1024 fins per meter, 2) a finned tube with 1575 fins per meter and 3) a Turbo-B tube. These tubes resulted in enhancement ratios in pure refrigerant of 2.8, 3.8 and 5.2, respectively, at a practical heat flux of 30 kW/sq. meter. With 3% oil, these ratios were decreased to 2.6, 3.5 and 5, while with 10% oil, these ratios were further reduced to 2.6, 3.2 and 4.7, respectively. Based on these results, the use of Turbo-B tubes is expected to result in significant savings in weight and size of evaporators over the finned tubes presently in use on board some naval vessels.

Murphy, T.J.

1987-09-01T23:59:59.000Z

230

Performance of Charcoal Cookstoves for Haiti Part 1: Results from the Water Boiling Test  

Science Conference Proceedings (OSTI)

In April 2010, a team of scientists and engineers from Lawrence Berkeley National Lab (LBNL) and UC Berkeley, with support from the Darfur Stoves Project (DSP), undertook a fact-finding mission to Haiti in order to assess needs and opportunities for cookstove intervention. Based on data collected from informal interviews with Haitians and NGOs, the team, Scott Sadlon, Robert Cheng, and Kayje Booker, identified and recommended stove testing and comparison as a high priority need that could be filled by LBNL. In response to that recommendation, five charcoal stoves were tested at the LBNL stove testing facility using a modified form of version 3 of the Shell Foundation Household Energy Project Water Boiling Test (WBT). The original protocol is available online. Stoves were tested for time to boil, thermal efficiency, specific fuel consumption, and emissions of CO, CO{sub 2}, and the ratio of CO/CO{sub 2}. In addition, Haitian user feedback and field observations over a subset of the stoves were combined with the experiences of the laboratory testing technicians to evaluate the usability of the stoves and their appropriateness for Haitian cooking. The laboratory results from emissions and efficiency testing and conclusions regarding usability of the stoves are presented in this report.

Booker, Kayje; Han, Tae Won; Granderson, Jessica; Jones, Jennifer; Lsk, Kathleen; Yang, Nina; Gadgil, Ashok

2011-06-01T23:59:59.000Z

231

Operating experience of natural circulation core cooling in boiling water reactors  

SciTech Connect

General Electric (GE) has proposed an advanced boiling water reactor, the Simplified Boiling Water Reactor (SBWR), which will utilize passive, gravity-driven safety systems for emergency core coolant injection. The SBWR design includes no recirculation loops or recirculation pumps. Therefore the SBWR will operate in a natural circulation (NC) mode at full power conditions. This design poses some concerns relative to stability during startup, shutdown, and at power conditions. As a consequence, the NRC has directed personnel at several national labs to help investigate SBWR stability issues. This paper will focus on some of the preliminary findings made at the INEL. Because of the broad range of stability issues this paper will mainly focus on potential geysering instabilities during startup. The two NC designs examined in detail are the US Humboldt Bay Unit 3 BWR-1 plant and Dodewaard plant in the Netherlands. The objective of this paper will be to review operating experience of these two plants and evaluate their relevance to planned SBWR operational procedures. For completeness, experimental work with early natural circulation GE test facilities will also be briefly discussed.

Kullberg, C.; Jones, K.; Heath, C.

1993-08-01T23:59:59.000Z

232

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

Science Conference Proceedings (OSTI)

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

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

1995-07-01T23:59:59.000Z

233

Analytical and experimental simulation of boiling oscillations in sodium with a low-pressure water system. [LMFBR  

SciTech Connect

An experimental and analytical program designed to simulate sodium boiling under low-power, low-flow conditions has been completed. Experiments were performed using atmospheric- pressure water as a simulant fluid and a simple one-dimensional model was developed for the system. Results indicate that water is a suitable simulant for liquid sodium under certain conditions and that the model does a fair job of modeling the system. In addition, oscillations that occur during the boiling process appear to augment substantially the heat transfer between liquid and vapor in condensation.

Levin, A.E.; Griffith, P.

1981-01-01T23:59:59.000Z

234

Modeling the Thermal Mechanical Behavior of a 300 K Vacuum Vesselthat is Cooled by Liquid Hydrogen in Film Boiling  

DOE Green Energy (OSTI)

This report discusses the results from the rupture of a thin window that is part of a 20-liter liquid hydrogen vessel. This rupture will spill liquid hydrogen onto the walls and bottom of a 300 K cylindrical vacuum vessel. The spilled hydrogen goes into film boiling, which removes the thermal energy from the vacuum vessel wall. This report analyzes the transient heat transfer in the vessel and calculates the thermal deflection and stress that will result from the boiling liquid in contact with the vessel walls. This analysis was applied to aluminum and stainless steel vessels.

Yang, S.Q.; Green, M.A.; Lau, W.

2004-05-07T23:59:59.000Z

235

PowerPoint Presentation  

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

Conard Stair Conard Stair Enforcement Program Manager B&W Y-12 March 2012 Enforcement Coordination Working Group Spring 2012 Meeting Y-12 Approach to Enforcement Y-12 Enforcement Program Office (EPO) * Integrated program with a single point of contact for enforcement activities for radiological protection, worker safety and health, and classified information security * Proceduralized and automated process that provides consistent documentation of compliance determinations and reporting * Uses a decentralized approach with Line Management Price- Anderson Officers (LMPOs) assisted by a cadre of subject matter experts to perform screening determinations * Provides policy, direction, guidance, and independent oversight * Serves as chief technical advisor to senior leadership team on

236

Numerical Simulation of Boiling Heat Transfer by Transient Heating *@--i"OE`H@j@@@"`@Zi@Oi"OE`Hj@@@"`@SZR@vi"OE`Hj  

E-Print Network (OSTI)

with macrolayer model of Maruyama, we simulated the transient boiling curve for water and fluorinert FC-72(C6F14 transient CHF in saturated pool boiling. The developed model includes the analysis of thermal energy conduction within the heater coupled with a macrolayer- thinning model. The prediction indicated favorable

Maruyama, Shigeo

237

PowerPoint Presentation  

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

Oxidation of SiC/BN/SiC Composites in Oxidation of SiC/BN/SiC Composites in Reduced Oxygen Partial Pressures Elizabeth Opila, Department of Materials Science, University of Virginia, Charlottesville, VA Meredith Boyd, Department of Chemical Engineering, University of Rochester, Rochester, NY Motivation Technical challenge for hypersonic vehicles: Develop lightweight, durable, reusable, 3000°F (1650C) structurally-integrated Thermal Protection Systems (TPS) to carry both thermal and mechanical loads using ceramic matrix composite materials Objectives * Characterize the oxidation resistance of BN-coated SiC fiber- reinforced SiC composites at temperatures and oxygen partial pressures relevant for hypersonic environments * Develop understanding of oxidation degradation kinetics and

238

PowerPoint Presentation  

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

TEC Rail Topic Group TEC Rail Topic Group Update Update Transportation External Coordination Meeting April 21-23, 2004 Steven Hamp Acting Director, National Transportation Program (EM) Rail Topic Group Charter: To Identify and Discuss Current Issues and Concerns Regarding Rail Transportation of Radioactive Materials by the Department of Energy. First Established in 1997 and Operated Until 1999 Re-formed Topic Group in 2002 Rail Topic Group Efforts: *Review Earlier Reports Completed by the Topic Group *Identify Rail Issues of Interest *Prepare Summary of the Rail Topic Group Report - "Transportation Safety WIPP-PIG Rail Comparison" *Circulate Annotated Bibliography of Rail Transport of Radioactive Material *Prepare Draft Issue Paper on Rail Route Selection Rail Topic Group Timeline Since Being Reactivated:

239

PowerPoint Presentation  

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

Lives. Better Planet.SM Lives. Better Planet.SM Centre for Applied Materials Science High Throughput Design of Ternary Pd Alloys for Optimum Sulfur / Carbon Resistance in Hydrogen Separation & Carbon Capture Membrane Systems NETL CO 2 Capture Technology Meeting Pittsburgh / July 8 - 11, 2013 Scott D. Hopkins, Hongbin Zhao 2 Centre for Applied Materials Science Palladium Membrane Technology: Problem and Opportunity Thomas Graham @ Royal Mint H 2 Permeation Pd L W McKeehan α & β-Phase Pd Hydrides J B Hunter @ Bishop Pd-Ag Alloy J B Hunter et al Large Scale Diffusion Cell, Tubes J Bishop & Co 115,000ft 3 /day H 2 Diffusion Plant D L McKinley @ Union Carbide Corp. 9 million ft 3 /day H 2 Diffusion Plant, Plates The State Nitrogen Industry, Russia 1.7 million ft 3 /day H 2 Diffusion Plant, Capillary

240

Microsoft PowerPoint - IPRC Crucible and Coating materials [Compatibil...  

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

graphite, Al 2 O 3 , ZrO 2 , ThO 2 , BeO - CaO stabilized ZrO 2 was used in the hot cell * Better Cs separation and higher pouring yields 5 2012 IPRC Fontana, Wisconsin...

Note: This page contains sample records for the topic "boiling point material" 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

Big Rock Point Aged Material Sampling Program -- Project Closeout Report  

Science Conference Proceedings (OSTI)

In submitting an application for license renewal for a nuclear power plant, utilities must demonstrate that aging effects applicable to plant components will be effectively managed during the extended operating term. Destructive and non-destructive evaluation of components in operating plants provides particularly relevant information on aging effects and mechanisms that can be used to support a license renewal submittal. Such information is difficult to obtain. This report describes an effort to obtain ...

2002-05-24T23:59:59.000Z

242

Flame size, heat release, and smoke points in materials ...  

Science Conference Proceedings (OSTI)

... to flame area was 0.25 cm for propane, ethylene, and ... means to insure a steady state condition (or ... Pergamon Press, New York, 1979, pp., 185–195. ...

2008-08-20T23:59:59.000Z

243

Advanced Materials  

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

Advanced Materials Advanced Materials Availability Technology Express Licensing Active Terahertz Metamaterial Devices Express Licensing Anion-Conducting Polymer, Composition, And...

244

A point of order 8  

E-Print Network (OSTI)

A formula expressing a point of order 8 on an elliptic curve, in terms of the roots of the associated cubic polynomial, is given. Doubling such a point yields a point of order 4 distinct from the well-known points of order 4 given in standard references such as "A course of Modern Analysis" by Whittaker and Watson.

Semjon Adlaj

2011-10-03T23:59:59.000Z

245

Thermal energy storage material  

DOE Patents (OSTI)

A thermal energy storage material which is stable at atmospheric temperature and pressure and has a melting point higher than 32.degree.F. is prepared by dissolving a specific class of clathrate forming compounds, such as tetra n-propyl or tetra n-butyl ammonium fluoride, in water to form a substantially solid clathrate. The resultant thermal energy storage material is capable of absorbing heat from or releasing heat to a given region as it transforms between solid and liquid states in response to temperature changes in the region above and below its melting point.

Leifer, Leslie (Hancock, MI)

1976-01-01T23:59:59.000Z

246

PowerPoint Presentation  

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

John Nangle, National Renewable Energy Laboratory (NREL) John Nangle, National Renewable Energy Laboratory (NREL) Tribal Leader Forum, Phoenix, AZ - May 30 - 31, 2013 State Incentives and Project Impacts Main Points - Market Context * State Renewable Portfolio Standards (RPS) - What are they? - How can they help your project? - Potential gap means more market demand for RE projects Starting a Renewable Energy Project * What renewable resources exist? * What sites with resources do you own? * To whom will you sell the electricity? * How will federal and state incentives or policies impact your project? * Access to transmission * Other policies - Interconnection standards - Environmental standards Renewable Portfolio Standard (RPS) * A requirement set by a state for utilities to generate x% of electricity from renewables by a specific date

247

PowerPoint Presentation  

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

Customer Acceptance of Smart Grid Customer Acceptance of Smart Grid DOE Energy Advisory Committee Meeting June 6, 2013 Judith Schwartz, To the Point + INNOVATORS EARLY ADOPTERS EARLY MAJORITY LATE MAJORITY LATE ADOPTERS Indifferents Tech Enthusiasts Green Altruists Comfort Lovers Cost Conscious Doubters Green buildings Simple feedback interface Price incentives Seamless automation Who Are Our Customers? + Why Will They Care About SG? 1. Information, incentives, and automation to easily reduce or defer electricity use 2. Integrate clean generation and transportation 3. Reduce, pinpoint, and restore outages + Fly Under the Radar Active Engagement Slow Build Back end deployment first in sequence AMI rollout in process or pilots are imminent Practice incremental modernization efforts High % of "indifferent"

248

PowerPoint Presentation  

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

Kennametal Overview Kennametal Overview Dr. Paul Prichard Innovation Ventures Group November 29, 2012 © 2012 Kennametal Inc. l All rights reserved. Mission: Deliver Productivity to Customers In Demanding Environments © 2012 Kennametal Inc. l All rights reserved. l 2 Energy & Process Market: Significantly Enhanced With Stellite Solutions * Regionalized Production Capability * Surface Treatment Technologies * Wear Solutions For Water * Stellite Components, Materials And Coatings * Corrosion Resistant Solutions * Deep Well Drilling Abrasive Solutions Initiatives Wear * Technology Development With Customers Reconditioning * Field Replacement/ Aftermarket Life Extension Emerging Markets * China, EMEA Expansion Strategies * Global Energy Demand * Emergence of Fracking

249

PowerPoint Presentation  

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

IOGCC/SSEB PTTF REPORT IOGCC/SSEB PTTF REPORT THE PIPELINE PROJECT: Analysis of potential pipeline infrastructure, transportation & storage of CO 2 Presented at DOE's Carbon Storage Program Infrastructure Annual Review Meeting Nov. 15, 2011 Acknowledgement * This material is based upon work supported by the U.S. Department of Energy's National Energy Technology Laboratory. The Report Four sections: 1. Overview 2. Background 3. Analysis 4. Recommendations PART 1: OVERVIEW * Pipeline Transportation Task Force * Collaborative Work Group Model * Task Force Objectives IOGCC-SSEB CO 2 Pipeline Transportation Task Force (PTTF) * Offshoot of IOGCC's Carbon Capture and Geologic Storage Task Force * Southeast Regional Carbon Sequestration Partnership Focus Area * Collaboration: Task Force Composition

250

PowerPoint Presentation  

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

December 12, 2013 December 12, 2013 EERE's National Mission To create American leadership in the global transition to a clean energy economy 1.) High-Impact Research, Development, and Demonstration to Make Clean Energy as Affordable and Convenient as Traditional Forms of Energy 2.) Breaking Down Barriers to Market Entry EERE Programs Buildings Vehicles Advanced Manufacturing Government Sector Solar Wind Water Biomass Geothermal Hydrogen and Fuel Cells Renewable Energy Energy Efficiency Sustainable Transportation Renewable Electricity Generation Energy-Saving Homes, Buildings & Manufacturing Washington: Battery Manufacturer Brings Material Production Home Michigan: General Motors Optimizes Engine Valve Technology Indiana: Improving Diesel Engine Performance for

251

Passive containment cooling system with drywell pressure regulation for boiling water reactor  

DOE Patents (OSTI)

A boiling water reactor is described having a regulating valve for placing the wetwell in flow communication with an intake duct of the passive containment cooling system. This subsystem can be adjusted to maintain the drywell pressure at (or slightly below or above) wetwell pressure after the initial reactor blowdown transient is over. This addition to the PCCS design has the benefit of eliminating or minimizing steam leakage from the drywell to the wetwell in the longer-term post-LOCA time period and also minimizes the temperature difference between drywell and wetwell. This in turn reduces the rate of long-term pressure buildup of the containment, thereby extending the time to reach the design pressure limit. 4 figures.

Hill, P.R.

1994-12-27T23:59:59.000Z

252

Assembly fixture for cross-shaped control rods of boiling water nuclear reactors  

Science Conference Proceedings (OSTI)

An assembly fixture is disclosed for cross-shaped control rods of boiling-water nuclear reactors with an upper core grid mesh for holding a core cell formed of four fuel assemblies having a gap therebetween and means disposed beneath the reactor core for driving the control rods in the gap, including a frame having corners formed therein, the frame being substantially the size of a core cell and being disposable on the core grid, templates diagonally oppositely disposed on the frame and extending into the core cell for lateral guidance of the control rods, stops for the control rods disposed on the templates, and a carrying handle having a first portion thereof being pivotable at one of the corners of the frame and a second portion thereof being locked to an opposite corner of the frame in a disassembled condition and swung out of the locked condition in an assembled condition.

Lippert, H.J.

1983-10-18T23:59:59.000Z

253

LIQUID PROPANE GAS (LPG) STORAGE AREA BOILING LIQUID EXPANDING VAPOR EXPLOSION (BLEVE) ANALYSIS  

SciTech Connect

The PHA and the FHAs for the SWOC MDSA (HNF-14741) identified multiple accident scenarios in which vehicles powered by flammable gases (e.g., propane), or combustible or flammable liquids (e.g., gasoline, LPG) are involved in accidents that result in an unconfined vapor cloud explosion (UVCE) or in a boiling liquid expanding vapor explosion (BLEVE), respectively. These accident scenarios are binned in the Bridge document as FIR-9 scenarios. They are postulated to occur in any of the MDSA facilities. The LPG storage area will be in the southeast corner of CWC that is relatively remote from store distaged MAR. The location is approximately 30 feet south of MO-289 and 250 feet east of 2401-W by CWC Gate 10 in a large staging area for unused pallets and equipment.

PACE, M.E.

2004-01-13T23:59:59.000Z

254

Oxygen suppression in boiling water reactors. Quarterly report 2, January 1--March 31, 1978  

DOE Green Energy (OSTI)

Boiling water reactors (BWR's) generally use high purity, no-additive feedwater. Primary recirculating coolant is neutral pH, and contains 100 to 300 ppB oxygen and stoichiometrically related dissolved hydrogen. However, oxygenated water increases austenitic stainless steel susceptibility to intergranular stress-corrosion cracking (IGSCC) when other requisite factors such as stress and sensitization are present. Thus, reduction or elimination of the oxygen in BWR water may preclude cracking incidents. One approach to reduction of the BWR coolant oxygen concentration is to adopt alternate water chemistry (AWC) conditions using an additive(s) to suppress or reverse radiolytic oxygen formation. Several additives are available to do this but they have seen only limited and specialized application in BWR's. The objective of this program is to perform an in-depth engineering evaluation of the potential suppression additives supported by critical experiments where required to resolve substantive uncertainties.

Burley, E.L.

1978-10-01T23:59:59.000Z

255

Passive containment cooling system with drywell pressure regulation for boiling water reactor  

DOE Patents (OSTI)

A boiling water reactor having a regulating valve for placing the wetwell in flow communication with an intake duct of the passive containment cooling system. This subsystem can be adjusted to maintain the drywell pressure at (or slightly below or above) wetwell pressure after the initial reactor blowdown transient is over. This addition to the PCCS design has the benefit of eliminating or minimizing steam leakage from the drywell to the wetwell in the longer-term post-LOCA time period and also minimizes the temperature difference between drywell and wetwell. This in turn reduces the rate of long-term pressure buildup of the containment, thereby extending the time to reach the design pressure limit.

Hill, Paul R. (Tucson, AZ)

1994-01-01T23:59:59.000Z

256

DESIGN STUDY OF SMALL BOILING REACTORS FOR POWER AND HEAT PRODUCTION  

SciTech Connect

A design study has been made of a small "Package" nuclear power plant for the production of electric power and heat in remotely located, inaccessible areas devoid of natural fuels. The design utilizes a horizontal boiling reactor as a steam generator consistent with safe and simple equipment and a minimum building height. A reactor design of 51/2 Mw capacity, with a combined net electric power output of 750 kw and a heat plant output of 4500 kw, was studied in detail. Tertative cost estimates are presented on the basis of this combination. General comparisons have been made between different systems designed for either independent or combined production of 425 kw net electric power and 2500 kw available heat. (auth)

Treshow, M.

1954-11-01T23:59:59.000Z

257

Materials Characterization | Advanced Materials | ORNL  

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

Characterization Nuclear Forensics Scanning Probes Related Research Materials Theory and Simulation Energy Frontier Research Centers Advanced Materials Home | Science &...

258

Measurement of Key Pool BOiling Parameters in nanofluids for Nuclerar Applications  

Science Conference Proceedings (OSTI)

Nanofluids, colloidal dispersions of nanoparticles in a base fluid such as water, can afford very significant Critical Heat Flux (CHF) enhancement. Such engineered fluids potentially could be employed in reactors as advanced coolants in safety systems with significant safety and economic advantages. However, a satisfactory explanation of the CHF enhancement mechanism in nanofluids is lacking. To close this gap, we have identified the important boiling parameters to be measured. These are the properties (e.g., density, viscosity, thermal conductivity, specific heat, vaporization enthalpy, surface tension), hydrodynamic parameters (i.e., bubble size, bubble velocity, departure frequency, hot/dry spot dynamics) and surface conditions (i.e., contact angle, nucleation site density). We have also deployed a pool boiling facility in which many such parameters can be measured. The facility is equipped with a thin indium-tin-oxide heater deposited over a sapphire substrate. An infra-red high-speed camera and an optical probe are used to measure the temperature distribution on the heater and the hydrodynamics above the heater, respectively. The first data generated with this facility already provide some clue on the CHF enhancement mechanism in nanofluids. Specifically, the progression to burnout in a pure fluid (ethanol in this case) is characterized by a smoothly-shaped and steadily-expanding hot spot. By contrast, in the ethanol-based nanofluid the hot spot pulsates and the progression to burnout lasts longer, although the nanofluid CHF is higher than the pure fluid CHF. The presence of a nanoparticle deposition layer on the heater surface seems to enhance wettability and aid hot spot dissipation, thus delaying burnout.

Bang, In C [ORNL; Buongiorno, Jdacopo [Massachusetts Institute of Technology (MIT); Hu, Lin-wen [Massachusetts Institute of Technology (MIT); Wang, Hsin [ORNL

2007-01-01T23:59:59.000Z

259

A DESIGN STUDY OF A LOW POWER AQUEOUS HOMOGENEOUS BOILING REACTOR POWER PLANT  

SciTech Connect

This design study describes a reactor and associated power plant that has been designed to produce 100 kv of net electric power and 400 kv of hot water space heating at a total thermal output of 1300 kw. The fuel consists of a solution of UO/sub 2/SO/sub 4/ in light water. Power is removed from the core by boiling the fuel solution and transferring the heat to the secondary steam system by condensing primary water on the external surface of a bayonet type boiler and boiling secondary water within the tubes. Saturated steam, produced in the boiler at 225 psia (Full Power) is used to drive a turbo generator, Extraction steam from the turbine is used, at a reduced pressure, for space heating. The initial loading of the reactor is approximately 4.8 kg of U/sub 235/ and operation based on an average load factor of 80% will require fuel addition at the rate of about 580 grams per year. It may be desirable to replace the fuel in the core after a period of 5 years operation due to the accumulation of corrosion products. The reactor control is affected automatically by power demand. The major objective has been to design a reactor that is reliable and simple, requiring little if any operating personnel and routine maintenance only which can be performed by one man. The design should stress simplicity of the system, ease of erection at the site, initial transportability, reliability and ease of operation; these characteristics are then expected to result in greatly reduced effort and manpower support over a conventional system. (auth)

Mong, B.A.; Colgan, J.E.; D' Elia, R.A.; Mooradian, J.S.; Rhode, G.K.; Wood, P.M.

1955-06-01T23:59:59.000Z

260

END POINTS MANAGEMENT End Points Management The Need for End Point Specifications  

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

MANAGEMENT MANAGEMENT End Points Management The Need for End Point Specifications The Need for a Method to Derive End Points Guiding Principles for Specifying End Points Tailored Approach Headquarters, Field Office, and Contractor Roles End Points Approvals Contractor Organization Functions for End Points Implementation Training and Walkdown Guidance for the Facility Engineers The Need for End Point Specifications The policy of the EM is that a formal project management approach be used for the planning, managing, and conducting of its projects. A fundamental premise of project management for facility deactivation is answering the question: How do you know when the project is complete? Just as the design specifications are essential to a

Note: This page contains sample records for the topic "boiling point material" 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

Effects of Carbon Nanotube Coating on Bubble Departure Diameter and Frequency in Pool Boiling on a Flat, Horizontal Heater  

E-Print Network (OSTI)

The effects of a carbon nanotube (CNT) coating on bubble departure diameter and frequency in pool boiling experiments was investigated and compared to those on a bare silicon wafer. The pool boiling experiments were performed at liquid subcooling of 10 degrees Celsius and 20 degrees Celsius using PF-5060 as the test fluid and at atmospheric pressure. High-speed digital image acquisition techniques were used to perform hydrodynamic measurements. Boiling curves obtained from the experiments showed that the CNT coating enhanced critical heat flux (CHF) by 63% at 10 degrees Celsius subcooling. The CHF condition was not measured for the CNT sample at 20 degrees Celsius subcooling. Boiling incipience superheat for the CNT-coated surface is shown to be much lower than predicted by Hsu's hypothesis. It is proposed that bubble nucleation occurs within irregularities at the surface of the CNT coating. The irregularities could provide larger cavities than are available between individual nanotubes of the CNT coating. Measurements from high-speed imaging showed that the average bubble departing from the CNT coating in the nucleate boiling regime (excluding the much larger bubbles observed near CHF) was about 75% smaller (0.26 mm versus 1.01 mm)and had a departure frequency that was about 70% higher (50.46 Hz versus 30.10 Hz). The reduction in departure diameter is explained as a change in the configuration of the contact line, although further study is required. The increase in frequency is a consequence of the smaller bubbles, which require less time to grow. It is suggested that nucleation site density for the CNT coating must drastically increase to compensate for the smaller departure diameters if the rate of vapor creation is similar to or greater than that of a bare silicon surface.

Glenn, Stephen T.

2009-08-01T23:59:59.000Z

262

NUCLEAR FUEL MATERIAL  

DOE Patents (OSTI)

An improved method is given for making the carbides of nuclear fuel material. The metal of the fuel material, which may be a fissile and/or fertile material, is transformed into a silicide, after which the silicide is comminuted to the desired particle size. This silicide is then carburized at an elevated temperature, either above or below the melting point of the silicide, to produce an intimate mixture of the carbide of the fuel material and the carbide of silicon. This mixture of the fuel material carbide and the silicon carbide is relatively stable in the presence of moisture and does not exhibit the highly reactive surface condition which is observed with fuel material carbides made by most other known methods. (AEC)

Goeddel, W.V.

1962-06-26T23:59:59.000Z

263

TEPP Points of Contact | Department of Energy  

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

Services » Waste Management » Packaging and Transportation » Services » Waste Management » Packaging and Transportation » Transportation Emergency Preparedness Program » TEPP Points of Contact TEPP Points of Contact TEPP is a national program managed at a headquarters level and implemented through the TEPP Central Operations Center managed by Technical Resources Group, Inc. For additional information on the TEPP, or to find out how you can obtain TEPP materials or schedule a class, contact either the HQ Program Manager or TEPP Central Operations. EM Contact EM Headquarters Program Manager Ella McNeil, Office of Transportation Ella.McNeil@em.doe.gov U.S. Department of Energy Washington, DC 20585 TEPP Central Operations admin@merrtt.com 208-528-8895 Waste Management Nuclear Materials & Waste Tank Waste and Waste Processing

264

PowerPoint Presentation  

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

Aqueous Rechargeable Lithium Batteries (ARLBs) Aqueous Rechargeable Lithium Batteries (ARLBs) of High Energy Density Prof. Dr. Yuping Wu New Energy and Materials Laboratory (NEML), Department of Chemistry, Fudan University, Shanghai 200433 Tel/Fax: +86-21-5566 4223 Email: wuyp@fudan.edu.cn @ 6th US-China Electric Vehicles and Battery Technology Workshop, Boston 23-24 August, 2012 Motto of NEML Electrochemical technologies 4E + E Energy problem Environmental pollution Enjoy life Solve Reduce To cultivate Elites for the society. 1. Chemical Power Sources * Supercapacitors * Polysulfide bromide battery (PSB) * Zn/Br battery * Vanadium redox couples (VRC) * Sodium sulfur battery (Na/S) * Lead acid battery * Metal-air battery * Ni-MH * Lithium ion battery * Safety * Rate capability

265

PowerPoint Presentation  

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

NERSC Cray XT4 NERSC Cray XT4 Helen He NERSC User Services yhe@lbl.gov NERSC User Group Meeting September 17-20, 2007 1 Training Topics * Overview * XT4 Architecture * PGI Compiler * Single Node and MPI Optimizations * Performance and Profiling Tools * Running Jobs * Third-party Softwares * ACTS Tools * DDT Debugger * I/O * Grid Services * Benchmark Performance 2 Benjamin Franklin, one of America's first scientists, performed ground breaking work in energy efficiency, electricity, materials, climate, ocean currents, transportation, health, medicine, acoustics and heat transfer. Franklin Franklin 3 About Franklin * Largest Cray XT-4 * 9,740 nodes with 19,480 CPU (cores) * dual-core AMD Opteron 2.6 GHz, 5.2 GFlops/sec peak * 102 node cabinets * 16 KWs per cabinet (~1.7 MWs total) * 39.5 TBs aggregate memory * 16.1+ Tflop/s

266

PowerPoint Presentation  

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

Ingersoll, F.M. Delnick, and K.E. Waldrip Ingersoll, F.M. Delnick, and K.E. Waldrip Sandia National Laboratories PO Box 5800 Albuquerque, NM 87185-0614 High Voltage Electrochemical Capacitor presented at EESAT 2007 September 23-27, 2007 PEER Review San Francisco, CA Sandia is a multi-program laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000. 2 Objective * New Start - 7/07 * Increasing the energy of the system * Energy = 1/2 CV 2 * Four general means to increasing energy - Increased surface area - most common approach * A - active area of electrode - high surface area materials (carbon - typically > 1000 m 2 /g) - nanomaterials (e.g. carbon multiwalled nanotube) - Employ Faradaic processes -

267

PowerPoint Presentation  

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

Combined Pressure and Temperature Contrast and Combined Pressure and Temperature Contrast and Surface-enhanced Separation of Carbon-dioxide for Post-combustion Carbon Capture Dr. Michael S. Wong Professor in Chemical and Biomolecular Engineering, Chemistry and Environmental Engineering Rice University NETL CO 2 Capture Technology Meeting July 10 th , 2013 DOE Project # DE0007531 Project Manager: Ms. Elaine Everitt Outline * About Rice University * Project Overview * Project Team * Combined Pressure and Temperature Contrast and Surface- enhanced Separation of Carbon-dioxide * Selection of materials * Integrated absorber and stripper - A proof-of-concept demonstration * Substrate functionalization * Project Budget 2 * Located in Houston, TX * 295-acre, heavily wooded campus * Ranked 17 th in the US and in the

268

PowerPoint Presentation  

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

National Laboratory Mentor-Protégé Program Business Success Stories Presented by Cassandra McGee Stuart ORNL Small Business Programs Office May 23, 2013 2 Presentation name Today, ORNL is DOE's largest science and energy laboratory 2 Managed by UT-Battelle for the U.S. Department of Energy $1.65B budget World's most intense neutron source 4,400 employees World-class research reactor 3,000 research guests annually $500M modernization investment Nation's largest materials research portfolio Most powerful open scientific computing facility Nation's most diverse energy portfolio Managing billion-dollar U.S. ITER project 3 Managed by UT-Battelle for the U.S. Department of Energy ORNL is managed by UT-Battelle, LLC * A 65-year relationship with DOE

269

PowerPoint Presentation  

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

Dual Interconnect Coatings for Planar SOFC Dual Interconnect Coatings for Planar SOFC Stacks Jung Pyung Choi, Jeffry W. Stevenson, K. Scott Weil, Yeong-Shyung Chou, Z. Gary Yang, and Gordon Xia Fuel Cell, P.O.Box999, Pacific Northwest National Laboratory, Richland, WA 99352, USA About Pacific Northwest National Laboratory The Pacific Northwest National Laboratory, located in southeastern Washington State, is a U.S. Department of Energy Office of Science laboratory that solves complex problems in energy, national security and the environment, and advances scientific frontiers in the chemical, biological, materials, environmental and computational sciences. The Laboratory employs 4,000 staff members, has a $760 million annual budget, and has been managed by Ohio-based Battelle since 1965. For more information about the science

270

PowerPoint Presentation  

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

Ramesh Ramesh Gupta, March 30, 2010 Initial Design of 200 mm, 6 T Superconducting Solenoid for e-lens Ramesh Gupta March 30, 2010 Ramesh Gupta, March 30, 2010 Main Features * Dipole copper correctors that were previously inside the solenoid coil are now moved outside the solenoid coil and are made superconducting. * This significantly reduces the aperture (~292 mm to ~200 mm). * This reduces the stored energy and Lorentz forces and thus makes the smaller aperture superconducting solenoid less demanding. * This also reduces the material cost - less superconductor, iron, etc. * In addition, there are some cost saving specific to us because of  the use of existing stainless steel shell.  the use of RHIC cryostat.  the use of existing tooling.  However, this makes corrector more complex in construction(?) and

271

PowerPoint Presentation  

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

This presentation was given for the This presentation was given for the Navigant Research Webinar on Fast DC Charging for Electric Vehicles * http://www.navigantresearch.com/webinar/fast-dc-charging-for-electric-vehicles * April 9, 2013 1 Lessons Learned on the EV Project and DC Fast Charging Garrett Beauregard Executive Vice President and General Manager, eTec Labs April 9, 2013 ECOtality Company Overview Leading Hardware, Software and R&D for electric transportation Diversified revenue base of 3 complementary business segments Blink * Residential, public & commercial EV charging solutions * Contracted by U.S. Dept. of Energy for The EV Project (~$115M) * Over 11,000 chargers installed as of April 2013 Minit-Charger * Fast charging electric material handling and ground support equipment

272

Materials Science  

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

Materials Science Materials Science Materials Science1354608000000Materials ScienceSome of these resources are LANL-only and will require Remote Access./No/Questions? 667-5809library@lanl.gov Materials Science Some of these resources are LANL-only and will require Remote Access. Key Resources Data Sources Reference Organizations Journals Key Resources CINDAS Materials Property Databases video icon Thermophysical Properties of Matter Database (TPMD) Aerospace Structural Metals Database (ASMD) Damage Tolerant Design Handbook (DTDH) Microelectronics Packaging Materials Database (MPMD) Structural Alloys Handbook (SAH) Proquest Technology Collection Includes the Materials Science collection MRS Online Proceedings Library Papers presented at meetings of the Materials Research Society Data Sources

273

Program on Technology Innovation: Environmentally Assisted Cracking in LWR Structural Materials, 2011 PEACE-E Annual Report  

Science Conference Proceedings (OSTI)

This report describes the interim results of PEACE-E, a joint research program sponsored by the Electric Power Research Institute (EPRI) in collaboration with the Fracture & Reliability Research Institute (FRRI) at Tohoku University, Japanese utilities, vendors, and international organizations. The program addressed environmentally assisted cracking of light water reactor structural materials in pressurized water reactor (PWR) and boiling water reactor (BWR) environments.

2011-12-23T23:59:59.000Z

274

Materials Reliability Program: A Review of the Cooperative Irradiation Assisted Stress Corrosion Cracking Research Program (MRP-98)  

Science Conference Proceedings (OSTI)

Irradiation-assisted stress corrosion cracking (IASCC) has been observed in reactor core internal structures fabricated from austenitic stainless steels in both pressurized water reactors (PWRs) and boiling water reactors (BWRs). This report reviews EPRI's Cooperative IASCC Research (CIR) Program data and findings relevant to materials aging and degradation of PWR vessel internals components.

2003-12-04T23:59:59.000Z

275

Reactor Materials  

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

The reactor materials crosscut effort will enable the development of innovative and revolutionary materials and provide broad-based, modern materials science that will benefit all four DOE-NE...

276

Application of the base catalyzed decomposition process to treatment of PCB-contaminated insulation and other materials associated with US Navy vessels. Final report  

SciTech Connect

The BCD process was applied to dechlorination of two types of PCB-contaminated materials generated from Navy vessel decommissioning activities at Puget Sound Naval Shipyard: insulation of wool felt impregnated with PCB, and PCB-containing paint chips/debris from removal of paint from metal surfaces. The BCD process is a two-stage, low-temperature chemical dehalogenation process. In Stage 1, the materials are mixed with sodium bicarbonate and heated to 350 C. The volatilized halogenated contaminants (eg, PCBs, dioxins, furans), which are collected in a small volume of particulates and granular activated carbon, are decomposed by the liquid-phase reaction (Stage 2) in a stirred-tank reactor, using a high-boiling-point hydrocarbon oil as the reaction medium, with addition of a hydrogen donor, a base (NaOH), and a catalyst. The tests showed that treating wool felt insulation and paint chip wastes with Stage 2 on a large scale is feasible, but compared with current disposal costs for PCB-contaminated materials, using Stage 2 would not be economical at this time. For paint chips generated from shot/sand blasting, the solid-phase BCD process (Stage 1) should be considered, if paint removal activities are accelerated in the future.

Schmidt, A.J.; Zacher, A.H.; Gano, S.R.

1996-09-01T23:59:59.000Z

277

On Convex Decompositions of Points  

Science Conference Proceedings (OSTI)

Given a planar point set in general position, S, we seek a partition of the points into convex cells, such that the union of the cells forms a simple polygon, P, and every point from S is on the boundary of P. Let f(S) ...

Kiyoshi Hosono; David Rappaport; Masatsugu Urabe

2000-11-01T23:59:59.000Z

278

Materials - Assessment  

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

Materials Assessment The staff of the Energy Systems Division has a long history of technical and economic analysis of the production and recycling of materials for transportation...

279

Materials Science  

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

Materials Science science-innovationassetsimagesicon-science.jpg Materials Science National security depends on science and technology. The United States relies on Los Alamos...

280

NETL: Utilization Projects - Novel Materials Development Using...  

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

include: (1) Characterize different fractions of gasification byproducts from the Polk Power plant from a materials development point of view. These characterization studies...

Note: This page contains sample records for the topic "boiling point material" 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

Thermoelectric Materials  

Science Conference Proceedings (OSTI)

Thermoelectric materials can generate electricity or provide cooling by converting thermal gradients to electricity or electricity to thermal gradients. More efficient thermoelectric materials would make feasible the widespread use of thermoelectric converters in mundane applications. This report summarizes the state-of-the-art of thermoelectric materials including currently available materials and applications, new developments, and future prospects.

2000-01-14T23:59:59.000Z

282

Design of a boiling water reactor equilibrium core using thorium-uranium fuel  

SciTech Connect

In this paper the design of a Boiling Water Reactor (BWR) equilibrium core using thorium is presented; a heterogeneous blanket-seed core arrangement concept was adopted. The design was developed in three steps: in the first step two different assemblies were designed based on the integrated blanket-seed concept, they are the blanket-dummy assembly and the blanket-seed assembly. The integrated blanketseed concept comes from the fact that the blanket and the seed rods are located in the same assembly, and are burned-out in a once-through cycle. In the second step, a core design was developed to achieve an equilibrium cycle of 365 effective full power days in a standard BWR with a reload of 104 fuel assemblies designed with an average 235U enrichment of 7.5 w/o in the seed sub-lattice. The main operating parameters, like power, linear heat generation rate and void distributions were obtained as well as the shutdown margin. It was observed that the analyzed parameters behave like those obtained in a standard BWR. The shutdown margin design criterion was fulfilled by addition of a burnable poison region in the assembly. In the third step an in-house code was developed to evaluate the thorium equilibrium core under transient conditions. A stability analysis was also performed. Regarding the stability analysis, five operational states were analyzed; four of them define the traditional instability region corner of the power-flow map and the fifth one is the operational state for the full power condition. The frequency and the boiling length were calculated for each operational state. The frequency of the analyzed operational states was similar to that reported for BWRs; these are close to the unstable region that occurs due to the density wave oscillation phenomena in some nuclear power plants. Four transient analyses were also performed: manual SCRAM, recirculation pumps trip, main steam isolation valves closure and loss of feed water. The results of these transients are similar to those obtained with the traditional UO2 nuclear fuel.

Francois, J-L.; Nunez-Carrera, A.; Espinosa-Paredes, G.; Martin-del-Campo, C.

2004-10-06T23:59:59.000Z

283

FUEL CYCLE PROGRAM, A BOILING WATER REACTOR RESEARCH DEVELOPMENT PROGRAM. First Summary Report for March 1959-July 1960  

SciTech Connect

The Fuel Cycle Development Program is a basic development program for boiling and other water technology. It covers the areas of oxide fuel fabrication. irradiation. and examination; the physics of water-moderated reactore; and boiling-water heat transfer and stability. Schedules for the fuel- cycle program were examined. and it was concluded that portions of the Task A program should be conducted during the period May to Dec. 1959 in order to keep costs of the work as low as possible and to allow initiation of the fuel-cycle program at the earliest possible date after the Vallecitos BWR was returned to service. The basis for the scheduling of the work is discussed. and a chronological summary describing the content of the work is given. Technical progress is outlined and details are summarized. Subsequent reports issued monthly and quarterly will summarize the progress of the prognam. (W.D.M.)

Cook, W.H.

1961-10-31T23:59:59.000Z

284

Investigation of the pool boiling heat transfer enhancement of nano-engineered fluids by means of high-speed infrared thermography  

E-Print Network (OSTI)

A high-speed video and infrared thermography based technique has been used to obtain detailed and fundamental time- and space-resolved information on pool boiling heat transfer. The work is enabled by recent advances in ...

Gerardi, Craig Douglas

2009-01-01T23:59:59.000Z

285

An investigation of the physical and numerical foundations of two-fluid representation of sodium boiling with applications to LMFBR experiments  

E-Print Network (OSTI)

This work involves the development of physical models for the constitutive relations of a two-fuid, three-dimensional sodium boiling code, THERMIT-6S. The code is equipped with a fluid conduction model, a fuel pin model, ...

No, Hee Cheon

1983-01-01T23:59:59.000Z

286

Nuclear fuel elements made from nanophase materials  

SciTech Connect

A nuclear reactor core fuel element is composed of nanophase high temperature materials. An array of the fuel elements in rod form are joined in an open geometry fuel cell that preferably also uses such nanophase materials for the cell structures. The particular high temperature nanophase fuel element material must have the appropriate mechanical characteristics to avoid strain related failure even at high temperatures, in the order of about 3000.degree. F. Preferably, the reactor type is a pressurized or boiling water reactor and the nanophase material is a high temperature ceramic or ceramic composite. Nanophase metals, or nanophase metals with nanophase ceramics in a composite mixture, also have desirable characteristics, although their temperature capability is not as great as with all-ceramic nanophase material. Combinations of conventional or nanophase metals and conventional or nanophase ceramics can be employed as long as there is at least one nanophase material in the composite. The nuclear reactor so constructed has a number of high strength fuel particles, a nanophase structural material for supporting a fuel rod at high temperature, a configuration to allow passive cooling in the event of a primary cooling system failure, an ability to retain a coolable geometry even at high temperatures, an ability to resist generation of hydrogen gas, and a configuration having good nuclear, corrosion, and mechanical characteristics.

Heubeck, Norman B. (Schenectady, NY)

1998-01-01T23:59:59.000Z

287

Nuclear fuel elements made from nanophase materials  

DOE Patents (OSTI)

A nuclear reactor core fuel element is composed of nanophase high temperature materials. An array of the fuel elements in rod form are joined in an open geometry fuel cell that preferably also uses such nanophase materials for the cell structures. The particular high temperature nanophase fuel element material must have the appropriate mechanical characteristics to avoid strain-related failure even at high temperatures, in the order of about 3,000 F. Preferably, the reactor type is a pressurized or boiling water reactor and the nanophase material is a high temperature ceramic or ceramic composite. Nanophase metals, or nanophase metals with nanophase ceramics in a composite mixture, also have desirable characteristics, although their temperature capability is not as great as with all ceramic nanophase material. Combinations of conventional or nanophase metals and conventional or nanophase ceramics can be employed as long as there is at least one nanophase material in the composite. The nuclear reactor so constructed has a number of high strength fuel particles, a nanophase structural material for supporting a fuel rod at high temperature, a configuration to allow passive cooling in the event of a primary cooling system failure, an ability to retain a coolable geometry even at high temperatures, an ability to resist generation of hydrogen gas, and a configuration having good nuclear, corrosion and mechanical characteristics.

Heubeck, Norman B.

1997-12-01T23:59:59.000Z

288

Nuclear fuel elements made from nanophase materials  

DOE Patents (OSTI)

A nuclear reactor core fuel element is composed of nanophase high temperature materials. An array of the fuel elements in rod form are joined in an open geometry fuel cell that preferably also uses such nanophase materials for the cell structures. The particular high temperature nanophase fuel element material must have the appropriate mechanical characteristics to avoid strain related failure even at high temperatures, in the order of about 3000 F. Preferably, the reactor type is a pressurized or boiling water reactor and the nanophase material is a high temperature ceramic or ceramic composite. Nanophase metals, or nanophase metals with nanophase ceramics in a composite mixture, also have desirable characteristics, although their temperature capability is not as great as with all-ceramic nanophase material. Combinations of conventional or nanophase metals and conventional or nanophase ceramics can be employed as long as there is at least one nanophase material in the composite. The nuclear reactor so constructed has a number of high strength fuel particles, a nanophase structural material for supporting a fuel rod at high temperature, a configuration to allow passive cooling in the event of a primary cooling system failure, an ability to retain a coolable geometry even at high temperatures, an ability to resist generation of hydrogen gas, and a configuration having good nuclear, corrosion, and mechanical characteristics. 5 figs.

Heubeck, N.B.

1998-09-08T23:59:59.000Z

289

Interfacing systems LOCAs (Loss of Coolant Accidents) at boiling water reactors  

Science Conference Proceedings (OSTI)

The work presented in this paper was performed by Brookhaven National Laboratory (BNL) in support of Nuclear Regulatory Commission's (NRC) effort towards the resolution of Generic Issue 105 ''Interfacing System Loss of Coolant Accidents (LOCAs) at Boiling Water Reactors (BWRs).'' For BWRs, intersystem LOCA have typically either not been considered in probabilistic risk analyses, or if considered, were judged to contribute little to the risk estimates because of their perceived low frequency of occurrence. However, recent operating experience indicates that the pressure isolation valves (PIVs) in BWRs may not adequately protect against overpressurization of low pressure systems. The objective of this paper is to present the results of a study which analyzed interfacing system LOCA at several BWRs. The BWRs were selected to best represent a spectrum of BWRs in service using industry operating event experience and plant-specific information/configurations. The results presented here include some possible changes in test requirements/practices as well as an evaluation of their reduction potential in terms of core damage frequency (CDF).

Chu, Tsong-Lun; Fitzpatrick, R.; Stoyanov, S.

1987-01-01T23:59:59.000Z

290

Knowledge and abilities catalog for nuclear power plant operators: Boiling water reactors, Revision 1  

SciTech Connect

The Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Boiling-Water Reactors (BWRs) (NUREG-1123, Revision 1) provides the basis for the development of content-valid licensing examinations for reactor operators (ROs) and senior reactor operators (SROs). The examinations developed using the BWR Catalog along with the Operator Licensing Examiner Standards (NUREG-1021) and the Examiner`s Handbook for Developing Operator Licensing Written Examinations (NUREG/BR-0122), will cover the topics listed under Title 10, Code of Federal Regulations, Part 55 (10 CFR 55). The BWR Catalog contains approximately 7,000 knowledge and ability (K/A) statements for ROs and SROs at BWRs. The catalog is organized into six major sections: Organization of the Catalog, Generic Knowledge and Ability Statements, Plant Systems grouped by Safety Functions, Emergency and Abnormal Plant Evolutions, Components, and Theory. Revision 1 to the BWR Catalog represents a modification in form and content of the original catalog. The K/As were linked to their applicable 10 CFR 55 item numbers. SRO level K/As were identified by 10 CFR 55.43 item numbers. The plant-wide generic and system generic K/As were combined in one section with approximately one hundred new K/As. Component Cooling Water and Instrument Air Systems were added to the Systems Section. Finally, High Containment Hydrogen Concentration and Plant Fire On Site evolutions added to the Emergency and Abnormal Plant Evolutions section.

NONE

1995-08-01T23:59:59.000Z

291

Multivent effects in a large scale boiling water reactor pressure suppression system  

Science Conference Proceedings (OSTI)

The steam-driven GKSS pressure suppression test facility, which contains 3 full scale vent pipes, has been used for 5 years to investigate the postulated loss-of-coolant accident in a Mark II and Type 69 boiling water reactor. Using the results from several of these tests, wetwell boundary load data (peak pressures and spectral power) during the chugging stage, have been evaluated for sparse pool response (one and two vents in the three vent pool) and for full pool response (one, two, or three vent operation in pools of constant wetwell pool area per vent). The sparse pool results indicate the pool-system, chug event boundary loads are strongly dependent on wetwell pool area per vent, with the load increasing with decreasing area. The full pool results show a substantial increase in the pool-system, chug event boundary loads upon a change from single cell to double cell operation; only minor change occurs in going from double to triple cell operation.

McCauley, E.W.; Aust, E.; Schwan, H.

1984-07-06T23:59:59.000Z

292

An Improved Model for Assessing the Effectiveness of Hydrogen Water Chemistry in Boiling Water Reactors  

Science Conference Proceedings (OSTI)

For nearly two decades, hydrogen water chemistry (HWC) has been used as a remedial measure to protect boiling water reactor (BWR) structural components against intergranular stress corrosion cracking (IGSCC). In this paper, computer modeling is used to evaluate the effectiveness of HWC for BWRs. The DEMACE computer code, equipped with an updated chemical reaction set, G values, and a Sherwood number, is adopted to predict the chemical species concentration and electrochemical corrosion potential (ECP) responses to HWC in the primary heat transport circuit of a typical BWR. In addition, plant-specific neutron and gamma dose rate profiles are reported. DEMACE is calibrated against the data of oxygen concentration variation as a function of feedwater hydrogen concentration in the recirculation system of the Chinshan Unit 2 BWR.The determinant result for assessing the effectiveness of HWC is the ECP. For a typical BWR/4-type reactor such as Chinshan Unit 2, it is found that protecting the core channel and the lower plenum outlet is quite difficult even though the feedwater hydrogen concentration is as high as 2 ppm, based on the predicted species concentration and ECP data. However, for regions other than those mentioned earlier, a moderate amount of hydrogen added to the feedwater (0.9 ppm) is enough to achieve the desired protection against IGSCC.

Yeh, T.-K. [National Tsing-Hua University, Taiwan (China); Chu Fang [Taiwan Power Company (China)

2001-10-15T23:59:59.000Z

293

A Numerical Model for Evaluating the Impact of Noble Metal Chemical Addition in Boiling Water Reactors  

SciTech Connect

The technique of noble metal chemical addition (NMCA), accompanied by a low-level hydrogen water chemistry (HWC), is being employed by several U.S. nuclear power plants for mitigating intergranular stress corrosion cracking in the vessel internals of their boiling water reactors (BWRs). An improved computer model by the name of DEMACE was employed to evaluate the performance of NMCA throughout the primary coolant circuit (PCC) of a commercial BWR. The molar ratios of hydrogen to oxidizing species in the PCC under normal water chemistry and HWC are analyzed. The effectiveness of NMCA is justified by calculated electrochemical corrosion potential (ECP) around the PCC and in a local power range monitoring (LPRM) housing tube, in which practical in-vessel ECP measurements are normally taken.Prior to the modeling work for the BWR, the Mixed Potential Model, which is embedded in DEMACE and responsible for ECP calculation, was calibrated against both laboratory and plant ECP data. After modeling for various HWC conditions, it is found that the effectiveness of NMCA in the PCC of the selected BWR varies from region to region. In particular, the predicted ECP in the LPRM housing tube is notably different from that in the nearby bulk environment under NMCA, indicating that cautions must be given to a possible, undesirable outcome due to a distinct ECP difference between a locally confined area and the actual bulk environment.

Yeh, T.-K. [National Tsing-Hua University, Taiwan (China)

2002-10-15T23:59:59.000Z

294

Enhancement of Heat Transfer with Pool and Spray Impingement Boiling on Microporous and Nanowire Surface Coatings  

DOE Green Energy (OSTI)

The DOE National Renewable Energy Laboratory (NREL) is leading a national effort to develop next-generation cooling technologies for hybrid vehicle electronics. The goal is to reduce the size, weight, and cost of power electronic modules that convert direct current from batteries to alternating current for the motor, and vice versa. Aggressive thermal management techniques help to increase power density and reduce weight and volume, while keeping chip temperatures within acceptable limits. The viability of aggressive cooling schemes such as spray and jet impingement in conjunction with enhanced surfaces is being explored. Here, we present results from a series of experiments with pool and spray boiling on enhanced surfaces, such as a microporous layer of copper and copper nanowires, using HFE-7100 as the working fluid. Spray impingement on the microporous coated surface showed an enhancement of 100%-300% in the heat transfer coefficient at a given wall superheat with respect to spray impingement on a plain surface under similar operating conditions. Critical heat flux also increased by 7%-20%, depending on flow rates.

Thiagarajan, S. J.; Wang, W.; Yang, R.; Narumanchi, S.; King, C.

2010-09-01T23:59:59.000Z

295

Decontamination and decommissioning of the Experimental Boiling Water Reactor (EBWR): Project final report, Argonne National Laboratory  

SciTech Connect

The Final Report for the Decontamination and Decommissioning (D&D) of the Argonne National Laboratory - East (ANL-E) Experimental Boiling Water Reactor (EBWR) facility contains the descriptions and evaluations of the activities and the results of the EBWR D&D project. It provides the following information: (1) An overall description of the ANL-E site and EBWR facility. (2) The history of the EBWR facility. (3) A description of the D&D activities conducted during the EBWR project. (4) A summary of the final status of the facility, including the final and confirmation surveys. (5) A summary of the final cost, schedule, and personnel exposure associated with the project, including a summary of the total waste generated. This project report covers the entire EBWR D&D project, from the initiation of Phase I activities to final project closeout. After the confirmation survey, the EBWR facility was released as a {open_quotes}Radiologically Controlled Area,{close_quotes} noting residual elevated activity remains in inaccessible areas. However, exposure levels in accessible areas are at background levels. Personnel working in accessible areas do not need Radiation Work Permits, radiation monitors, or other radiological controls. Planned use for the containment structure is as an interim transuranic waste storage facility (after conversion).

Fellhauer, C.R.; Boing, L.E. [Argonne National Lab., IL (United States); Aldana, J. [NES, Inc., Danbury, CT (United States)

1997-03-01T23:59:59.000Z

296

Experimental studies of adiabatic flow boiling in fractal-like branching microchannels  

SciTech Connect

Experimental results of adiabatic boiling of water flowing through a fractal-like branching microchannel network are presented and compared to numerical model simulations. The goal is to assess the ability of current pressure loss models applied to a bifurcating flow geometry. The fractal-like branching channel network is based on channel length and width ratios between adjacent branching levels of 2{sup -1/2}. There are four branching sections for a total flow length of 18 mm, a channel height of 150 {mu}m and a terminal channel width of 100 {mu}m. The channels were Deep Reactive Ion Etched (DRIE) into a silicon disk. A Pyrex disk was anodically bonded to the silicon to form the channel top to allow visualization of the flow within the channels. The flow rates ranged from 100 to 225 g/min and the inlet subcooling levels varied from 0.5 to 6 C. Pressure drop along the flow network and time averaged void fraction in each branching level were measured for each of the test conditions. The measured pressure drop ranged from 20 to 90 kPa, and the measured void fraction ranged from 0.3 to 0.9. The measured pressure drop results agree well with separated flow model predictions accounting for the varying flow geometry. The measured void fraction results followed the same trends as the model; however, the scatter in the experimental results is rather large. (author)

Daniels, Brian J.; Liburdy, James A.; Pence, Deborah V. [Mechanical Engineering, Oregon State University, Corvallis, OR 97330 (United States)

2011-01-15T23:59:59.000Z

297

Impact of aspect ratio on flow boiling of water in rectangular microchannels  

SciTech Connect

In this paper we focus on the impact of varying the aspect ratio of rectangular microchannels, on the overall pressure drop involving water boiling. An integrated system comprising micro-heaters, sensors and microchannels has been realized on (110) silicon wafers, following CMOS compatible process steps. Rectangular microchannels were fabricated with varying aspect ratios (width [W] to depth [H]) but constant hydraulic diameter of 142{+-}2{mu}m and length of 20 mm. The invariant nature of the hydraulic diameter is confirmed through two independent means: physical measurements using profilometer and by measuring the pressure drop in single-phase fluid flow. The experimental results show that the pressure drop for two-phase flow in rectangular microchannels experiences minima at an aspect ratio of about 1.6. The minimum is possibly due to opposing trends of frictional and acceleration pressure drops, with respect to aspect ratio. In a certain heat flux and mass flux range, it is observed that the two-phase pressure drop is lower than the corresponding single-phase value. This is the first study to investigate the effect of aspect ratio in two-phase flow in microchannels, to the best of our knowledge. The results are in qualitative agreement with annular flow model predictions. These results improve the possibility of designing effective heat-sinks based on two-phase fluid flow in microchannels. (author)

Singh, S.G.; Kulkarni, A.; Duttagupta, S.P. [Nanoelectronics Center, Department of Electrical Engineering, Indian Institute of Technology Bombay, Powai, Mumbai 400 076 (India); Puranik, B.P.; Agrawal, A. [Suman Mashruwala Lab, Department of Mechanical Engineering, Indian Institute of Technology Bombay, Powai, Mumbai 400 076 (India)

2008-10-15T23:59:59.000Z

298

Florida Nuclear Profile - Turkey Point  

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

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

299

The toxicity of X material  

SciTech Connect

This report addresses toxicity (largely chemical) of Manhattan Project materials from the point of worker protection. Known chemical toxicities of X material (uranium), nitrous fumes, fluorine, vanadium, magnesium, and lime are described followed by safe exposure levels, symptoms of exposure, and treatment recommendations. The report closes with an overview of general policy in a question and answer format.

Ferry, J.L.

1943-12-31T23:59:59.000Z

300

NaK pool-boiler bench-scale receiver durability test: Test results and materials analysis  

DOE Green Energy (OSTI)

Pool-boiler reflux receivers have been considered as an alternative to heat pipes for the input of concentrated solar energy to Stirling-cycle engines in dish-Stirling electric generation systems. Pool boilers offer simplicity in design and fabrication. The operation of a full-scale pool-boiler receiver has been demonstrated for short periods of time. However, to generate cost-effective electricity, the receiver must operate Without significant maintenance for the entire system life, as much as 20 to 30 years. Long-term liquid-metal boiling stability and materials compatibility with refluxing NaK-78 is not known and must be determined for the pool boiler receiver. No boiling system has been demonstrated for a significant duration with the current porous boiling enhancement surface and materials. Therefore, it is necessary to simulate the full-scale pool boiler design as much as possible, including flux levels, materials, and operating cycles. On-sun testing is impractical because of the limited test time available. A test vessel was constructed with a porous boiling enhancement surface. The boiling surface consisted of a brazed stainless steel powder with about 50% porosity. The vessel was heated with a quartz lamp array providing about go W/CM2 peak incident thermal flux. The vessel was charged with NaK-78. This allows the elimination of costly electric preheating, both on this test and on fullscale receivers. The vessel was fabricated from Haynes 230 alloy. The vessel operated at 750{degrees}C around the clock, with a 1/2-hour shutdown cycle to ambient every 8 hours. The test completed 7500 hours of lamp-on operation time, and over 1000 startups from ambient. The test was terminated when a small leak in an Inconel 600 thermowell was detected. The test design and data are presented here. Metallurgical analysis of virgin and tested materials has begun, and initial results are also presented.

Andraka, C.E.; Goods, S.H.; Bradshaw, R.W.; Moreno, J.B.; Moss, T.A.; Jones, S.A.

1994-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "boiling point material" 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.


301

Magnetocaloric Materials  

Science Conference Proceedings (OSTI)

Magnetic Materials for Energy Applications IV: Magnetocaloric Materials ... due to cost-effectiveness as well as superior magneto-thermal characteristics. ... metals and p-block elements can be explored in a time- and energy-saving manner.

302

Materials Science  

Science Conference Proceedings (OSTI)

Materials Science. Summary: Key metrologies/systems: In situ spectroscopic ellipsometry, linear and non-linear spectroscopies ...

2012-10-02T23:59:59.000Z

303

Training Materials  

Science Conference Proceedings (OSTI)

Training Materials. NIST Handbook 44 Self-Study Course. ... Chapter 3 – Organization and Format of NIST Handbook 44 DOC. ...

2011-08-10T23:59:59.000Z

304

Evaluation of multiple emission point facilities  

SciTech Connect

In 1970, the New York State Department of Environmental Conservation (NYSDEC) assumed responsibility for the environmental aspect of the state's regulatory program for by-product, source, and special nuclear material. The major objective of this study was to provide consultation to NYSDEC and the US NRC to assist NYSDEC in determining if broad-based licensed facilities with multiple emission points were in compliance with NYCRR Part 380. Under this contract, BNL would evaluate a multiple emission point facility, identified by NYSDEC, as a case study. The review would be a nonbinding evaluation of the facility to determine likely dispersion characteristics, compliance with specified release limits, and implementation of the ALARA philosophy regarding effluent release practices. From the data collected, guidance as to areas of future investigation and the impact of new federal regulations were to be developed. Reported here is the case study for the University of Rochester, Strong Memorial Medical Center and Riverside Campus.

Miltenberger, R.P.; Hull, A.P.; Strachan, S.; Tichler, J.

1988-01-01T23:59:59.000Z

305

Material matting  

Science Conference Proceedings (OSTI)

Despite the widespread use of measured real-world materials, intuitive tools for editing measured reflectance datasets are still lacking. We present a solution inspired by natural image matting and texture synthesis to the material matting problem, ... Keywords: appearance models, material separation, matting, spatially-varying BRDFs, texture synthesis

Daniel Lepage; Jason Lawrence

2011-12-01T23:59:59.000Z

306

Materializing energy  

Science Conference Proceedings (OSTI)

Motivated and informed by perspectives on sustainability and design, this paper draws on a diverse body of scholarly works related to energy and materiality to articulate a perspective on energy-as-materiality and propose a design approach of ... Keywords: design, design theory, energy, materiality, sustainability

James Pierce; Eric Paulos

2010-08-01T23:59:59.000Z

307

Materials Education Community  

Science Conference Proceedings (OSTI)

Digital Resource Center Home. Materials Education. Materials Education. Established Materials Technologies. Magnesium · Superalloys. Emerging Materials ...

308

Emerging Materials Technologies  

Science Conference Proceedings (OSTI)

Digital Resource Center Home. Materials Education. Materials Education. Established Materials Technologies. Magnesium · Superalloys. Emerging Materials ...

309

Established Materials Technologies  

Science Conference Proceedings (OSTI)

Digital Resource Center Home. Materials Education. Materials Education. Established Materials Technologies. Magnesium · Superalloys. Emerging Materials ...

310

Points  

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

Project Selections Project Selections Announced October 26, 2009 Lead Research Organization (Partner Organizations) DOE Grant Amount Lead Organization Location Project Description 1366 Technologies Inc. (Massachusetts Institute of Technology - Lab for PV Research) $4,000,000 Lexington, MA Renewable Power (solar) "Direct Wafer" technology to form high efficiency "monocrystalline- equivalent" silicon wafers directly from molten silicon, with potential to halve the installed cost of solar photovoltaics. Agrivida, Inc. $4,565,800 Medford, MA Biomass Energy Cell wall-degrading enzymes grown within the plant itself that are activated after harvest, dramatically reducing the cost of cellulosic biofuels and chemicals Arizona State University (Fluidic Energy,

311

Program on Technology Innovation: Prediction and Evaluation of Environmentally Assisted Cracking in LWR Structural Materials: 2011 P EACE-E Phase II Report  

Science Conference Proceedings (OSTI)

This report describes the interim results of PEACE-E, a joint research program sponsored by the Electric Power Research Institute (EPRI) in collaboration with the Fracture & Reliability Research Institute (FRRI) at Tohoku University, Japanese utilities, vendors, and international organizations. The program addressed environmentally assisted cracking (EAC) of light water reactor (LWR) structural materials in pressurized water reactor (PWR) and boiling water reactor (BWR) ...

2012-12-23T23:59:59.000Z

312

Analysis of the Simplified Boiling Water Reactor using the code Ramona-4B  

E-Print Network (OSTI)

The analysis of the Simplified Boiling Water Reactor (SBVVR) is carried out through the use of the reactor analysis code RAMONA-4B in a scenario of an operational transient, a turbine trip with failure of all the bypass valves. This study is divided in three parts. As an introduction, a brief description of the code RAMONA-4B. Later, the implemented SBWR model, based on the General Electric Standard Safety Analysis Report (SSAR), is described and discussed. Finally, the reactor behavior during a turbine trip transient is numerically simulated through the description of nuclear and thermal hydraulic parameters and under the scenario conditions suggested by General Electric. The SBWR model consists of the representation of the vessel internal components through parameters such as areas, diameters and volumes, and the one-quarter-core neutron parameters which were obtained using the transport theory lattice physics code CASMO-3. The thermohydraulic equations are solved by RAMONA-4B in a closed-contour inside the vessel and in a hundred eighty four parallel channels (including bypass) in the core. The tridimensional representation of the reactor core is accomplished through a proposed fuel load which was obtained from a selection of out of three fuel loads and using some standard fuel design parameters. The cross sections are represented using a polynomial as a function of the bumup, void fraction, fuel and moderator temperatures. The six-group delayed neutron equation and the one-and-a-half neutron diffusion equation are solved and the power distribution in the reactor core is obtained.Also, RAMONA-4B has implemented a (adiabatic) steam line model to represent the acoustic effects of the turbine stop valve closure during the transient. Finally, the two-phase coolant and neutronic parameters are calculated in steady state and during the turbine trip transient. The results are discussed and compared against the ones shown in the chapter XV of the SSAR.

Cuevas Vivas, Gabriel Francisco

1995-01-01T23:59:59.000Z

313

MODULAR AND FULL SIZE SIMPLIFIED BOILING WATER REACTOR DESIGN WITH FULLY PASSIVE SAFETY SYSTEMS  

SciTech Connect

OAK B204 The overall goal of this three-year research project was to develop a new scientific design of a compact modular 200 MWe and a full size 1200 MWe simplified boiling water reactors (SBWR). Specific objectives of this research were: (1) to perform scientific designs of the core neutronics and core thermal-hydraulics for a small capacity and full size simplified boiling water reactor, (2) to develop a passive safety system design, (3) improve and validate safety analysis code, (4) demonstrate experimentally and analytically all design functions of the safety systems for the design basis accidents (DBA) and (5) to develop the final scientific design of both SBWR systems, 200 MWe (SBWR-200) and 1200 MWe (SBWR-1200). The SBWR combines the advantages of design simplicity and completely passive safety systems. These advantages fit well within the objectives of NERI and the Department of Energy's focus on the development of Generation III and IV nuclear power. The 3-year research program was structured around seven tasks. Task 1 was to perform the preliminary thermal-hydraulic design. Task 2 was to perform the core neutronic design analysis. Task 3 was to perform a detailed scaling study and obtain corresponding PUMA conditions from an integral test. Task 4 was to perform integral tests and code evaluation for the DBA. Task 5 was to perform a safety analysis for the DBA. Task 6 was to perform a BWR stability analysis. Task 7 was to perform a final scientific design of the compact modular SBWR-200 and the full size SBWR-1200. A no cost extension for the third year was requested and the request was granted and all the project tasks were completed by April 2003. The design activities in tasks 1, 2, and 3 were completed as planned. The existing thermal-hydraulic information, core physics, and fuel lattice information was collected on the existing design of the simplified boiling water reactor. The thermal-hydraulic design were developed. Based on a detailed integral system scaling analysis, design parameters were obtained and designs of the compact modular 200 MWe SBWR and the full size 1200 MWe SBWR were developed. These reactors are provided with passive safety systems. A new passive vacuum breaker check valve was designed to replace the mechanical vacuum beaker check valve. The new vacuum breaker check valve was based on a hydrostatic head, and was fail safe. The performance of this new valve was evaluated both by the thermal-hydraulic code RELAP5 and by the experiments in a scaled SBWR facility, PUMA. In the core neutronic design a core depletion model was implemented to PARCS code. A lattice design for the SBWR fuel assemblies was performed. Design improvements were made to the neutronics/thermal-hydraulics models of SBWR-200 and SBWR-1200, and design analyses of these reactors were performed. The design base accident analysis and evaluation of all the passive safety systems were completed as scheduled in tasks 4 and 5. Initial conditions for the small break loss of coolant accidents (LOCA) and large break LOCA using REALP5 code were obtained. Small and large break LOCA tests were performed and the data was analyzed. An anticipated transient with scram was simulated using the RELAP5 code for SBWR-200. The transient considered was an accidental closure of the main steam isolation valve (MSIV), which was considered to be the most significant transient. The evaluation of the RELAP5 code against experimental data for SBWR-1200 was completed. In task 6, the instability analysis for the three SBWR designs (SBWR-1200, SBWR-600 and SBWR-200) were simulated for start-up transients and the results were similar. Neither the geysering instability, nor the loop type instability was predicted by RAMONA-4B in the startup simulation following the recommended procedure by GE. The density wave oscillation was not observed at all because the power level used in the simulation was not high enough. A study was made of the potential instabilities by imposing an unrealistically high power ramp in a short time period, as suggested by GE. RAMON

M. Ishii; S. T. Revankar; T. Downar; Y. Xu, H. J. Yoon; D. Tinkler; U. S. Rohatgi

2003-06-16T23:59:59.000Z

314

Program on Technology Innovation: Prediction and Evaluation of Environmentally Assisted Cracking in LWR Structural Materials  

Science Conference Proceedings (OSTI)

This report describes the interim results of PEACE-E, a five-year extension of the joint research program sponsored by EPRI in collaboration with Fracture & Reliability Research Institute (FRRI) at Tohoku University, Japanese utilities, vendors, and international organizations. The program addressed environmentally assisted cracking (EAC) of light water reactor (LWR) structural materials in pressurized water reactor (PWR) and boiling water reactor (BWR) environments.

2009-12-16T23:59:59.000Z

315

END POINTS SPECIFICATION METHODS End Points Specification Methods  

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

hazards must be addressed. Examples include steps to preclude nuclear criticality and removal or stabilization of hazardous nuclear and chemical materials. *...

316

Grid Points (GridSampleSet)  

Science Conference Proceedings (OSTI)

... OOF2: The Manual. Grid Points (GridSampleSet). ... Name. Grid Points (GridSampleSet) — Evaluate data on a rectangular grid of points. Synopsis. ...

2013-08-23T23:59:59.000Z

317

Grid Points (StatGridSampleSet)  

Science Conference Proceedings (OSTI)

... OOF2: The Manual. Grid Points (StatGridSampleSet). ... Name. Grid Points (StatGridSampleSet) — Evaluate data on a rectangular grid of points. ...

2013-08-23T23:59:59.000Z

318

A Critical Point for Science?  

E-Print Network (OSTI)

, taboo ideas become arespectable part of science? Occult Sciences Tripos? CU Institute of Astrology? Telepathy, ‘memory of water’, ‘cold fusion’?Scientific theology, intelligent design? Mar. 5, 2008/CUPS A Critical Point for Science / Brian Josephson 32...

Josephson, B D

2008-03-05T23:59:59.000Z

319

Minor Materials  

Science Conference Proceedings (OSTI)

Table 1   Materials used in glass manufacture...Table 1 Materials used in glass manufacture Material Purpose Antimony oxide (Sb 2 O 3 ) Decolorizing and fining agent Aplite (K, Na, Ca, Mg, alumina silicate) Source of alumina Aragonite (CaCO 3 ) Source of calcium oxide Arsenic oxide (As 2 O 3 ) Fining and decolorizing agent Barite/barytes (BaSO 4 )...

320

Scintillator material  

DOE Patents (OSTI)

An improved scintillator material comprising cerium fluoride is disclosed. Cerium fluoride has been found to provide a balance of good stopping power, high light yield and short decay constant that is superior to known scintillator materials such as thallium-doped sodium iodide, barium fluoride and bismuth germanate. As a result, cerium fluoride is favorably suited for use as a scintillator material in positron emission tomography.

Anderson, David F. (Batavia, IL); Kross, Brian J. (Aurora, IL)

1992-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "boiling point material" 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

Scintillator material  

DOE Patents (OSTI)

An improved scintillator material comprising cerium fluoride is disclosed. Cerium fluoride has been found to provide a balance of good stopping power, high light yield and short decay constant that is superior to known scintillator materials such as thallium-doped sodium iodide, barium fluoride and bismuth germanate. As a result, cerium fluoride is favorably suited for use as a scintillator material in positron emission tomography. 4 figs.

Anderson, D.F.; Kross, B.J.

1994-06-07T23:59:59.000Z

322

Scintillator material  

DOE Patents (OSTI)

An improved scintillator material comprising cerium fluoride is disclosed. Cerium fluoride has been found to provide a balance of good stopping power, high light yield and short decay constant that is superior to known scintillator materials such as thallium-doped sodium iodide, barium fluoride and bismuth germanate. As a result, cerium fluoride is favorably suited for use as a scintillator material in positron emission tomography. 4 figs.

Anderson, D.F.; Kross, B.J.

1992-07-28T23:59:59.000Z

323

Scintillator material  

DOE Patents (OSTI)

An improved scintillator material comprising cerium fluoride is disclosed. Cerium fluoride has been found to provide a balance of good stopping power, high light yield and short decay constant that is superior to known scintillator materials such as thallium-doped sodium iodide, barium fluoride and bismuth germanate. As a result, cerium fluoride is favorably suited for use as a scintillator material in positron emission tomography.

Anderson, David F. (Batavia, IL); Kross, Brian J. (Aurora, IL)

1994-01-01T23:59:59.000Z

324

Advanced Materials  

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

Advanced Materials Advanced Materials Advanced Materials Express Licensing Active Terahertz Metamaterial Devices Express Licensing Anion-Conducting Polymer, Composition, And Membrane Express Licensing Analysis Of Macromolecule, Liggands And Macromolecule-Lingand Complexes Express Licensing Carbon Microtubes Express Licensing Chemical Synthesis Of Chiral Conducting Polymers Express Licensing Forming Adherent Coatings Using Plasma Processing Express Licensing Hydrogen Scavengers Express Licensing Laser Welding Of Fused Quartz Express Licensing Multiple Feed Powder Splitter Negotiable Licensing Boron-10 Neutron Detectors for Helium-3 Replacement Negotiable Licensing Insensitive Extrudable Explosive Negotiable Licensing Durable Fuel Cell Membrane Electrode Assembly (MEA) Express Licensing Method of Synthesis of Proton Conducting Materials

325

Advanced Materials  

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

Conducting Materials Negotiable Licensing Microseismic Tracer Particles for Hydraulic Fracturing Negotiable Licensing A Photo-Stimulated Low Electron Temperature High Current...

326

Magnetic Materials  

Science Conference Proceedings (OSTI)

Oct 27, 2009 ... Extreme magnetic fields (>2 tesla), especially when combined with temperature, are being shown to revolutionize materials processing and ...

327

materials processing  

Science Conference Proceedings (OSTI)

... of the Stainless Steel Elaborated by the Duplex Procedure (Electric Furnace- VOD Installation) [pp. ... Materials Processing on a Solar Furnace Satellite [pp.

328

Materials Studio  

Science Conference Proceedings (OSTI)

Jan 14, 2008 ... G. Fitzgerald; G. Goldbeck-Wood; P. Kung; M. Petersen; L. Subramanian; J. Wescott, " Materials Modeling from Quantum Mechanics to The ...

329

Nuclear Materials  

Science Conference Proceedings (OSTI)

Materials and Fuels for the Current and Advanced Nuclear Reactors III ... response of oxide ceramics for nuclear applications through experiment, theory, and ...

330

Experimental Investigation on the Effects of Coolant Concentration on Sub-Cooled Boiling and Crud Deposition on Reactor Cladding at Prototypical PWR Operating Conditions  

SciTech Connect

Increasing demand for energy necessitates nuclear power units to increase power limits. This implies significant changes in the design of the core of the nuclear power units, therefore providing better performance and safety in operations. A major hindrance to the increase of nuclear reactor performance especially in Pressurized Deionized water Reactors (PWR) is Axial Offset Anomaly (AOA)--the unexpected change in the core axial power distribution during operation from the predicted distribution. This problem is thought to be occur because of precipitation and deposition of lithiated compounds like boric acid (H{sub 2}BO{sub 3}) and lithium metaborate (LiBO{sub 2}) on the fuel rod cladding. Deposited boron absorbs neutrons thereby affecting the total power distribution inside the reactor. AOA is thought to occur when there is sufficient build-up of crud deposits on the cladding during subcooled nucleate boiling. Predicting AOA is difficult as there is very little information regarding the heat and mass transfer during subcooled nucleate boiling. An experimental investigation was conducted to study the heat transfer characteristics during subcooled nucleate boiling at prototypical PWR conditions. Pool boiling tests were conducted with varying concentrations of lithium metaborate (LiBO{sub 2}) and boric acid (H{sub 2}BO{sub 3}) solutions in deionized water. The experimental data collected includes the effect of coolant concentration, subcooling, system pressure and heat flux on pool the boiling heat transfer coefficient. The analysis of particulate deposits formed on the fuel cladding surface during subcooled nucleate boiling was also performed. The results indicate that the pool boiling heat transfer coefficient degrades in the presence of boric acid and lithium metaborate compared to pure deionized water due to lesser nucleation. The pool boiling heat transfer coefficients decreased by about 24% for 5000 ppm concentrated boric acid solution and by 27% for 5000 ppm lithium metaborate solution respectively at the saturation temperature for 1000 psi (68.9 bar) coolant pressure. Boiling tests also revealed the formation of fine deposits of boron and lithium on the cladding surface which degraded the heat transfer rates. The boron and lithium metaborate precipitates after a 5 day test at 5000 ppm concentration and 1000 psi (68.9 bar) operating pressure reduced the heat transfer rate 21% and 30%, respectively for the two solutions.

Schultis, J., Kenneth; Fenton, Donald, L.

2006-10-20T23:59:59.000Z

331

An evaluation of alternative reactor vessel cutting technologies for the experimental boiling water reactor at Argonne National Laboratory  

SciTech Connect

Metal cutting techniques that can be used to segment the reactor pressure vessel of the Experimental Boiling Water Reactor (EBWR) at Argonne National Laboratory (ANL) have been evaluated by Nuclear Energy Services. Twelve cutting technologies are described in terms of their ability to perform the required task, their performance characteristics, environmental and radiological impacts, and cost and schedule considerations. Specific recommendations regarding which technology should ultimately be used by ANL are included. The selection of a cutting method was the responsibility of the decommissioning staff at ANL, who included a relative weighting of the parameters described in this document in their evaluation process. 73 refs., 26 figs., 69 tabs.

Boing, L.E.; Henley, D.R. (Argonne National Lab., IL (USA)); Manion, W.J.; Gordon, J.W. (Nuclear Energy Services, Inc., Danbury, CT (USA))

1989-12-01T23:59:59.000Z

332

Preliminary phenomena identification and ranking tables for simplified boiling water reactor Loss-of-Coolant Accident scenarios  

Science Conference Proceedings (OSTI)

For three potential Loss-of-Coolant Accident (LOCA) scenarios in the General Electric Simplified Boiling Water Reactors (SBWR) a set of Phenomena Identification and Ranking Tables (PIRT) is presented. The selected LOCA scenarios are typical for the class of small and large breaks generally considered in Safety Analysis Reports. The method used to develop the PIRTs is described. Following is a discussion of the transient scenarios, the PIRTs are presented and discussed in detailed and in summarized form. A procedure for future validation of the PIRTs, to enhance their value, is outlined. 26 refs., 25 figs., 44 tabs.

Kroeger, P.G.; Rohatgi, U.S.; Jo, J.H.; Slovik, G.C.

1998-04-01T23:59:59.000Z

333

Materials Science Advanced Materials News  

Science Conference Proceedings (OSTI)

... Contributes to Discovery of Novel Quantum Spin-Liquid Release Date ... Novel Filter Material Could Cut Natural Gas Refining Costs Release Date: 03 ...

2010-12-16T23:59:59.000Z

334

Materials Science Advanced Materials Portal  

Science Conference Proceedings (OSTI)

... to Discovery of Novel Quantum Spin-Liquid. illustration of metal organic framework Novel Filter Material Could Cut Natural Gas Refining Costs. ...

2013-06-27T23:59:59.000Z

335

Optimized nanoporous materials.  

Science Conference Proceedings (OSTI)

Nanoporous materials have maximum practical surface areas for electrical charge storage; every point in an electrode is within a few atoms of an interface at which charge can be stored. Metal-electrolyte interfaces make best use of surface area in porous materials. However, ion transport through long, narrow pores is slow. We seek to understand and optimize the tradeoff between capacity and transport. Modeling and measurements of nanoporous gold electrodes has allowed us to determine design principles, including the fact that these materials can deplete salt from the electrolyte, increasing resistance. We have developed fabrication techniques to demonstrate architectures inspired by these principles that may overcome identified obstacles. A key concept is that electrodes should be as close together as possible; this is likely to involve an interpenetrating pore structure. However, this may prove extremely challenging to fabricate at the finest scales; a hierarchically porous structure can be a worthy compromise.

Braun, Paul V. (University of Illinois at Urbana-Champaign, Urbana, IL); Langham, Mary Elizabeth; Jacobs, Benjamin W.; Ong, Markus D.; Narayan, Roger J. (North Carolina State University, Raleigh, NC); Pierson, Bonnie E. (North Carolina State University, Raleigh, NC); Gittard, Shaun D. (North Carolina State University, Raleigh, NC); Robinson, David B.; Ham, Sung-Kyoung (Korea Basic Science Institute, Gangneung, South Korea); Chae, Weon-Sik (Korea Basic Science Institute, Gangneung, South Korea); Gough, Dara V. (University of Illinois at Urbana-Champaign, Urbana, IL); Wu, Chung-An Max; Ha, Cindy M.; Tran, Kim L.

2009-09-01T23:59:59.000Z

336

Development of a fully-consistent reduced order model to study instabilities in boiling water reactors  

SciTech Connect

A simple nonlinear Reduced Order Model to study global, regional and local instabilities in Boiling Water Reactors is described. The ROM consists of three submodels: neutron-kinetic, thermal-hydraulic and heat-transfer models. The neutron-kinetic model allows representing the time evolution of the three first neutron kinetic modes: the fundamental, the first and the second azimuthal modes. The thermal-hydraulic model describes four heated channels in order to correctly simulate out-of-phase behavior. The coupling between the different submodels is performed via both void and Doppler feedback mechanisms. After proper spatial homogenization, the governing equations are discretized in the time-domain. Several modifications, compared to other existing ROMs, have been implemented, and are reported in this paper. One novelty of the ROM is the inclusion of both azimuthal modes, which allows to study combined instabilities (in-phase and out-of-phase), as well as to investigate the corresponding interference effects between them. The second modification concerns the precise estimation of so-called reactivity coefficients or C{sub mn}{sup *V,D} - coefficients by using direct cross-section data from SIMULATE-3 combined with the CORE SIM core simulator in order to calculate Eigenmodes. Furthermore, a non-uniform two-step axial power profile is introduced to simulate the separate heat production in the single and two-phase regions, respectively. An iterative procedure was developed to calculate the solution to the coupled neutron-kinetic/thermal-hydraulic static problem prior to solving the time-dependent problem. Besides, the possibility of taking into account the effect of local instabilities is demonstrated in a simplified manner. The present ROM is applied to the investigation of an actual instability that occurred at the Swedish Forsmark-1 BWR in 1996/1997. The results generated by the ROM are compared with real power plant measurements performed during stability tests and show a good qualitative agreement. The present study provides some insight in a deeper understanding of the physical principles which drive both core-wide and local instabilities. (authors)

Dykin, V.; Demaziere, C. [Chalmers Univ. of Technology, Div. of Nuclear Engineering, Dept. of Applied Physics, SE-412 96 Gothenburg (Sweden)

2012-07-01T23:59:59.000Z

337

Validation and Calibration of Nuclear Thermal Hydraulics Multiscale Multiphysics Models - Subcooled Flow Boiling Study  

SciTech Connect

In addition to validation data plan, development of advanced techniques for calibration and validation of complex multiscale, multiphysics nuclear reactor simulation codes are a main objective of the CASL VUQ plan. Advanced modeling of LWR systems normally involves a range of physico-chemical models describing multiple interacting phenomena, such as thermal hydraulics, reactor physics, coolant chemistry, etc., which occur over a wide range of spatial and temporal scales. To a large extent, the accuracy of (and uncertainty in) overall model predictions is determined by the correctness of various sub-models, which are not conservation-laws based, but empirically derived from measurement data. Such sub-models normally require extensive calibration before the models can be applied to analysis of real reactor problems. This work demonstrates a case study of calibration of a common model of subcooled flow boiling, which is an important multiscale, multiphysics phenomenon in LWR thermal hydraulics. The calibration process is based on a new strategy of model-data integration, in which, all sub-models are simultaneously analyzed and calibrated using multiple sets of data of different types. Specifically, both data on large-scale distributions of void fraction and fluid temperature and data on small-scale physics of wall evaporation were simultaneously used in this work’s calibration. In a departure from traditional (or common-sense) practice of tuning/calibrating complex models, a modern calibration technique based on statistical modeling and Bayesian inference was employed, which allowed simultaneous calibration of multiple sub-models (and related parameters) using different datasets. Quality of data (relevancy, scalability, and uncertainty) could be taken into consideration in the calibration process. This work presents a step forward in the development and realization of the “CIPS Validation Data Plan” at the Consortium for Advanced Simulation of LWRs to enable quantitative assessment of the CASL modeling of Crud-Induced Power Shift (CIPS) phenomenon, in particular, and the CASL advanced predictive capabilities, in general. This report is prepared for the Department of Energy’s Consortium for Advanced Simulation of LWRs program’s VUQ Focus Area.

Anh Bui; Nam Dinh; Brian Williams

2013-09-01T23:59:59.000Z

338

Asymptotics of Greedy Energy Points  

E-Print Network (OSTI)

For a symmetric kernel $k:X\\times X \\to \\mathbb{R}\\cup\\{+\\infty\\}$ on a locally compact Hausdorff space $X$, we investigate the asymptotic behavior of greedy $k$-energy points $\\{a_{i}\\}_{1}^{\\infty}$ for a compact subset $A\\subset X$ that are defined inductively by selecting $a_{1}\\in A$ arbitrarily and $a_{n+1}$ so that $\\sum_{i=1}^{n}k(a_{n+1},a_{i})=\\inf_{x\\in A}\\sum_{i=1}^{n}k(x,a_{i})$. We give sufficient conditions under which these points (also known as Leja points) are asymptotically energy minimizing (i.e. have energy $\\sum_{i\

A. López García; E. B. Saff

2009-01-24T23:59:59.000Z

339

Materials - Home  

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

* Coatings & Lubricants * Coatings & Lubricants * Nanofluids * Deformation Joining * Recycling * Catalysts * Assessment * Illinois Center for Advanced Tribology Modeling, Simulation & Software Plug-In Hybrid Electric Vehicles PSAT Smart Grid Student Competitions Technology Analysis Transportation Research and Analysis Computing Center Working With Argonne Contact TTRDC Materials ring on liner reciprocating tester Tribology Lab: Ring-on-liner reciprocating tester. Argonne National Laboratory plays an important role in the Department of Energy's (DOE's) efforts to develop advanced materials for transportation. The materials are developed with DOE support from the EERE Office of Vehicle Technology and Office of Hydrogen, Fuel Cells, and Infrastructure Technologies in collaboration with worldwide industrial partners. Examples

340

Los Alamos Lab: Materials Physics & Applications Division  

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

ADEPS Materials Physics and Applications, MPA ADEPS Materials Physics and Applications, MPA About Us Organization Jobs Materials Physics & Applications Home Center for Integrated Nanotechnologies Superconductivity Technology Center Condensed Matter and Magnet Science Sensors & Electrochemical Devices Materials Chemistry CONTACTS Division Leader Antoinette Taylor Deputy Division Leader David Watkins Point of Contact Susan Duran 505-665-1131 Materials Physics and Applications Division serves as the Laboratory's focal point for fundamental materials physics and materials chemistry, provides world-class user facilities, unique experimental capabilities, and the scientific talent and infrastructure to facilitate understanding and control of materials properties, and develops and apply materials-based solutions

Note: This page contains sample records for the topic "boiling point material" 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

Flow instabilities in the core and the coolant circuit of advances low-boiling light water reacto: classification of causes and development of simulator for the future analysis  

E-Print Network (OSTI)

The coolant flow instability, apparent in the coolant mass flow fluctuations in the separate parallel heating channels and also in a closed loop of the primary circuit under some operating conditions, is observed in the core fuel assemblies of light water reactors. In some ways this phenomenon is identical with the fluctuations in the once-through steam generators pipes, and changes of the coolant mass flows and length of flow patterns are initiating this phenomenon. The parameters at the core output and the secondary circuit parameters have influence on each other. These parameter changes have significant influences on the operating processes, operating and control algorithms, operating and control system design, and reliability of the operating power plant's machines and equipment. Changes of heating surface temperatures, displacement borders of the flow patterns, and critical heat flux entail changes of the coolant flow parameters, finally causing changes of the initial primary system parameters due to closed loop system feedback. In turn, these cause over-circuit instability in the reactor. Core power generation changes are carried out by means of influencing the nuclear fission process through changing the multiplication factor. Additionally, these local side-to-side power irregularities in sub-zones may appear due to the influence of various hydrodynamic instabilities. The local side-to-side power in these sub-zones may differ significantly from each other. The aforesaid arguments are correct for the both light water reactor types. But, as is shown by our investigations and operational practice of low-boiling reactors, behavior of the core-circuit hydrodynamic system is significantly different from its behavior in the boiling or pressurized reactors with pumping circulation. The coolant flow regimes in typical reactors are defined through pump operating regimes and are not adjustable inside a certain power range. The objective of this thesis is to understand more precisely the influence and the nature of these phenomena. After analyzing the problem from different points of view and showing the necessity of its comprehensive understanding, we present recommendations for engineering solutions and plans for further investigations. We will try to determine limits of their reliable practical application with modern low-to-medium power reactor design and investigate this dynamic system behavior. Finally, it is necessary to take into consideration not separate phenomena, but their complex influence on the whole primary system (i.e. a kind of macro-system is examined without being separated into its individual elements). But, the analysis of every phenomenon is fulfilled separately and a process of formation of a block-scheme, consisting of several sub-systems, is given in this thesis. The final block-scheme is presented as a simulator model, taking into consideration design components chosen for the analysis of system dynamics as the first step of model development.

Rezvyi, Aleksey

2002-01-01T23:59:59.000Z

342

thermoelectric materials  

E-Print Network (OSTI)

It has been proven that the maximum cooling temperature of a thermoelectric material can be increased by using either pulsed operation or graded Seebeck profiles. In this paper, we show that the maximum cooling temperature can be further increased by the pulsed operation of optimal inhomogeneous thermoelectric materials. A random sampling method is used to obtain the optimal electrical conductivity profile of inhomogeneous materials, which can achieve a much higher cooling temperature than the best uniform materials under the steady-state condition. Numerical simulations of pulsed operation are then carried out in the time domain. In the limit of low thermoelectric figure-of-merit ZT, the finite-difference time-domain simulations are verified by an analytical solution for homogeneous material. This numerical method is applied to high ZT BiTe materials and simulations show that the effective figure-of-merit can be improved by 153 % when both optimal graded electrical conductivity profiles and pulsed operation are used. 1.

Q Zhou; Z Bian; A Shakouri

2007-01-01T23:59:59.000Z

343

Final safety evaluation report related to the certification of the advanced boiling water reactor design. Volume 2: Appendices  

Science Conference Proceedings (OSTI)

This safety evaluation report (SER) documents the technical review of the US Advanced Boiling Water Reactor (ABWR) standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the ABWR design was initially submitted by the General Electric Company, now GE Nuclear Energy (GE), in accordance with the procedures of Appendix O of Part 50 of Title 10 of the code of Federal Regulations (10 CFR Part 50). Later GE requested that its application be considered as an application for design approval and subsequent design certification pursuant to 10 CFR {section} 52.45. The ABWR is a single-cycle, forced-circulation, boiling water reactor (BWR) with a rated power of 3,926 megawatts thermal (MWt) and a design power of 4,005 MWt. To the extent feasible and appropriate, the staff relied on earlier reviews for those ABWR design features that are substantially the same as those previously considered. Unique features of the ABWR design include internal recirculation pumps, fine-motion control rod drives, microprocessor-based digital logic and control systems, and digital safety systems. On the basis of its evaluation and independent analyses, the NRC staff concludes that, subject to satisfactory resolution of the confirmatory items identified in Section 1.8 of this SER, GE`s application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the US ABWR standard design.

Not Available

1994-07-01T23:59:59.000Z

344

Final safety evaluation report related to the certification of the advanced boiling water reactor design. Volume 1: Main report  

SciTech Connect

This safety evaluation report (SER) documents the technical review of the US Advanced Boiling Water Reactor (ABWR) standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the ABWR design was initially submitted by the General Electric Company, now GE Nuclear Energy (GE), in accordance with the procedures of Appendix O of Part 50 of Title 10 of the Code of Federal Regulations (10 CFR Part 50). Later GE requested that its application be considered as an application for design approval and subsequent design certification pursuant to 10 CFR {section} 52.45. The ABWR is a single-cycle, forced-circulation, boiling water reactor (BWR) with a rated power of 3,926 megawatts thermal (MWt) and a design power of 4,005 MWt. To the extent feasible and appropriate, the staff relied on earlier reviews for those ABWR design features that are substantially the same as those previously considered. Unique features of the ABWR design include internal recirculation pumps, fine-motion control rod drives, microprocessor-based digital logic and control systems, and digital safety systems. On the basis of its evaluation and independent analyses, the NRC staff concludes that, subject to satisfactory resolution of the confirmatory items identified in Section 1.8 of this SER, GE`s application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the US ABWR standard design.

Not Available

1994-07-01T23:59:59.000Z

345

Wellness Program WELLNESS POINTS BANK  

E-Print Network (OSTI)

Wellness Program WELLNESS POINTS BANK Renew your commitment to health. Start again October 1, 2012 to your family and friends, too. Your health and well-being are also important to the University of Minnesota. As your employer, the University recognizes the value of investing in a comprehensive Wellness

Thomas, David D.

346

New Filtration Material Could Make Petroleum Refining ...  

Science Conference Proceedings (OSTI)

... Creating premium fuel requires a refinery to boil the mixture at precise ... The new MOF, however, could allow refineries to sidestep this problem by ...

2013-05-28T23:59:59.000Z

347

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

SciTech Connect

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

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

1982-03-01T23:59:59.000Z

348

APPARATUS FOR CONTROL OF A BOILING REACTOR RESPONSIVE TO STEAM DEMAND  

DOE Patents (OSTI)

A method of controlling a fuel-rod-in-tube-type boilingwater reactor having nozzles at the point of water entry into the tube is described. Water is pumped into the nozzles by an auxiliary pump operated by steam from an interstage position of the associated turbine, so that the pumping speed is responsive to turbine demand. (AEC)

Treshow, M.

1963-07-23T23:59:59.000Z

349

Nondestructive ultrasonic testing of materials  

DOE Patents (OSTI)

Reflection wave forms obtained from aged and unaged material samples can be compared in order to indicate trends toward age-related flaws. Statistical comparison of a large number of data points from such wave forms can indicate changes in the microstructure of the material due to aging. The process is useful for predicting when flaws may occur in structural elements of high risk structures such as nuclear power plants, airplanes, and bridges.

Hildebrand, Bernard P. (Richland, WA)

1994-01-01T23:59:59.000Z

350

Nondestructive ultrasonic testing of materials  

DOE Patents (OSTI)

Reflection wave forms obtained from aged and unaged material samples can be compared in order to indicate trends toward age-related flaws. Statistical comparison of a large number of data points from such wave forms can indicate changes in the microstructure of the material due to aging. The process is useful for predicting when flaws may occur in structural elements of high risk structures such as nuclear power plants, airplanes, and bridges. 4 figs.

Hildebrand, B.P.

1994-08-02T23:59:59.000Z

351

QUANTITATIVE METALLOGRAPHY OF PLUTONIUM USING POINT-COUNT TECHNIQUES  

SciTech Connect

A point-counter was designed and adapted for use on a ausch and Lomb Balphot Metallograph. The results of quantitative metallography performed on materials with two or more phases are given and some of the results are compared with x-ray analysis. (auth)

Greeson, R.L.

1964-01-01T23:59:59.000Z

352

Hardfacing material  

SciTech Connect

A method of producing a hard metallic material by forming a mixture containing at least 55% iron and at least one of boron, carbon, silicon and phosphorus. The mixture is formed into an alloy and cooled to form a metallic material having a hardness of greater than about 9.2 GPa. The invention includes a method of forming a wire by combining a metal strip and a powder. The metal strip and the powder are rolled to form a wire containing at least 55% iron and from two to seven additional elements including at least one of C, Si and B. The invention also includes a method of forming a hardened surface on a substrate by processing a solid mass to form a powder, applying the powder to a surface to form a layer containing metallic glass, and converting the glass to a crystalline material having a nanocrystalline grain size.

Branagan, Daniel J. (Iona, ID)

2012-01-17T23:59:59.000Z

353

BP Cherry Point Congeneration Project  

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

REVISED 404 (B) (1) REVISED 404 (B) (1) ALTERNATIVES ANALYSIS BP Cherry Point Cogeneration Project Prepared for: BP West Coast Products, LLC Revised June 29, 2004 1501 Fourth Avenue, Suite 1400 Seattle, WA 98101-1616 (206) 438-2700 33749546.05070 i TABLE OF CONTENTS Page 1.0 I NT RODUCTI ON ................................................................................................................... 1 2.0 P URPOSE AND NEE D .......................................................................................................... 1 2.1 RELIABILITY .................................................................................................... 1 2.2 COST-EFFECTIVENESS ................................................................................... 3 2.3 SIZE OF FACILITY............................................................................................

354

Cryogenic Material Properties Database Cryogenic Material ...  

Science Conference Proceedings (OSTI)

... properties. These include the Handbook on Materials for Superconducting Machinery and the LNG Materials & Fluids. Neither ...

2000-10-27T23:59:59.000Z

355

Material containment enclosure  

DOE Patents (OSTI)

An isolation enclosure and a group of isolation enclosures was designed which is useful when a relatively large containment area is required. The enclosure is in the form of a ring having a section removed so that a technician may enter the center area of the ring. in a preferred embodiment, an access zone is located in the transparent wall of the enclosure and extends around the inner perimeter of the ring so that a technician can insert his hands into the enclosure to reach any point within. The inventive enclosures provide more containment area per unit area of floor space than conventional material isolation enclosures.

Carlson, D.O.

1991-04-01T23:59:59.000Z

356

Green Materials  

Science Conference Proceedings (OSTI)

Mar 6, 2013 ... Incorporation of Granite Waste Diamond Wire in Cementitious Matrices: ... determination method simplex from a stroke cement using standard CP-V, ... its property in building materials manufacture, alumina recovery, etc. ... as well as their changes during heat treatment were studied by XRD, FTIR and XPS.

357

Optimization of Core Point Detection in Fingerprints  

Science Conference Proceedings (OSTI)

This paper compares and documents the work of an optimized fingerprint core point determination algorithm. This work focuses to present an efficient and precise way for the extraction of core point. Core Point is detected using least mean square algorithm. ...

Nabeel Younus Khan; M. Younus Javed; Naveed Khattak; Umer Munir Yongjun Chang

2007-12-01T23:59:59.000Z

358

Program on Technology Innovation: Environmentally Assisted Cracking in LWR Structural Materials--2009-10 PEACE-E Annual Report  

Science Conference Proceedings (OSTI)

This report describes the interim results of PEACE-E Phase-1, a three-year joint research program sponsored by EPRI in collaboration with Fracture Reliability Research Institute (FRRI) at Tohoku University, Japanese utilities, vendors, and international organizations. The program addressed environmentally assisted cracking (EAC) of light water reactor (LWR) structural materials in pressurized water reactor (PWR) and boiling water reactor (BWR) environments. PEACE-E Phase-1 focuses on combining multiple a...

2010-12-15T23:59:59.000Z

359

Materials Reliability Program: Technical Basis for Primary Water Stress Corrosion Cracking Mitigation by Surface Stress Improvement (MRP-267, Revision 1)  

Science Conference Proceedings (OSTI)

During the past two decades, stress corrosion cracking (SCC) has become the most relevant phenomenon affecting nuclear plant availability and plant lifetime management. SCC can lead to increased costs for operation, maintenance, assessment, repair, and replacement of boiling water reactor (BWR) and pressurized water reactor (PWR) components. Alloy 600 and 82/182 materials, which are widely used in PWR systems, are susceptible to primary water stress corrosion cracking (PWSCC). PWSCC has been reported in ...

2012-07-31T23:59:59.000Z

360

BWRVIP-228: BWR Vessel and Internals Project, A Computational Modeling Tool for Welding Repair of Irradiated Materials  

Science Conference Proceedings (OSTI)

Repair welding on highly irradiated stainless steel BWR internals can lead to cracking in the heat-affected zone (HAZ) of the weld region. EPRI and participating Boiling Water Reactor Vessel and Internals Project (BWRVIP) members have sponsored development of a computational modeling tool to assist in determining appropriate welding process conditions (heat input and process selection) to produce crack-free welds on irradiated materials. This tool integrates a finite-element-based welding temperature and...

2009-11-30T23:59:59.000Z

Note: This page contains sample records for the topic "boiling point material" 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.


361

Erratum: Experimental Vibrational Zero-Point Energies ...  

Science Conference Proceedings (OSTI)

Erratum: Experimental Vibrational Zero-Point Energies: Diatomic Molecules †J ... error in the calculated zero point energy ZPE for ... All rights reserved. ...

2013-04-16T23:59:59.000Z

362

Critical Analysis and Review of Flash Points of High Molecular Weight Poly-functional C, H, N, O Compounds  

E-Print Network (OSTI)

The research focuses on the critical review and prediction of flash points of high molecular weight compounds used mainly in the specialty chemical area. Thus far this area of high molecular weight specialty chemicals has not been thoroughly reviewed for flash point prediction; therefore critical review for accuracy of experimental values is difficult. Without critical review, the chance of hazards occurring in the processing and handling of these compounds increases. A reliable method for making predictions is important to efficiently review experimental values since duplicate experimentation can be time consuming and costly. The flash point is strongly correlated to the normal boiling point (NBP) but experimental NBP is not feasible for chemicals of high molecular weight. The reliability of existing NBP prediction methods was found inadequate for our compounds of interest therefore a new NBP prediction method was developed first. This method is based on ten simple group contributions and the molecular weight of the molecule. The training set included 196 high molecular weight C, H, N and O compounds. It produced an average absolute error (AAE) of 13K, superior to any other model tested so far. An accurate NBP is essential for critical review and new method development for flash point. A preliminary data analysis based on chemical family analysis allowed for detection of erroneous data points. These compounds were re-tested at a Huntsman facility. With a predicted normal boiling point, a new FP method that differentiates strong and iv weak hydrogen bonding compounds was developed. This was done because of the differences in entropy of vaporization for hydrogen bonding compounds. The training set consisted of 191 diverse C, H, N, O compounds ranging from 100 to 4000 g/mol in molecular weight. The test set consisted of 97 compounds of similar diversity. Both data sets produced an AAE of 5K and maximum deviation of 17.5K. It was also found that no substantial decomposition was found for these compounds at flash point conditions. These compounds appear to follow the same physical trends as lower molecular weight compounds. With this new method it is possible to critically review this class of chemicals as well as update NBP and other physical property data.

Thomas, Derrick

2011-05-01T23:59:59.000Z

363

Energy Conversion Materials Through Chemical Synthesis Route  

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

Conversion Materials Through Chemical Synthesis Route Speaker(s): Lionel Vayssieres Date: April 27, 2004 - 12:00pm Location: Bldg. 90 Seminar HostPoint of Contact: Samuel Mao The...

364

BWRVIP-241: BWR Vessel and Internals Project, Probabilistic Fracture Mechanics Evaluation for the Boiling Water Reactor Nozzle-to-Ve ssel Shell Welds and Nozzle Blend Radii  

Science Conference Proceedings (OSTI)

This report documents supplemental analyses for boiling water reactor (BWR) reactor pressure vessel (RPV) recirculation inlet and outlet nozzle-to-shell welds and nozzle inner radii to address limitations imposed by the U.S. Nuclear Regulatory Commission (NRC) regarding the reduction of inspections specified in Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code.

2010-10-26T23:59:59.000Z

365

Study of Pu consumption in advanced light water reactors: Evaluation of GE advanced boiling water reactor plants - compilation of Phase 1B task reports  

SciTech Connect

This report contains an extensive evaluation of GE advanced boiling water reactor plants prepared for United State Department of Energy. The general areas covered in this report are: core and system performance; fuel cycle; infrastructure and deployment; and safety and environmental approval.

NONE

1993-09-15T23:59:59.000Z

366

Executive Director for Operations CONSIDERATION OF ADDITIONAL REQUIREMENTS FOR CONTAINMENT VENTING SYSTEMS FOR BOILING WATER REACTORS WITH MARK I AND MARK II CONTAINMENTS  

E-Print Network (OSTI)

information, options, and a recommendation from the NRC staff to impose new requirements for containment venting systems for boiling-water reactors (BWRs) with Mark I and Mark II containments. This paper is provided in response to the Commission’s staff requirements memorandum (SRM) for SECY-11-0137, “Prioritization of Recommended Actions To Be

R. W. Borchardt

2012-01-01T23:59:59.000Z

367

Summary and bibliography of safety-related events at boiling-water nuclear power plants as reported in 1980  

SciTech Connect

This document presents a bibliography that contains 100-word abstracts of event reports submitted to the US Nuclear Regulatory Commission concerning operational events that occurred at boiling-water-reactor nuclear power plants in 1980. The 1547 abstracts included on microfiche in this bibliography describe incidents, failures, and design or construction deficiencies that were experienced at the facilities. These abstracts are arranged alphabetically by reactor name and then chronologically for each reactor. Full-size keyword and permuted-title indexes to facilitate location of individual abstracts are provided following the text. Tables that summarize the information contained in the bibliography are also provided. The information in the tables includes a listing of the equipment items involved in the reported events and the associated number of reports for each item. Similar information is given for the various kinds of instrumentation and systems, causes of failures, deficiencies noted, and the time of occurrence (i.e., during refueling, operation, testing, or construction).

McCormack, K.E.; Gallaher, R.B.

1982-03-01T23:59:59.000Z

368

Experimental and Thermalhydraulic Code Assessment of the Transient Behavior of the Passive Condenser System in an Advanced Boiling Water Reactor  

Science Conference Proceedings (OSTI)

The main goal of the project was to study analytically and experimentally the condensation heat transfer for the passive condenser system such as GE Economic Simplified Boiling Water Reactor (ESBWR). The effect of noncondensable gas in condenser tube and the reduction of secondary pool water level to the condensation heat transfer coefficient was the main focus in this research. The objectives of this research were to : 1) obtain experimental data on the local and tube averaged condensation heat transfer rates for the PCCS with non-condensable and with change in the secondary pool water, 2) assess the RELAP5 and TRACE computer code against the experimental data, and 3) develop mathematical model and ehat transfer correlation for the condensation phenomena for system code application. The project involves experimentation, theoretical model development and verification, and thermal- hydraulic codes assessment.

S.T. Revankar; W. Zhou; Gavin Henderson

2008-07-08T23:59:59.000Z

369

New Materials for Spintronics  

SciTech Connect

One of the critical materials needs for the development of spin electronics is diluted magnetic semiconductors (DMS) which retain their ferromagnetism at and above room temperature. Spin polarization in DMS materials leads to the possibility of spin-polarized current injection into nonmagnetic semiconductor heterostructures. Such transport is of critical importance in the development of devices that utilize spin (e.g. spin-LEDs and spin-FETs). New magnetically-doped semiconducting oxides that show promise because of Curie points which exceed room temperature are currently being investigated in our lab and elsewhere. However, the detailed materials properties and mechanism(s) of magnetism in these systems have been elusive. In this talk, I will present recent results from our laboratory focused on the MBE synthesis and properties of these ferromagnetic oxide semiconductors. This work was funded by the PNNL Nanoscience and Technology Initiative, the US Department of Energy, Office of Science, Office of Basic Energy Sciences, Division of Materials Science and Engineering Physics, and the DARPA Spins in Semiconductors (SPINS) Initiative.

Chambers, Scott A.; Yoo, Young K.

2003-10-10T23:59:59.000Z

370

Investigation of the physical and numerical foundations of two-fluid representation of sodium boiling with applications to LMFBR experiments  

Science Conference Proceedings (OSTI)

This work involves the development of physical models for the constitutive relations of a two-fluid, three-dimensional sodium boiling code, THERMIT-6S. The code is equipped with a fluid conduction model, a fuel pin model, and a subassembly wall model suitable for stimulating LMFBR transient events. Mathematically rigorous derivations of time-volume averaged conservation equations are used to establish the differential equations of THERMIT-6S. These equations are then discretized in a manner identical to the original THERMIT code. A virtual mass term is incorporated in THERMIT-6S to solve the ill-posed problem. Based on a simplified flow regime, namely cocurrent annular flow, constitutive relations for two-phase flow of sodium are derived. The wall heat transfer coefficient is based on momentum-heat transfer analogy and a logarithmic law for liquid film velocity distribution. A broad literature review is given for two-phase friction factors. It is concluded that entrainment can account for some of the discrepancies in the literature. Mass and energy exchanges are modelled by generalization of the turbulent flux concept. Interfacial drag coefficients are derived for annular flows with entrainment. Code assessment is performed by simulating three experiments for low flow-high power accidents and one experiment for low flow/low power accidents in the LMFBR. While the numerical results for pre-dryout are in good agreement with the data, those for post-dryout reveal the need for improvement of the physical models. The benefits of two-dimensional non-equilibrium representation of sodium boiling are studied.

No, H.C.; Kazimi, M.S.

1983-03-01T23:59:59.000Z

371

Heat transfer characteristics of R410A-oil mixture flow boiling inside a 7 mm straight smooth tube  

SciTech Connect

Two-phase flow patterns and heat transfer characteristics of R410A-oil mixture flow boiling inside a straight smooth tube with the outside diameter of 7.0 mm were investigated experimentally. The experimental conditions include the evaporation temperature of 5 C, the mass flux from 200 to 400 kg m{sup -2} s{sup -1}, the heat flux from 7.56 to 15.12 kW m{sup -2}, the inlet vapor quality from 0.2 to 0.7, nominal oil concentration from 0% to 5%. The test results show that the heat transfer coefficient of R410A-oil mixture increases with mass flux of refrigerant-oil mixture; the presence of oil enhances the heat transfer at the range of low and intermediate vapor qualities; there is a peak of local heat transfer coefficient at about 2-4% nominal oil concentration at higher vapor qualities, and the peak shifts to lower nominal oil concentration with the increasing of vapor qualities; higher nominal oil concentration gives more detrimental effect at high vapor qualities. The flow pattern map of R410A-oil mixture was developed based on refrigerant-oil mixture properties, and the observed flow patterns match well with the flow pattern map. New correlation to predict the local heat transfer of R410A-oil mixture flow boiling inside the straight smooth tube was developed based on flow patterns and local properties of refrigerant-oil mixture, and it agrees with 90% of the experiment data within the deviation of {+-}25%. (author)

Hu, Haitao; Ding, Guoliang; Wei, Wenjian; Wang, Zhence [Institute of Refrigeration and Cryogenics, Shanghai Jiaotong University, Shanghai 200240 (China); Wang, Kaijian [Fujitsu General Institute of Air-Conditioning Technology Limited, Kawasaki 213-8502 (Japan)

2008-01-15T23:59:59.000Z

372

EM QA Working Group September 2011 Meeting Materials  

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

PowerPoint presentations and reference material used in the EM QA Working Group video conference meeting held in September 2011.

373

EM QA Working Group September 2011 Meeting Materials | Department...  

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

PowerPoint presentations and reference material used in the EM QA Working Group video conference meeting held in September 2011. EM QA Working Group September 2011 Meeting...

374

Educated U.S. Workforce & Government Support Will Fuel Materials ...  

Science Conference Proceedings (OSTI)

Feb 21, 2012 ... “We are at a tipping point in the way that computational materials science can be used to enable advanced product manufacturing and fuel ...

375

Heat transfer characteristics of a three-phase volume boiling direct contact heat exchanger  

DOE Green Energy (OSTI)

The advantages of direct contact heat transfer over heat transfer utilizing conventional metallic heat exchangers are listed. The performance characteristics of a three-phase direct contact heat exchanger in near counterflow operation were evaluated using water as the continuous phase fluid and refrigerant 113 as the dispersed phase fluid. Conclusions are drawn from the results having to do with refrigerant injection technique, vessel operating height, mass flow rate of refrigerant, water inlet temperature, operation at pinch point temperature differences below 13 to 20/sup 0/C, and operation with a dispersed phase fluid less dense than water. (MHR)

Blair, C.K.; Boehm, R.F.; Jacobs, H.R.

1976-03-01T23:59:59.000Z

376

MSD Molecular Materials - Argonne National Laboratories, Materials...  

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

Home Molecular Materials Molecular Materials Group carries out synthesis and characterization of novel materials whose unique properties originate at the molecular level. Our...

377

Convertibility of Function Points into COSMIC Function Points: A study using Piecewise Linear Regression  

Science Conference Proceedings (OSTI)

Background: COSMIC Function Points and traditional Function Points (i.e., IFPUG Function Points and more recent variation of Function Points, such as NESMA and FISMA) are probably the best known and most widely used Functional Size Measurement methods. ... Keywords: COSMIC Function Points, Data analysis, Function Point analysis, Functional Size Measurement, Functional size measure convertibility, Outliers

Luigi Lavazza; Sandro Morasca

2011-08-01T23:59:59.000Z

378

Alloy materials  

DOE Patents (OSTI)

An alloy that contains at least two metals and can be used as a substrate for a superconductor is disclosed. The alloy can contain an oxide former. The alloy can have a biaxial or cube texture. The substrate can be used in a multilayer superconductor, which can further include one or more buffer layers disposed between the substrate and the superconductor material. The alloys can be made a by process that involves first rolling the alloy then annealing the alloy. A relatively large volume percentage of the alloy can be formed of grains having a biaxial or cube texture.

Hans Thieme, Cornelis Leo (Westborough, MA); Thompson, Elliott D. (Coventry, RI); Fritzemeier, Leslie G. (Acton, MA); Cameron, Robert D. (Franklin, MA); Siegal, Edward J. (Malden, MA)

2002-01-01T23:59:59.000Z

379

Critical Point Symmetries in Nuclei  

E-Print Network (OSTI)

Critical Point Symmetries (CPS) appear in regions of the nuclear chart where a rapid change from one symmetry to another is observed. The first CPSs, introduced by F. Iachello, were E(5), which corresponds to the transition from vibrational [U(5)] to gamma-unstable [O(6)] behaviour, and X(5), which represents the change from vibrational [U(5)] to prolate axially deformed [SU(3)] shapes. These CPSs have been obtained as special solutions of the Bohr collective Hamiltonian. More recent special solutions of the same Hamiltonian, to be described here, include Z(5) and Z(4), which correspond to maximally triaxial shapes (the latter with ``frozen'' gamma=30 degrees), as well as X(3), which corresponds to prolate shapes with ``frozen'' gamma=0. CPSs have the advantage of providing predictions which are parameter free (up to overall scale factors) and compare well to experiment. However, their mathematical structure [with the exception of E(5)] needs to be clarified.

Bonatsos, D; Petrellis, D; Terziev, P A; Yigitoglu, I; Bonatsos, Dennis

2006-01-01T23:59:59.000Z

380

BP Cherry Point Cogeneration Project  

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

Final Environmental Impact Statement Final Environmental Impact Statement DOE/EIS-0349 Lead Agencies: Energy Facility Site Evaluation Council Bonneville Power Administration Cooperating Agency: U.S. Army Corps of Engineers August 2004 EFSEC Washington State Energy Facility Site Evaluation Council July 12, 2004 Dear Reader: Enclosed for your reference is the abbreviated Final Environmental Impact Statement (FEIS) for the proposed BP Cherry Point Cogeneration Project. This document is designed to correct information and further explain what was provided in the Draft Environmental Impact Statement (DEIS). The proponent, BP West Coast Products, LLC, has requested to build a 720-megawatt gas-fired combined cycle cogeneration facility in Whatcom County, Washington, and interconnect this facility into the regional

Note: This page contains sample records for the topic "boiling point material" 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

Photovoltaic Materials  

Science Conference Proceedings (OSTI)

The goal of the current project was to help make the US solar industry a world leader in the manufacture of thin film photovoltaics. The overall approach was to leverage ORNL’s unique characterization and processing technologies to gain a better understanding of the fundamental challenges for solar cell processing and apply that knowledge to targeted projects with industry members. ORNL has the capabilities in place and the expertise required to understand how basic material properties including defects, impurities, and grain boundaries affect the solar cell performance. ORNL also has unique processing capabilities to optimize the manufacturing process for fabrication of high efficiency and low cost solar cells. ORNL recently established the Center for Advanced Thin-film Systems (CATS), which contains a suite of optical and electrical characterization equipment specifically focused on solar cell research. Under this project, ORNL made these facilities available to industrial partners who were interested in pursuing collaborative research toward the improvement of their product or manufacturing process. Four specific projects were pursued with industrial partners: Global Solar Energy is a solar industry leader in full scale production manufacturing highly-efficient Copper Indium Gallium diSelenide (CIGS) thin film solar material, cells and products. ORNL worked with GSE to develop a scalable, non-vacuum, solution technique to deposit amorphous or nanocrystalline conducting barrier layers on untextured stainless steel substrates for fabricating high efficiency flexible CIGS PV. Ferro Corporation’s Electronic, Color and Glass Materials (“ECGM”) business unit is currently the world’s largest supplier of metallic contact materials in the crystalline solar cell marketplace. Ferro’s ECGM business unit has been the world's leading supplier of thick film metal pastes to the crystalline silicon PV industry for more than 30 years, and has had operational cells and modules in the field for 25 years. Under this project, Ferro leveraged world leading analytical capabilities at ORNL to characterize the paste-to-silicon interface microstructure and develop high efficiency next generation contact pastes. Ampulse Corporation is developing a revolutionary crystalline-silicon (c-Si) thin-film solar photovoltaic (PV) technology. Utilizing uniquely-textured substrates and buffer materials from the Oak Ridge National Laboratory (ORNL), and breakthroughs in Hot-Wire Chemical Vapor Deposition (HW-CVD) techniques in epitaxial silicon developed at the National Renewable Energy Laboratory (NREL), Ampulse is creating a solar technology that is tunable in silicon thickness, and hence in efficiency and economics, to meet the specific requirements of multiple solar PV applications. This project focused on the development of a high rate deposition process to deposit Si, Ge, and Si1-xGex films as an alternate to hot-wire CVD. Mossey Creek Solar is a start-up company with great expertise in the solar field. The primary interest is to create and preserve jobs in the solar sector by developing high-yield, low-cost, high-efficiency solar cells using MSC-patented and -proprietary technologies. The specific goal of this project was to produce large grain formation in thin, net-shape-thickness mc-Si wafers processed with high-purity silicon powder and ORNL's plasma arc lamp melting without introducing impurities that compromise absorption coefficient and carrier lifetime. As part of this project, ORNL also added specific pieces of equipment to enhance our ability to provide unique insight for the solar industry. These capabilities include a moisture barrier measurement system, a combined physical vapor deposition and sputtering system dedicated to cadmium-containing deposits, adeep level transient spectroscopy system useful for identifying defects, an integrating sphere photoluminescence system, and a high-speed ink jet printing system. These tools were combined with others to study the effect of defects on the performance of crystalline silicon and

Duty, C.; Angelini, J.; Armstrong, B.; Bennett, C.; Evans, B.; Jellison, G. E.; Joshi, P.; List, F.; Paranthaman, P.; Parish, C.; Wereszczak, A.

2012-10-15T23:59:59.000Z

382

Functional Materials for Energy | Advanced Materials | ORNL  

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

Energy Storage Fuel Cells Thermoelectrics Separations Materials Catalysis Sensor Materials Polymers and Composites Carbon Fiber Related Research Chemistry and Physics at Interfaces Materials Synthesis from Atoms to Systems Materials Characterization Materials Theory and Simulation Energy Frontier Research Centers Advanced Materials Home | Science & Discovery | Advanced Materials | Research Areas | Functional Materials for Energy SHARE Functional Materials for Energy The concept of functional materials for energy occupies a very prominent position in ORNL's research and more broadly the scientific research sponsored by DOE's Basic Energy Sciences. These materials facilitate the capture and transformation of energy, the storage of energy or the efficient release and utilization of stored energy. A different kind of

383

Materials Technology @ TMS  

Science Conference Proceedings (OSTI)

ESTABLISHED MATERIALS TECHNOLOGIES ... Specifically, digital resources are available relating to materials for nuclear power, materials sustainability, and  ...

384

Information about Materials Properties  

Science Conference Proceedings (OSTI)

Table 6   Examples of materials information required during detail design...identification Material class (metal, plastic, ceramic composite) Material subclass Material industry designation Material product form Material condition designation (temper, heat treatment, etc.) Material specification Material alternative names Material component designations (composite/assembly)...

385

Questions and Answers - What's the melting point of steel?  

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

If you jumped into a pool of liquid oxygen,would your body instantly crystallize? If you jumped into a pool of liquid oxygen,<br>would your body instantly crystallize? Previous Question (If you jumped into a pool of liquid oxygen, would your body instantly crystallize?) Questions and Answers Main Index Next Question (What is a material with a freezing point above 0 degrees Celsius?) What is a material with a freezingpoint above 0 degrees Celsius? What's the melting point of steel? That depends on the alloy of steel you are talking about. The term alloy is almost always used incorrectly these days, especially amongst bicyclists. They use the term to mean aluminum. What the term alloy really means is a mixture of metals, any kind of metals. Almost all metal used today is a mixture and therefore an alloy. Most steel has other metals added to tune its properties, like strength,

386

Microsoft PowerPoint - factoids  

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

tennis ball size quantity tennis ball size quantity of nuclear fuel commonly used in commercial nuclear plants can power the average daily needs in the U.S. of 200,000 homes. It would take 31 boxcars of coal, at 100 tons per boxcar, to generate the same 250 MWe of power. Reducing the threat of nuclear weapon proliferation Argonne's Reduced Enrichment for Research and Test Reactors (RERTR) program, initiated in 1978, has long utilized our nuclear expertise to convert research & test reactors using high-enriched uranium (HEU) to low enriched uranium (LEU) fuel - a material that cannot be diverted for direct use in nuclear weapons. 63 reactors in 32 countries from Argentina to Uzbekistan have been converted; 66 additional reactors are prime candidates. RERTR is a key element of the nation's efforts to

387

VT PowerPoint Template  

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

DISTRIBUTED FIBER OPTIC SENSOR FOR DISTRIBUTED FIBER OPTIC SENSOR FOR ON-LINE MONITORING OF COAL GASIFIER REFRACTORY HEALTH DE-FE0005703 Anbo Wang, Cheng Ma Virginia Tech Center for Photonics Technology Blacksburg, VA 24061 awang@vt.edu, cma1@vt.edu http://photonics.ece.vt.edu/ 1 Advanced Research Sensor and Controls Project Review Meeting DOE NETL Morgantown, WV 03/12/2012 Outline * Motivation, Overview & Objectives * Background and Fundamentals of Proposed Technology * Project Scope and Work Plan * Project Progress 2 MOTIVATION AND OBJECTIVES 3 Motivation * Refractory health monitoring in slagging coal gasifiers: * Rapid corrosion of refractory materials. * High-temperature reducing environment. * Difficult to predict remaining refractory life. * Localized thinning, spallation, cracking.

388

Engineering to Control Noise, Loading, and Optimal Operating Points  

Science Conference Proceedings (OSTI)

Successful engineering of low-energy nuclear systems requires control of noise, loading, and optimum operating point (OOP) manifolds. The latter result from the biphasic system response of low-energy nuclear reaction (LENR)/cold fusion systems, and their ash production rate, to input electrical power. Knowledge of the optimal operating point manifold can improve the reproducibility and efficacy of these systems in several ways. Improved control of noise, loading, and peak production rates is available through the study, and use, of OOP manifolds. Engineering of systems toward the OOP-manifold drive-point peak may, with inclusion of geometric factors, permit more accurate uniform determinations of the calibrated activity of these materials/systems.

Mitchell R. Swartz

2000-11-12T23:59:59.000Z

389

Performance of Photovoltaic Maximum Power Point Tracking Algorithms in the Presence of Noise  

E-Print Network (OSTI)

algorithms for stand- alone photovoltaic systems," Solar Energy Materials and Solar Cells, vol. 90, no. 11 of a maximum power point tracker," in IEEE Photovolatic Specialists Conference, 2008, pp. 1­3. [10] W. Wu, N

Odam, Kofi

390

Apparatus for draining lower drywell pool water into suppresion pool in boiling water reactor  

DOE Patents (OSTI)

An apparatus which mitigates temperature stratification in the suppression pool water caused by hot water drained into the suppression pool from the lower drywell pool. The outlet of a spillover hole formed in the inner bounding wall of the suppression pool is connected to and in flow communication with one end of piping. The inlet end of the piping is above the water level in the suppression pool. The piping is routed down the vertical downcomer duct and through a hole formed in the thin wall separating the downcomer duct from the suppression pool water. The piping discharge end preferably has an elevation at or near the bottom of the suppression pool and has a location in the horizontal plane which is removed from the point where the piping first emerges on the suppression pool side of the inner bounding wall of the suppression pool. This enables water at the surface of the lower drywell pool to flow into and be discharged at the bottom of the suppression pool.

Gluntz, Douglas M. (San Jose, CA)

1996-01-01T23:59:59.000Z

391

Nondestructive Evaluation: Nondestructive Evaluation for Material Characterization  

Science Conference Proceedings (OSTI)

This report summarizes the results of nondestructive evaluation (NDE) for material characterization conducted on Alloy 600 samples that have undergone changes in material properties due to simulated operating conditions, including heat treatment, three-point bending load, cracking, and repair. The overall objective was to evaluate the feasibility of using eddy current and ultrasonic data fusion techniques to conduct NDE for material characterization by relying on a set of fabricated Alloy 600 samples.

2007-12-11T23:59:59.000Z

392

Fixed-Point Cell Mini Workshop  

Science Conference Proceedings (OSTI)

... The ITS-90 Fixed-Point Cell Mini-Workshop is scheduled to be given at ... hands-on" laboratory training in the realization of ITS-90 fixed-point cells. ...

2011-10-03T23:59:59.000Z

393

InitiativesTalkingPoints | Department of Energy  

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

ativesTalkingPoints&0; More Documents & Publications Suggested Talking Points for Hydrogen Road Tour &8220;C-3E&8221; WOMEN&8217;S INITIATIVE: Renewable Energy and a Smart Grid...

394

Function points as a universal software metric  

Science Conference Proceedings (OSTI)

Function point metrics are the most accurate and effective metrics yet developed for software sizing and also for studying software productivity, quality, costs, risks, and economic value. Unlike the older "lines of code" metric function points can be ...

Capers Jones

2013-07-01T23:59:59.000Z

395

Minimal capacity points and the Lowest eigenfunctions  

E-Print Network (OSTI)

We introduce the concept of the point of minimal capacity of the domain, and observe a connection between this point and the lowest eigenfunction of a Laplacian on this domain, in one special case.

Mark Levi; Jia Pan

2011-04-04T23:59:59.000Z

396

Materials Science Evaluation Portal  

Science Conference Proceedings (OSTI)

NIST Home > Materials Science Evaluation Portal. Materials Science Evaluation Portal. Subject Areas. Modeling; Nondestructive; ...

2013-08-08T23:59:59.000Z

397

Materials Performance Staff  

Science Conference Proceedings (OSTI)

... Kinetics Staff; Materials Science and Engineering Division Staff Directory; MML Organization. Contact. Materials Performance ...

2013-08-20T23:59:59.000Z

398

Corrosion resistant ceramic materials  

DOE Patents (OSTI)

Ceramic materials which exhibit stability in severely-corrosive environments having high alkali-metal activity, high sulfur/sulfide activity and/or molten halides at temperatures of 200.degree.-550.degree. C. or organic salt (including SO.sub.2 and SO.sub.2 Cl.sub.2) at temperatures of 25.degree.-200.degree. C. These sulfide ceramics form stoichiometric (single-phase) compounds with sulfides of Ca, Li, Na, K, Al, Mg, Si, Y, La, Ce, Ga, Ba, Zr and Sr and show melting-points that are sufficiently low and have excellent wettability with many metals (Fe, Ni, Mo) to easily form metal/ceramic seals. Ceramic compositions are also formulated to adequately match thermal expansion coefficient of adjacent metal components.

Kaun, Thomas D. (320 Willow St., New Lenox, IL 60451)

1995-01-01T23:59:59.000Z

399

Corrosion resistant ceramic materials  

DOE Patents (OSTI)

Ceramic materials which exhibit stability in severely-corrosive environments having high alkali-metal activity, high sulfur/sulfide activity and/or molten halides at temperatures of 200.degree.-550.degree. C. or organic salt (including SO.sub.2 and SO.sub.2 Cl.sub.2) at temperatures of 25.degree.-200.degree. C. These sulfide ceramics form stoichiometric (single-phase) compounds with sulfides of Ca, Li, Na, K, Al, Mg, Si, Y, La, Ce, Ga, Ba, Zr and Sr and show melting-points that are sufficiently low and have excellent wettability with many metals (Fe, Ni, Mo) to easily form metal/ceramic seals. Ceramic compositions are also formulated to adequately match thermal expansion coefficient of adjacent metal components.

Kaun, Thomas D. (320 Willow St., New Lenox, IL 60451)

1996-01-01T23:59:59.000Z

400

Selective spatio-temporal interest points  

Science Conference Proceedings (OSTI)

Recent progress in the field of human action recognition points towards the use of Spatio-Temporal Interest Points (STIPs) for local descriptor-based recognition strategies. In this paper, we present a novel approach for robust and selective STIP detection, ... Keywords: Action recognition, Bag-of-words, Complex scenes, Local descriptors, Multiple actors, Spatio-temporal interest points, Support vector machines

Bhaskar Chakraborty; Michael B. Holte; Thomas B. Moeslund; Jordi Gonzílez

2012-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "boiling point material" 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

Final safety evaluation report related to the certification of the Advanced Boiling Water Reactor design. Supplement 1  

SciTech Connect

This report supplements the final safety evaluation report (FSER) for the US Advanced Boiling Water Reactor (ABWR) standard design. The FSER was issued by the US Nuclear Regulatory Commission (NRC) staff as NUREG-1503 in July 1994 to document the NRC staff`s review of the US ABWR design. The US ABWR design was submitted by GE Nuclear Energy (GE) in accordance with the procedures of Subpart B to Part 52 of Title 10 of the Code of Federal Regulations. This supplement documents the NRC staff`s review of the changes to the US ABWR design documentation since the issuance of the FSER. GE made these changes primarily as a result of first-of-a-kind-engineering (FOAKE) and as a result of the design certification rulemaking for the ABWR design. On the basis of its evaluations, the NRC staff concludes that the confirmatory issues in NUREG-1503 are resolved, that the changes to the ABWR design documentation are acceptable, and that GE`s application for design certification meets the requirements of Subpart B to 10 CFR Part 52 that are applicable and technically relevant to the US ABWR design.

NONE

1997-05-01T23:59:59.000Z

402

Nuclear Desalination Complex with VK-300 Boiling-Type Reactor Facility  

E-Print Network (OSTI)

With regard to the global-scale development of desalination technologies and the stable growth demand for them, Russia also takes an active part in the development of these technologies. Two major aspects play a special role here: they are providing the desalination process with power and introducing new materials capable of making the production of fresh water cheaper and of raising the technical reliability of desalination units. In achieving these tasks, the focus is on the most knowledge-intensive issues, to which Russia is capable of making its contribution based both on the experience of developing national nuclear power and the experience of developing, manufacturing and operating desalination units, including the use of nuclear power (the experience of BN-350 in Aktau (formerly Shevchenko), Kazakhstan). In terms of design, the Nuclear Desalination Complex (NDC) with a VK-300 reactor facility is a modification of a nuclear power unit with a VK-300 reactor developed for application at Russian nuclear cogeneration plants. A power unit

B. A. Gabaraev; Yu. N. Kuznetzov; A. A. Romenkov; Yu. A. Mishanina

2004-01-01T23:59:59.000Z

403

BWR (boiling-water reactor) radiation control: In-plant demonstration at Vermont Yankee: Final report  

Science Conference Proceedings (OSTI)

Results of the RP1934 program, which was established by EPRI in 1981 to demonstrate the adequacy of BRAC program (RP819) principles for BWR radiation control at Vermont Yankee, are presented. Evaluations were performed of the effectiveness of optimization of purification system performance, control of feedwater dissolved oxygen concentrations, minimization of corrosion product and ionic transport, and improved startup, shutdown, and layup practices. The impact on shutdown radiation levels of these corrective actions was assessed based on extensive primary system radiation survey and component gamma scan data. Implementation of the BRAC recommendations was found to be insufficient to reduce the rate of activity buildup on out-of-core surfaces at Vermont Yankee, and additional corrective actions were found necessary. Specifically, replacement of cobalt-bearing materials in the control rod drive pins and rollers and feedwater regulating valves was pursued as was installation of electropolished 316 stainless steel during a recirculation piping replacement program. Aggressive programs to further reduce copper concentrations in the reactor water by improving condensate demineralizer efficiency and to minimize organic ingress to the power cycle by reducing organic concentrations in recycled radwaste also were undertaken. Evaluations of the impact on activity buildup of several pretreatment processes including prefilming in moist air, preexposure to high temperature water containing zinc, and electropolishing also were performed in a test loop installed in the reactor water cleanup system. A significant beneficial impact of electropolishing was shown to be present for periods up to 6000 hours.

Palino, G.F.; Hobart, R.L.; Sawochka, S.G.

1987-10-01T23:59:59.000Z

404

Gas storage materials, including hydrogen storage materials  

DOE Patents (OSTI)

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

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

2013-02-19T23:59:59.000Z

405

AMF Deployment, Point Reyes National Seashore, California  

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

California California Point Reyes Deployment AMF Home Point Reyes Home Data Plots and Baseline Instruments Experiment Planning MASRAD Proposal Abstract and Related Campaigns Outreach Posters Climate Research at Point Reyes National Seashore (horizontal) Climate Research at Point Reyes National Seashore (vertical) News Campaign Images AMF Deployment, Point Reyes National Seashore, California Point Reyes National Seashore, on the California coast north of San Francisco. Shelters: 38° 5' 30.51" N, 122° 57' 19.90" W Instrument Field: 38° 5' 27.6" N, 122° 57' 25.80" W Altitude: 8 meters Point Reyes National Seashore, on the California coast north of San Francisco, was the location of the first deployment of the DOE's Atmospheric Radiation Measurement (ARM) Mobile Facility (AMF). The ARM

406

Analysis of Crossover Points for MVLT Superclass  

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

of Crossover Points for MVLT Superclass of Crossover Points for MVLT Superclass 58761v1 Page 1 White Paper - Analysis of Cross-Over Points for Grain-Oriented Electrical Steel and Amorphous Ribbon for the MVLT Superclass Cross-over points for the Medium Voltage Liquid Filled distribution transformer super-class have been analyzed based on the Engineering Analysis provided by the Department of Energy. For the purpose of this white paper, a cross-over point is defined as where the low-cost curve fitted to the point cloud for all of the transformers with M-3 grain-oriented electrical steel core designs crosses the low-cost curve fitted to the point cloud for all of the transformers with amorphous (SA1) core designs. This analysis is based on the data from the DOE Engineering Analysis. It excludes uncorroborated data

407

Theory and models of material erosion and lifetime during plasma instabilities in a tokamak environment.  

SciTech Connect

Surface and structural damage to plasma-facing components (PFCs) due to the frequent loss of plasma confinement remains a serious problem for the tokamak reactor concept. The deposited plasma energy causes significant surface erosion, possible structural failure, and frequent plasma contamination. Surface damage consists of vaporization, spallation, and liquid splatter of metallic materials. Structural damage includes large temperature increases in structural materials and at the interfaces between surface coatings and structural members. To evaluate the lifetimes of plasma-facing materials and nearby components and to predict the various forms of damage that they experience, comprehensive models (contained in the HEIGHTS computer simulation package) are developed, integrated self-consistently, and enhanced. Splashing mechanisms such as bubble boiling and various liquid magnetohydrodynamic instabilities and brittle destruction mechanisms of nonmelting materials are being examined. The design requirements and implications of plasma-facing and nearby components are discussed, along with recommendations to mitigate and reduce the effects of plasma instabilities on reactor components.

Hassanein, A.; Konkashbaev, I.

1999-11-08T23:59:59.000Z

408

Functional Materials for Energy | Advanced Materials | ORNL  

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

Energy Storage Fuel Cells Thermoelectrics Separations Materials Catalysis Sensor Materials Polymers and Composites Carbon Fiber Related Research Chemistry and Physics at...

409

Materials Science & Tech Division | Advanced Materials | ORNL  

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

accident tolerant fuels, and providing the materials underpinning for fusion energy. The nuclear materials program leverages off both fundamental and applied capabilities within...

410

Sandia National Labs: Materials Science & Engineering, Materials...  

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

MATERIALS SCIENCE & ENGINEERING HOME OrganizationMission Capabilities Awards & Accomplishments Patents MATERIALS SCIENCE AND ENGINEERING CENTER Techniques 1 2 3 4 5 6 7 These are...

411

Materials Project: A Materials Genome Approach  

DOE Data Explorer (OSTI)

Technological innovation - faster computers, more efficient solar cells, more compact energy storage - is often enabled by materials advances. Yet, it takes an average of 18 years to move new materials discoveries from lab to market. This is largely because materials designers operate with very little information and must painstakingly tweak new materials in the lab. Computational materials science is now powerful enough that it can predict many properties of materials before those materials are ever synthesized in the lab. By scaling materials computations over supercomputing clusters, this project has computed some properties of over 80,000 materials and screened 25,000 of these for Li-ion batteries. The computations predicted several new battery materials which were made and tested in the lab and are now being patented. By computing properties of all known materials, the Materials Project aims to remove guesswork from materials design in a variety of applications. Experimental research can be targeted to the most promising compounds from computational data sets. Researchers will be able to data-mine scientific trends in materials properties. By providing materials researchers with the information they need to design better, the Materials Project aims to accelerate innovation in materials research.[copied from http://materialsproject.org/about] You will be asked to register to be granted free, full access.

Ceder, Gerbrand [MIT; Persson, Kristin [LBNL

412

Materials Under Extremes | ORNL  

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

Materials Defect Physics Lightweight Related Research Functional Materials for Energy Chemistry and Physics at Interfaces Materials Synthesis from Atoms to Systems...

413

NETL: Advanced Research - Materials  

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

Performance Materials High Temperature Materials The environment inside a slagging gasifier is one of the worst imaginable from a materials standpoint. Another extreme...

414

Nuclear Materials Committee  

Science Conference Proceedings (OSTI)

The Nuclear Materials Committee is part of the Structural Materials Division. Our Mission: Includes the scientific and technical aspects of materials which are ...

415

Revised analyses of decommissioning for the reference boiling water reactor power station. Effects of current regulatory and other considerations on the financial assurance requirements of the decommissioning rule and on estimates of occupational radiation exposure - main report. Final report  

SciTech Connect

The NRC staff is in need of updated bases documentation that will assist them in assessing the adequacy of the licensee submittals, from the viewpoint of both the planned actions, including occupational radiation exposure, and the probable costs. The purpose of this reevaluation study is to update the needed bases documentation. This report presents the results of a review and reevaluation of the PNL 1980 decommissioning study of the Washington Public Power Supply System`s Washington Nuclear Plant Two (WNP-2), which is a boiling water reactor (BWR), located at Richland, Washington, including all identifiable factors and cost assumptions which contribute significantly to the total cost of decommissioning the plant for the DECON, SAFSTOR, and ENTOMB decommissioning alternatives. These alternatives now include an initial 5-7 year period during which time the spent fuel is stored in the spent fuel pool prior to beginning major disassembly or extended safe storage of the plant. Included for information (but not part of the license termination cost) is an estimate of the cost to demolish the decontaminated and clean structures on the site and to restore the site to a {open_quotes}green field{close_quotes} condition. This report also includes consideration of the NRC requirement that decontamination and decommissioning activities leading to termination of the nuclear license be completed within 60 years of final reactor shutdown, consideration of packaging and disposal requirements for materials whose radionuclide concentrations exceed the limits for Class C low- level waste (i.e., Greater-Than-Class C), and reflects 1993 costs for labor, materials, transport, and disposal activities. Sensitivity of the total license termination cost to the disposal costs at different low-level radioactive waste disposal sites, to different depths of contaminated concrete surface removal within the facilities, and to different transport distances is also examined.

Smith, R.I.; Bierschbach, M.C.; Konzek, G.J.; McDuffie, P.N.

1996-07-01T23:59:59.000Z

416

Solar Superabsorption of Semiconductor Materials  

E-Print Network (OSTI)

We theoretically demonstrate the fundamental limit in volume for given materials (e.g. Si, a-Si, CdTe) to fully absorb the solar radiation above bandgap, which we refer as solar superabsorption limit. We also point out the general principles for experimentally designing light trapping structures to approach the superabsorption. This study builds upon an intuitive model, coupled leaky mode theory (CLMT), for the analysis of light absorption in nanostructures. The CLMT provides a useful variable transformation. Unlike the existing methods that rely on information of physical features (e.g. morphology, dimensionality) to analyze light absorption, the CLMT can evaluate light absorption in given materials with only two variables, the radiative loss and the resonant wavelength, of leaky modes, regardless the physical features of the materials. This transformation allows for surveying the entire variable space to find out the solar superabsorption and provides physical insights to guide the design of solar superabso...

Yu, Yiling; Cao, Linyou

2013-01-01T23:59:59.000Z

417

End Points Management | Department of Energy  

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

Management Management End Points Management The policy of the EM is that a formal project management approach be used for the planning, managing, and conducting of its projects. Specifying and achieving end points is a systematic, engineering way of proceeding from an existing condition to a stated desired final set of conditions in which the facility is safe and can be economically monitored and maintained. An end point method is a way to translate broad mission statements to explicit goals that are readily understood by engineers and craft personnel who do the work. (It should be recognized that while end points as addressed here are for a final set of conditions for deactivation, they may represent an interim point for the overall EM cleanup goal.) End Points Management

418

Reactor and method for hydrocracking carbonaceous material  

DOE Patents (OSTI)

Solid, carbonaceous material is cracked in the presence of hydrogen or other reducing gas to provide aliphatic and aromatic hydrocarbons of lower molecular weight for gaseous and liquid fuels. The carbonaceous material, such as coal, is entrained as finely divided particles in a flow of reducing gas and preheated to near the decomposition temperature of the high molecular weight polymers. Within the reactor, small quantities of oxygen containing gas are injected at a plurality of discrete points to burn corresponding amounts of the hydrogen or other fuel and elevate the mixture to high temperatures sufficient to decompose the high molecular weight, carbonaceous solids. Turbulent mixing at each injection point rapidly quenches the material to a more moderate bulk temperature. Additional quenching after the final injection point can be performed by direct contact with quench gas or oil. The reactions are carried out in the presence of a hydrogen-containing reducing gas at moderate to high pressure which stabilizes the products.

Duncan, Dennis A. (Downers Grove, IL); Beeson, Justin L. (Clarendon Hills, IL); Oberle, R. Donald (Hammond, IN); Dirksen, Henry A. (Harvey, IL)

1980-01-01T23:59:59.000Z

419

A phenomenological model of thermal-hydraulics of convective boiling during the quenching of hot rod bundles  

Science Conference Proceedings (OSTI)

After completion of the thermal-hydraulic model developed in a companion paper, the authors performed developmental assessment calculation of the model using steady-state and transient post-critical heat flux (CHF) data. This paper discusses the results of those calculations. The overall interfacial drag model predicted reasonable drag coefficients for both the nucleate boiling and the inverted annular flow (IAF) regimes. The predicted pressure drops agreed reasonably well with the measured data of two transient experiments, CCTF Run 14 and a Lehigh reflood test. The thermal-hydraulic model for post-CHF convective heat transfer predicted the rewetting velocities reasonably well for both experiments. The predicted average slope of the wall temperature traces for these tests showed reasonable agreement with the measured data, indicating that the transient-calculated precursory cooling rates agreed with measured data. The hot-patch model, in conjunction with the other thermal-hydraulic models, was capable of modeling the Winfrith post-CHF hot-patch experiments. The hot-patch model kept the wall temperatures at the specified levels in the hot-patch regions and did not allow any quench-front propagation from either the bottom or the top of the test section. The interfacial heat-transfer model tended to slightly underpredict the vapor temperatures. The maximum difference between calculated and measured vapor temperatures was 20%, with a 10% difference for the remainder of the runs considered. The wall-to-fluid heat transfer was predicted reasonably well, and the predicted wall temperatures were in reasonable agreement with measured data with a maximum relative error of less than 13%.

Unal, C.; Nelson, R.

1991-01-01T23:59:59.000Z

420

Inexact and accelerated proximal point algorithms  

E-Print Network (OSTI)

required, with the sum of total errors that can be possibly infinite. This is a remarkable fact that does not occur in the classical (non accelerated) proximal point ...

Note: This page contains sample records for the topic "boiling point material" 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

Josephson phase qubit with an optimal point  

SciTech Connect

Current fluctuations in a Josephson phase qubit are considered to be a source of decoherence, especially for pure dephasing. One possible way of evading such decoherence is to employ an optimal operation point as used in flux and charge qubits, where the qubit is insensitive to the bias fluctuations. However, there is no optimal point in a phase qubit since qubit energy splitting becomes monotonically smaller with increasing the bias current. Here we propose a phase qubit with an optimal point by introducing qubit energy splitting that depends nonmonotonically on the current bias realized in capacitively coupled Josephson junctions. The effect of junction asymmetry on the optimal point is also investigated.

Kosugi, Norihito; Fujii, Toshiyuki; Hatakenaka, Noriyuki [Graduate School of Integrated Arts and Sciences, Hiroshima University, Higashi-Hiroshima 739-8521 (Japan); Matsuo, Shigemasa [Graduate School of Integrated Arts and Sciences, Hiroshima University, Higashi-Hiroshima 739-8521 (Japan); Research Institute for Science and Engineering, Waseda University, Shinjuku-ku, Tokyo 169-8555 (Japan)

2010-01-01T23:59:59.000Z

422

Approximating the Radii of Point Sets?  

E-Print Network (OSTI)

p and flat F. Computing the radii of point sets is a fundamental problem ...... tributions, and order statistics,” Handbook of Combinatorial Optimization. (Vol.

423

Wisconsin Nuclear Profile - Point Beach Nuclear Plant  

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

Point Beach Nuclear Plant" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration...

424

New York Nuclear Profile - Indian Point  

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

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

425

Wolf Point Substation, Roosevelt County, Montana  

Science Conference Proceedings (OSTI)

The Western Area Power Administration (Western), an agency of the United States Department of Energy, is proposing to construct the 115-kV Wolf Point Substation near Wolf Point in Roosevelt County, Montana (Figure 1). As part of the construction project, Western's existing Wolf Point Substation would be taken out of service. The existing 115-kV Wolf Point Substation is located approximately 3 miles west of Wolf Point, Montana (Figure 2). The substation was constructed in 1949. The existing Wolf Point Substation serves as a Switching Station'' for the 115-kV transmission in the region. The need for substation improvements is based on operational and reliability issues. For this environmental assessment (EA), the environmental review of the proposed project took into account the removal of the old Wolf Point Substation, rerouting of the five Western lines and four lines from the Cooperatives and Montana-Dakota Utilities Company, and the new road into the proposed substation. Reference to the new proposed Wolf Point Substation in the EA includes these facilities as well as the old substation site. The environmental review looked at the impacts to all resource areas in the Wolf Point area. 7 refs., 6 figs.

Not Available

1991-05-01T23:59:59.000Z

426

FINAL_2013_NBC_Talking-Points  

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

ENERGY STAR National Building Competition Talking Points and Messages Competition Overview * For the fourth consecutive year, EPA's ENERGY STAR program is hosting the 2013...

427

PowerPoint Presentation | Department of Energy  

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

Presentation PowerPoint Presentation More Documents & Publications US Department of Energy Office of the Chief Information Officer PARS II User Guide LES' URENCO-USA Facility...

428

End Point Implementation Examples | Department of Energy  

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

Examples End Point Implementation Examples More Documents & Publications Post-Deactivation Surveillance and Maintenance Planning Project Management Plan Examples 1 - 80...

429

Materials Technology @ TMS  

Science Conference Proceedings (OSTI)

May 28, 2012 ... Administrative & Policy Manual .... Materials and Society: Energy Technology, Policy, and Education; Materials Processing and Production; and ...

430

Magnetic Materials Staff  

Science Conference Proceedings (OSTI)

... Materials Science and Engineering Division Staff Directory; MML Organization. Contact. Magnetic Materials Group Robert Shull, Group Leader. ...

2012-10-09T23:59:59.000Z

431

Anisotropic Curie Temperature Materials  

Science Conference Proceedings (OSTI)

Symposium, Magnetic Materials for Energy Applications -III. Presentation Title, Anisotropic Curie Temperature Materials. Author(s), Harsh Deep Chopra, Jason ...

432

Material Properties References  

Science Conference Proceedings (OSTI)

... Thermal Conductivity. LNG Materials and Fluids. Ed. ... Aluminum 3003. Linear thermal expansion. LNG Materials and Fluids. Ed. ...

2013-02-05T23:59:59.000Z

433

emerging materials - TMS  

Science Conference Proceedings (OSTI)

…plenary discussion. Energy and Security; Nuclear Materials; Fuel Cells; Materials for Alternative Energy Applications. Advanced Metallic Composites and  ...

434

Bioinspired Materials Engineering  

Science Conference Proceedings (OSTI)

Conference Tools for Materials Science & Technology 2014 ... structured functional materials with improved and designed (piezo )electrical, magnetic, optical, ...

435

Multiscale Modeling of Materials  

Science Conference Proceedings (OSTI)

Oct 27, 2009 ... Parametric materials design integrating materials science, applied mechanics and quantum physics within a systems engineering framework ...

436

Radiation Shields Materials  

Science Conference Proceedings (OSTI)

About this Abstract. Meeting, Materials Science & Technology 2009. Symposium, Materials Solutions for the Nuclear Renaissance. Presentation Title, Radiation ...

437

Nanomechanical Materials Behavior Committee  

Science Conference Proceedings (OSTI)

The Nanomechanical Materials Behavior Committee is part of the Materials Processing & Manufacturing Division;. Our Mission: Focuses on the nanomechanical ...

438

Method for forming materials  

DOE Patents (OSTI)

A material-forming tool and a method for forming a material are described including a shank portion; a shoulder portion that releasably engages the shank portion; a pin that releasably engages the shoulder portion, wherein the pin defines a passageway; and a source of a material coupled in material flowing relation relative to the pin and wherein the material-forming tool is utilized in methodology that includes providing a first material; providing a second material, and placing the second material into contact with the first material; and locally plastically deforming the first material with the material-forming tool so as mix the first material and second material together to form a resulting material having characteristics different from the respective first and second materials.

Tolle, Charles R. (Idaho Falls, ID); Clark, Denis E. (Idaho Falls, ID); Smartt, Herschel B. (Idaho Falls, ID); Miller, Karen S. (Idaho Falls, ID)

2009-10-06T23:59:59.000Z

439

Microsoft PowerPoint - ZajcTribbleII.pptx  

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

Relativistic Heavy Ion Overview Relativistic Heavy Ion Overview NSAC Sub-committee presentation W A Zajc W.A. Zajc Columbia University Questions Addressed by Relativistic Heavy Ion Physics 2  Overarching questions: 4Are there new states of matter at extremely high Are there new states of matter at extremely high temperature and density? 4Can we explore the phase structure of a fundamental gauge theory via nuclear collisions? 4Can the study of strongly-coupled QCD matter inform our understanding of other gauge theories (including gravity)? (See back-up material for compendium) Questions Addressed by Relativistic Heavy Ion Physics 3  Discovery oriented questions: 4Is there a critical point in the QCD phase diagram? Is there a critical point in the QCD phase diagram? 4Are exotic (locally CP-violating) states

440

Materials Informatics: Fast Track to New Materials  

SciTech Connect

Current methods for new materials development focus on either deeper fundamental-level studies or generation of large quantities of data. The data challenge in materials science is not only the volume of data being generated by many independent investigators, but its heterogeneity and also its complexity that must be transformed, analyzed, correlated and communicated. Materials informatics addresses these issues. Materials informatics is an emerging information-based field combining computational, statistical, and mathematical approaches with materials sciences for accelerating discovery and development of new materials. Within the informatic framework, the various different forms of information form a system architecture, an iterative cycle for transforming data into knowledge.

Ferris, Kim F.; Peurrung, Loni M.; Marder, James M.

2007-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "boiling point material" 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

New statistical methods for detecting point alignments  

Science Conference Proceedings (OSTI)

Detection of straight-linear point alignments has a number of geological applications. Assessing the statistical significance of such alignments is relatively straightforward in the case of overall lineament orientation, but becomes complicated for non-stationary ... Keywords: Alignment detection, Directional statistics, Point patterns, Spatial analysis

Ø. Hammer

2009-03-01T23:59:59.000Z

442

Interaction between Injection Points during Hydraulic Fracturing  

E-Print Network (OSTI)

We present a model of the hydraulic fracturing of heterogeneous poroelastic media. The formalism is an effective continuum model that captures the coupled dynamics of the fluid pressure and the fractured rock matrix and models both the tensile and shear failure of the rock. As an application of the formalism, we study the geomechanical stress interaction between two injection points during hydraulic fracturing (hydrofracking) and how this interaction influences the fracturing process. For injection points that are separated by less than a critical correlation length, we find that the fracturing process around each point is strongly correlated with the position of the neighboring point. The magnitude of the correlation length depends on the degree of heterogeneity of the rock and is on the order of 30-45 m for rocks with low permeabilities. In the strongly correlated regime, we predict a novel effective fracture-force that attracts the fractures toward the neighboring injection point.

Hals, Kjetil M D

2012-01-01T23:59:59.000Z

443

Definition: Point Absorber | Open Energy Information  

Open Energy Info (EERE)

Point Absorber Point Absorber Jump to: navigation, search Dictionary.png Point Absorber Wave energy capture device, with principal dimension relatively small compared to the wavelength, and is able to capture energy from a wave front greater than the physical dimension of the device. There are floating and submerged models.[1] Related Terms Wave power; PowerBouy References ↑ http://en.wikipedia.org/wiki/Wave_power Poi LikeLike UnlikeLike You like this.Sign Up to see what your friends like. ntabsorber.jpg Example of a Point Absorber A submerged pressure differential wave energy capturing device, which can be considered a fully submerged point absorber. A pressure differential is induced within the device as the wave passes, driving a fluid pump to create mechanical energy. Retrieved from

444

NEWTON's Material Science References  

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

Material Science References Material Science References Do you have a great material science reference link? Please click our Ideas page. Featured Reference Links: Materials Research Society Materials Research Society The Materials Research Society has assembled many resources in its Materials Science Enthusiasts site. This site has information for the K-12 audience, general public, and materials science professionals. Material Science nanoHUB nanHUB.org is the place for nanotechnology research, education, and collaboration. There are Simulation Programs, Online Presentations, Courses, Learning Modules, Podcasts, Animations, Teaching Materials, and more. (Intened for high school and up) Materials Science Resources on the Web Materials Science Resources on the Web This site gives a good general introduction into material science. Sponsered by Iowa State, it talks about what material science is, ceramics and composites, and other topics.

445

Results from Point Contact Tunnelling Spectroscopy and Atomic Layer Deposition  

SciTech Connect

We have shown previously that magnetic niobium oxides can influence the superconducting density of states at the surface of cavity-grade niobium coupons. We will present recent results obtained by Point Contact Tunneling spectroscopy (PCT) on coupons removed from hot and cold spots in a niobium cavity, as well as a comparative study of magnetic oxides on mild baked/unbaked electropolished coupons. We will also describe recent results obtained from coated cavities, ALD films properties and new materials using Atomic Layer Deposition (ALD).

Proslier, Th. [Illinois Institute of Technology; Zasadzinski, J. [Illinois Institute of Technology; Ciovati, Gianluigi [JLAB; Kneisel, Peter K. [JLAB; Elam, J. W. [ANL; Norem, J. [ANL; Pellin, M. J. [ANL

2009-11-01T23:59:59.000Z

446

Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 2. Appendices. Technical report, September 1977-October 1979  

SciTech Connect

Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWE. This volume contains the appendices.

Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

1980-06-01T23:59:59.000Z

447

Environmental Assessment for Authorizing the Puerto Rico Electric Power Authority (PREPA) to allow Public Access to the Boiling Nuclear Superheat (BONUS) Reactor Building, Rincon, Puerto Rico  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy (DOE) proposes to consent to a proposal by the Puerto Rico Electric Power Authority (PREPA) to allow public access to the Boiling Nuclear Superheat (BONUS) reactor building located near Rincon, Puerto Rico for use as a museum. PREPA, the owner of the BONUS facility, has determined that the historical significance of this facility, as one of only two reactors of this design ever constructed in the world, warrants preservation in a museum, and that this museum would provide economic benefits to the local community through increased tourism. Therefore, PREPA is proposing development of the BONUS facility as a museum.

N /A

2003-02-24T23:59:59.000Z

448

Educational Material Science Games  

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

Material Science Games Material Science Games Do you have a great material science game? Please click our Ideas page. Featured Games: >KS2 Bitsize BBC - Materials KS2 Bitsize BBC - Materials Sponsored by the BBC, K2S Bitsize offers tons of free online science games including a section on materials. Learn about the changes in materials, changing states, heat, rocks, soils, solids, liquids, gases, and much more. Science Kids - Properties of Materials Science Kids - Properties of Materials Learn about the properties of materials as you experiment with a variety of objects in this great science activity for kids. Discover the interesting characteristics of materials; are they flexible, waterproof, strong or transparent? Characteristics of Materials - BBC Schools Characteristics of Materials - BBC Schools

449

Strategies for sharing a floating point unit between SPEs  

E-Print Network (OSTI)

Floating Point Unit . . . . . . . . . . . . . . . . . . .compliant floating point unit”. In DATE ’06: Proceedings offor sharing a Floating Point Unit between SPEs A Thesis

Lugo Martinez, Jose E.

2010-01-01T23:59:59.000Z

450

Suggested Talking Points for Hydrogen Road Tour | Department...  

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

Suggested Talking Points for Hydrogen Road Tour Suggested Talking Points for Hydrogen Road Tour Suggested Talking Points for Hydrogen Road Tour More Documents & Publications...

451

Microsoft PowerPoint - Tsinghua Slideshow final for distribution...  

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

PowerPoint - Tsinghua Slideshow final for distribution (2) Microsoft PowerPoint - Tsinghua Slideshow final for distribution (2) Microsoft PowerPoint - Tsinghua Slideshow final for...

452

End Points Specification Methods | Department of Energy  

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

End Points Specification Methods End Points Specification Methods End Points Specification Methods Two methods to develop end point specifications are presented. These have evolved from use in the field for deactivation projects. The hierarchical method is systematic, comprehensive, and completely defensible as to the basis for each specification. This method may appear complex to the uninitiated, but it is a straightforward application of a systematic engineering approach. It is labor intensive only during the final stage. This method is appropriate to the type of project involving a complex facility that contains process systems and a variety of contaminated areas or other hazards. The checklist method is an approach that is more appropriate to facilities which require less detailed planning, such as for industrial

453

Tribal Points of Contacts | Department of Energy  

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

Points of Contacts Points of Contacts Tribal Points of Contacts US DOE-Office of Environmental Management 1000 Independence Avenue, SW Washington, DC 20585 ph: (202) 586-5944 fax: (202) 586-5000 Richland Operations Office- Hanford Indian Nations Program P.O. Box 550- MSIN A7-75 Richland, WA 99352 ph: (509) 376-6332 fax: (509) 376-1563 West Valley Demonstration Project Tribal Government Liaison P.O. Box 191- 10282 Rock Springs Road West Valley, NY 14171 ph: (716) 942-4629 fax: (716) 942-2068 Albuquerque Operations Office Tribal Government Liaison P.O. Box 5400 Albuquerque, NM 87185 ph: (505) 845-5977 fax: (505) 845-4154 Tribal Points of Contact Richland Operations Office: Hanford Albuquerque Operations Office: Yakama Indian Nation Environmental Restoration/ Waste Management Program

454

Star Point Wind Farm | Open Energy Information  

Open Energy Info (EERE)

Point Wind Farm Point Wind Farm Jump to: navigation, search Name Star Point Wind Farm Facility Star Point Wind Farm Sector Wind energy Facility Type Commercial Scale Wind Facility Status In Service Owner Iberdrola Renewables Developer Iberdrola Renewables Energy Purchaser Modesto Irrigation District Location Near Moro OR Coordinates 45.474734°, -120.704412° 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":45.474734,"lon":-120.704412,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

455

Point380 LLC | Open Energy Information  

Open Energy Info (EERE)

Point380 LLC Point380 LLC Jump to: navigation, search Name Point380, LLC Place Boulder, Colorado Zip 80302 Sector Carbon Product Point380 provides carbon consulting and resource management solutions to a broad range of clients seeking energy related risk analysis and policy analysis. Coordinates 42.74962°, -109.714163° 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":42.74962,"lon":-109.714163,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

456

Cedar Point Wind Farm | Open Energy Information  

Open Energy Info (EERE)

Point Wind Farm Point Wind Farm Jump to: navigation, search Name Cedar Point Wind Farm Facility Cedar Point Wind Farm Sector Wind energy Facility Type Commercial Scale Wind Facility Status In Service Owner Enbridge Inc. Developer RES Americas Energy Purchaser Xcel Energy Location Elbert CO Coordinates 39.219417°, -104.537167° 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":39.219417,"lon":-104.537167,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

457

Saturation Point Analysis of Moist Convective Overturning  

Science Conference Proceedings (OSTI)

A unified approach to the thermodynamics of cloudy air, cloud-clear air mixing processes, atmospheric thermodynamic equilibrium structure and instability is formulated, using a new concept: the Saturation Point. This permits the representation of ...

Alan K. Betts

1982-07-01T23:59:59.000Z

458

INTERIOR-POINT METHODS FOR NONCONVEX NONLINEAR ...  

E-Print Network (OSTI)

Nov 4, 2005 ... problem is not convex, the algorithm will be searching for a local optimum. ..... the terms in the barrier objective of our infeasible interior-point method. ..... In order to enter dual feasibility restoration mode, we monitored the ...

459

Computing proximal points of nonconvex functions  

E-Print Network (OSTI)

The search direction used in an inexact proximal point algorithm is an .... term is a convex function on an open neighbourhood V of x; see [35, Thm. 10.33, p. ...... (3c

460

Indian Point-2 Flash Photography Event  

Science Conference Proceedings (OSTI)

This report presents the results of an independent assessment by the EPRI Electromagnetic & Radio Frequency Interference Working Group on a flash photography event at the Indian Point-2 (IP-2) nuclear power plant.

2009-03-17T23:59:59.000Z

Note: This page contains sample records for the topic "boiling point material" 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

Cloud Thermodynamic Models in Saturation Point Coordinates  

Science Conference Proceedings (OSTI)

One-dimensional thermodynamic models for cloud-environment mixing, evaporation into downdrafts and precipitation from updrafts are presented in a parallel treatment using convective pressure scales and saturation point coordinates. This common ...

Alan K. Betts

1982-10-01T23:59:59.000Z

462

N=8 Supergravity 4-point Amplitudes  

E-Print Network (OSTI)

We present the explicit expressions in N=8 supergravity for the bosonic 4-particle tree and 1-loop amplitudes including vectors and scalars. We also present the candidate 4-point UV divergences in a form of helicity amplitudes, corresponding to 3-loop manifestly N=8 supersymmetric and Lorentz covariant counterterm. This may shed some light on the 3-loop finiteness of N=8 SG and on a conjectured higher loop finiteness. We perform a supersymmetric deformation to complex momentum of the 4-point generating function including higher-loop counterterms and the 1-loop UV finite amplitudes. Using the explicit form of the scalar part of the 3-loop counterterm and of the 1-loop UV finite scalar 4-point amplitudes we find that they both have an unbroken E7 symmetry. We derive from E7 symmetry the low-energy theorem for the 1-loop n-point amplitudes.

Renata Kallosh; Ching Hua Lee; Tomas Rube

2008-11-20T23:59:59.000Z

463

N=8 Supergravity 4-point Amplitudes  

E-Print Network (OSTI)

We present the explicit expressions in N=8 supergravity for the bosonic 4-particle tree and 1-loop amplitudes including vectors and scalars. We also present the candidate 4-point UV divergences in a form of helicity amplitudes, corresponding to 3-loop manifestly N=8 supersymmetric and Lorentz covariant counterterm. This may shed some light on the 3-loop finiteness of N=8 SG and on a conjectured higher loop finiteness. We perform a supersymmetric deformation to complex momentum of the 4-point generating function including higher-loop counterterms and the 1-loop UV finite amplitudes. Using the explicit form of the scalar part of the 3-loop counterterm and of the 1-loop UV finite scalar 4-point amplitudes we find that they both have an unbroken E7 symmetry. We derive from E7 symmetry the low-energy theorem for the 1-loop n-point amplitudes.

Kallosh, Renata; Rube, Tomas

2009-01-01T23:59:59.000Z

464

Point-Contact Silicon Solar Cells  

Science Conference Proceedings (OSTI)

A new type of silicon photovoltaic cell called the point-contact cell is under development. This report describes the cell and an analytic model developed for use in design optimization. Necessary future cell development work is discussed.

1983-05-01T23:59:59.000Z

465

FortyPoint Seven | Open Energy Information  

Open Energy Info (EERE)

search Name FortyPoint Seven Place England, United Kingdom Zip BH14 8LQ Sector Biofuels Product A Biofuels company founded by John Nicholas, one of Biofuels Corporation...

466

Change-Point Detection in Meteorological Measurement  

Science Conference Proceedings (OSTI)

Statistical methods of change-point detection can be useful for discovering inhomogeneities in precipitation, air pressure, or temperature time series caused by a change in the measurement process such as a relocation of a gauge. The method is ...

Daniela Jarušková

1996-07-01T23:59:59.000Z

467

Points of Contact (POCs) | U.S. DOE Office of Science (SC)  

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

Points of Contact (POCs) Points of Contact (POCs) New Brunswick Laboratory (NBL) NBL Home About Organization Chart .pdf file (189KB) Points of Contact (POCs) History Directions Jobs Programs Certified Reference Materials (CRMs) Training Categorical Exclusion Determinations News Contact Information New Brunswick Laboratory U.S. Department of Energy Building 350 9800 South Cass Avenue Argonne, IL 60439-4899 P: (630) 252-2442 (NBL) P: (630) 252-2767 (CRM sales) F: (630) 252-6256 E: usdoe.nbl@ch.doe.gov About Points of Contact (POCs) Print Text Size: A A A RSS Feeds FeedbackShare Page Useful Websites and Email Addresses CRM Prices and Certificates CRM Ordering Information Customer Feedback General Questions (sales, shipping, general inquiries) Reference Materials (technical info, requests, projects)

468

Instrumentness for creativity mediation, materiality & metonymy  

Science Conference Proceedings (OSTI)

We introduce the concept instrumentness as a quality of human-computer interfaces. Instrumentness points to the way musical instruments are controlled and conceptualized through values such as virtuosity and playability, which are important for computer-mediated ... Keywords: activity theory, computer mediated creativity, instrumental interactions, instrumentness, interface aesthetics, materiality, mediation, metonymy, music composition

Olav W. Bertelsen; Morten Breinbjerg; Søren Pold

2007-06-01T23:59:59.000Z

469

Microsoft PowerPoint - Proceedings Cover Sheets  

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

Molecular-beam mass-spectrometric analysis of lignocellulosic materials, I. Herbaceous biomass. J. Anal. Appl. Pyrolysis 30: 125-144. Table 3 Depth, footprint, and volume...

470

Lower-Melting-Point Solder Alloy  

Science Conference Proceedings (OSTI)

Significant manufacturing cost reductions can be realized with ... and/or circuit board materials in product assembly in order to reduce production costs.

471

Photovoltaics R&D: At the Tipping Point  

DOE Green Energy (OSTI)

'' . . . with robust investments in research and market development, the picture changes dramatically.'' Thus, the realigned U.S. Photovoltaic Industry Roadmap highlights R&D as critical to the tipping point that will make solar photovoltaics (PV) significant in the U.S. energy portfolio--part of a well-designed plan that would bring ''2034 expectations'' to reality by 2020. Technology improvement and introduction depend on key, focused, and pertinent research contributions that range from the most fundamental through the applied. In this paper, we underscore the successes and relevance of our current systems-driven PV R&D programs, which are built on integrated capabilities. These capabilities span atomic-level characterization, nanotechnology, new materials design, interface and device engineering, theoretical guidance and modeling, processing, measurements and analysis, and process integration. This presentation identifies and provides examples of critical research tipping points needed to foster now and near technologies (primarily crystalline silicon and thin films) and to introduce coming generations of solar PV that provide options to push us to the next performance levels (devices with ultra-high efficiencies and with ultra-low cost). The serious importance of science and creativity to U.S. PV technology ownership--and the increased focus to accelerate the time from laboratory discovery to industry adoption--are emphasized at this ''tipping point'' for solar PV.

Kazmerski, L. L.

2005-01-01T23:59:59.000Z

472

Advanced Materials Processing  

Science Conference Proceedings (OSTI)

Feb 15, 2010... the copper bearing materials which did not contain inflammable materials due to a restriction on capacity of furnace waste heat boilers.

473

Advanced Materials | ORNL  

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

Research Areas Research Areas Research Highlights Facilities and Capabilities Science to Energy Solutions News & Awards Events and Conferences Supporting Organizations Directionally Solidified Materials Using high-temperature optical floating zone furnace to produce monocrystalline molybdenum alloy micro-pillars Home | Science & Discovery | Advanced Materials Advanced Materials | Advanced Materials SHARE ORNL has the nation's most comprehensive materials research program and is a world leader in research that supports the development of advanced materials for energy generation, storage, and use. We have core strengths in three main areas: materials synthesis, characterization, and theory. In other words, we discover and make new materials, we study their structure,

474

Material Properties References  

Science Conference Proceedings (OSTI)

... Cryogenics June 1962 p.230-235. Thermal Conductivity. LNG Materials and Fluids. Ed. ... Linear thermal expansion. LNG Materials and Fluids. Ed. ...

2013-02-05T23:59:59.000Z

475

Advanced Research Materials Program  

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

materials requirements for all fossil energy systems, including materials for advanced power generation and coal fuels technologies. Examples of these technologies include coal...

476

Material Design Tools  

Science Conference Proceedings (OSTI)

Mar 12, 2012 ... In this presentation, we will discuss our activities in developing an infrastructure, named MaterialsGenome® (Trademark of MaterialsGenome, ...

477

Materials Technology @ TMS  

Science Conference Proceedings (OSTI)

Defining the data challenges associated with building the materials innovation infrastructure at the core of the U.S. Materials Genome Initiative (MGI) was the ...

478

Novel Materials and Phenomenon  

Science Conference Proceedings (OSTI)

Mar 6, 2013 ... Magnetic Materials for Energy Applications -III: Novel Materials and ... In traditional Permanent Magnet Machines, such as motors and ...

479

MATERIALS TRANSFER AGREEMENT  

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

MTAXX-XXX 1 MATERIAL TRANSFER AGREEMENT for Manufacturing Demonstration Facility and Carbon Fiber Technology Facility In order for the RECIPIENT to obtain materials, the RECIPIENT...

480

Photovoltaic Cell Materials  

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

Although crystalline silicon cells are the most common type, photovoltaic (PV), or solar cells, can be made of many semiconductor materials. Each material has unique strengths and characteristics...

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481

Materials Technology @ TMS  

Science Conference Proceedings (OSTI)

DOE Awards $45 Million to Deploy Advanced Transportation Technologies · Novel Electrode Material Offers Alternative for Li-ion Batteries · New Materials Make ...

482

IOMMMS Global Materials Forum  

Science Conference Proceedings (OSTI)

Natural Fiber Composites – Significant Contribution to a Green Economy · Recent Development of Materials for Green Energy in Korea · The Role of Materials ...

483

EXPERIMENTAL INVESTIGATION OF THE EFFECTS OF ULTRASONIC VIBRATION ON BURNOUT HEAT FLUX WITH BOILING WATER. Final Summary Report, October 3, 1960-July 31, 1961  

SciTech Connect

Experimental results were obtained on the effect of an ultrasonic field on the burnout heat flux for water flowing at atmospheric pressure, through an annular flow channel formed by a 1/4-in.-diameter electrically heated tube and a concentric glass tube of 3/4-in. ID. The active length of the central heating element was 5 1/2 in. The ultrasonic transducer, which was operated at 25,000 cps and a maximum electrical input of 300 watts, was located at the inlet end of the flow channel. The ultrasonic waves were propagated in the water in the direction of flow and thus parallel to the surface of the heating element. Burnout conditions covered channel inlet flows from 1.61 to 6.25 ft/sec and subcooling from 16 to 28 deg F. No effect of the ultrasonic field on the burnout heat flux or on the visible boiling phenomena at burnout conditions was detectable. During boiling at heat fluxes well below burnout, the effect of the ultrasonic field was a reduction in the diameter of the envelope of bubble activity surrounding the heating element. Visual inspectibn appeared to show that this reduction was associated with a smaller average bubble size and a greater frequency of bubble formation. However, all evidence of the presence of the ultrasonic field vanished as the flow velocity increased or as the heat flux increased to the burnout level. (auth)

Romie, F.E.; Aronson, C.A.

1961-07-31T23:59:59.000Z

484

Prospective Life-Cycle Modeling of Novel Carbon Capture Materials  

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

Prospective Life-Cycle Modeling of Novel Carbon Capture Materials Speaker(s): Roger Sathre Date: December 5, 2011 - 3:30pm Location: 90-4133 Seminar HostPoint of Contact: Anita...