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Note: This page contains sample records for the topic "heavy naphtha boiling" 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.


1

Coal liquefaction process with increased naphtha yields  

DOE Patents (OSTI)

An improved process for liquefying solid carbonaceous materials wherein the solid carbonaceous material is slurried with a suitable solvent and then subjected to liquefaction at elevated temperature and pressure to produce a normally gaseous product, a normally liquid product and a normally solid product. The normally liquid product is further separated into a naphtha boiling range product, a solvent boiling range product and a vacuum gas-oil boiling range product. At least a portion of the solvent boiling-range product and the vacuum gas-oil boiling range product are then combined and passed to a hydrotreater where the mixture is hydrotreated at relatively severe hydrotreating conditions and the liquid product from the hydrotreater then passed to a catalytic cracker. In the catalytic cracker, the hydrotreater effluent is converted partially to a naphtha boiling range product and to a solvent boiling range product. The naphtha boiling range product is added to the naphtha boiling range product from coal liquefaction to thereby significantly increase the production of naphtha boiling range materials. At least a portion of the solvent boiling range product, on the other hand, is separately hydrogenated and used as solvent for the liquefaction. Use of this material as at least a portion of the solvent significantly reduces the amount of saturated materials in said solvent.

Ryan, Daniel F. (Friendswood, TX)

1986-01-01T23:59:59.000Z

2

Multizone naphtha reforming process  

Science Conference Proceedings (OSTI)

This patent describes a catalytic reforming process for conversion of a naphtha hydrocarbon at reforming conditions having at least two segregated catalyst zones. The improvement comprises contacting the hydrocarbon in a first zone with a first catalyst comprising tin and at least one platinum group metal deposited on a solid catalyst support followed by contacting in a second zone with a second catalyst comprising at least one metal selected from the group consisting of platinum group metals deposited on a solid catalyst support.

Fleming, B.

1987-05-05T23:59:59.000Z

3

Selective hydrocracking of light naphtha cuts  

Science Conference Proceedings (OSTI)

For the production of high-quality automotive gasolines, technology has been developed for a combined ''isoreforming'' process, in which hydrocracking of a heavy straight-run naphtha cut to give a high-octane component with an octane number of 84-86 (MM) is combined with catalytic reforming of the residual fraction from hydrocracking. The ''isoreforming'' technology can be used to produce AI-93 automotive gasolines with aromatic hydrocarbon contents of 45-49% by weight, without TEL, in yields of 78-82% by weight on the original feed. The authors also discuss a catalytic upgrading process for light straight-run naphtha distillates or raffinates from catalytic reforming. The influence of the depth of reaction in hydrocracking n-paraffins in the straight-run 62-105 degrees C cut on the yield of the C5-EP cut and its octane number is investigated.

Koslov, I.T.; Khavkin, V.A.; Nefedov, B.K.

1986-03-01T23:59:59.000Z

4

Method for hydrocracking a heavy polynuclear hydrocarbonaceous feedstock in the presence of a molten metal halide catalyst  

DOE Patents (OSTI)

A method for hydrocracking a heavy polynuclear hydrocarbonaceous feedstock to produce lighter hydrocarbon fuels by contacting the feedstock with hydrogen in the presence of a molten metal halide catalyst, the method comprising: mixing the feedstock with a heavy naphtha fraction which has an initial boiling point from about 100.degree. to about 160.degree. C. with a boiling point difference between the initial boiling point and the final boiling point of no more than about 50.degree. C. to produce a mixture; thereafter contacting the mixture with partially spent molten metal halide and hydrogen under temperature and pressure conditions so that the temperature is near the critical temperature of the heavy naphtha fraction; separating at least a portion of the heavy naphtha fraction and lighter hydrocarbon fuels from the partially spent molten metal halide, unreacted feedstock and reaction products; thereafter contacting the partially spent molten metal halide, unreacted feedstock and reaction products with hydrogen and fresh molten metal halide in a hydrocracking zone to produce additional lighter hydrocarbon fuels and separating at least a major portion of the lighter hydrocarbon fuels from the spent molten metal halide.

Gorin, Everett (San Rafael, CA)

1981-01-01T23:59:59.000Z

5

Process for removing polymer-forming impurities from naphtha fraction  

DOE Patents (OSTI)

Polymer precursor materials are vaporized without polymerization or are removed from a raw naphtha fraction by passing the raw naphtha to a vaporization zone and vaporizing the naphtha in the presence of a wash oil while stripping with hot hydrogen to prevent polymer deposits in the equipment. 2 figs.

Kowalczyk, D.C.; Bricklemyer, B.A.; Svoboda, J.J.

1983-12-27T23:59:59.000Z

6

Process for removing polymer-forming impurities from naphtha fraction  

DOE Patents (OSTI)

Polymer precursor materials are vaporized without polymerization or are removed from a raw naphtha fraction by passing the raw naphtha to a vaporization zone (24) and vaporizing the naphtha in the presence of a wash oil while stripping with hot hydrogen to prevent polymer deposits in the equipment.

Kowalczyk, Dennis C. (Pittsburgh, PA); Bricklemyer, Bruce A. (Avonmore, PA); Svoboda, Joseph J. (Pittsburgh, PA)

1983-01-01T23:59:59.000Z

7

Conversion of light naphthas over sulfided nickle erionite  

Science Conference Proceedings (OSTI)

A natural erionite ore has been exchanged with ammonium and nickel salts to yield a Ni/H erionite catalyst that is active and stable for selectively hydrocracking only the n-paraffins from light straight-run naphthas. The primary product is a C[sup 5+] liquid that is 15-20 octane numbers higher than the feed and a propane- and butane-rich gas by-product. Results from a 110-day pilot plant run demonstrated that a catalyst life of more than 1 year should be possible. Naphthenes, aromatics, and isoparaffins are neither produced nor consumed in this process, resulting in a C[sup 5+] liquid product that is lower in benzene and total aromatics than attainable by catalytic reforming of these feeds. Although no further work is planned with this catalyst, a naphtha-upgrading process based on shape-selective zeolitic hydrocracking could provide an attractive alternative to catalytic reforming or isomerization for these hard to upgrade naphthas. It should be particularly attractive in areas where the by-product propane and butane have good value.

Heck, R.H.; Chen, Nai Y. (Mobil Research and Development Corp., Princeton, NJ (United States). Central Research Laboratory)

1993-06-01T23:59:59.000Z

8

Advances in the chemistry of catalytic reforming of naphtha  

Science Conference Proceedings (OSTI)

Catalytic reforming of naphtha remains the key process for production of high octane gasoline and aromatics (BTX) which are used as petrochemicals feedstocks. The increased demand for these products has led refiners to investigate ways for improving the performance of the reforming process and its catalysts. Moreover, in order to comply with environmental restrictions, the reduction in lead content would require further increase in the reformate octane number. In response to these requirements, refiners and catalyst manufacturers are examining the role of the catalysts in improving the selectivity to aromatics and in octane enhancement. By understanding the chemistry and the mechanism of the reforming process, higher performance catalysts with longer life on stream and lower cost can be developed. This review covers recent developments in reforming catalysts, process reaction chemistry and mechanism. It also highlights prospective areas of research.

Anabtawi, J.A.; Redwan, D.S.; Al-Jarallah, A.M.; Aitani, A.M. (Petroleum and Gas Technology Div., Research Inst., King Fahd Univ. of Petroleum and Minerals, Dhahran (SA))

1991-01-01T23:59:59.000Z

9

Rate enhancement for catalytic upgrading coal naphthas. Final of final technical progress report, July 1991--September 1994  

Science Conference Proceedings (OSTI)

The objective of this project is to remove sulfur, nitrogen, and oxygen from naphtha derived from coal liquefaction. The project is concerned with the development of hydrotreating catalysts. This period, a ruthenium sulfide catalyst has been studied.

Davis, B.H.

1995-08-01T23:59:59.000Z

10

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...

11

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.

12

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

13

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

14

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

15

A NOVEL VAPOR-PHASE PROCESS FOR DEEP DESULFURIZATION OF NAPHTHA/DIESEL  

Science Conference Proceedings (OSTI)

Tier 2 regulations issued by the U.S. Environmental Protection Agency (EPA) require a substantial reduction in the sulfur content of gasoline. Similar regulations have been enacted for the sulfur level in on-road diesel and recently off-road diesel. The removal of this sulfur with existing and installed technology faces technical and economic challenges. These challenges created the opportunity for new emerging technologies. Research Triangle Institute (RTI) with subcontract support from Kellogg Brown & Root, Inc., (KBR) used this opportunity to develop RTI's transport reactor naphtha desulfurization (TReND) process. Starting with a simple conceptual process design and some laboratory results that showed promise, RTI initiated an accelerated research program for sorbent development, process development, and marketing and commercialization. Sorbent development has resulted in the identification of an active and attrition resistant sorbent that has been prepared in commercial equipment in 100 lb batches. Process development has demonstrated both the sulfur removal performance and regeneration potential of this sorbent. Process development has scaled up testing from small laboratory to pilot plant transport reactor testing. Testing in the transport reactor pilot plant has demonstrated the attrition resistance, selective sulfur removal activity, and regeneration activity of this sorbent material. Marketing and commercialization activities have shown with the existing information that the process has significant capital and operating cost benefits over existing and other emerging technologies. The market assessment and analysis provided valuable feedback about the testing and performance requirements for the technical development program. This market analysis also provided a list of potential candidates for hosting a demonstration unit. Although the narrow window of opportunity generated by the new sulfur regulations and the conservative nature of the refining industry slowed progress of the demonstration unit, negotiations with potential partners are proceeding for commercialization of this process.

B.S. Turk; R.P. Gupta; S.K. Gangwal

2003-06-30T23:59:59.000Z

16

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

17

The Role of the Flexicoking Process in Heavy Oil Processing  

E-Print Network (OSTI)

The recently commercialized FLEXICOKING Process has a significant role to play in developing, known heavy oil reserves. The process upgrades virtually any pumpable feed including residual, pitch or total crude. Combined with HYDROFINING, it produces a clean product slate composed of low Btu gas, high Btu gas, LPG, naphtha, distillate and gas oil. The low Btu gas falls within the definition of an "Alternate Fuel" under current legislation (PL 95-620). Originally developed for refinery bottoms conversion, the FLEXICOKING process can also be used as the primary technology for Stand Alone Energy Centers upgrading low quality, high metals, heavy crudes. These efficient energy centers can be located either at a heavy oil production field or integrated with an energy-intensive industrial complex.

Taylor, R. I.

1980-01-01T23:59:59.000Z

18

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...

19

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

20

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

Note: This page contains sample records for the topic "heavy naphtha boiling" 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

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

22

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

23

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

24

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":""}]}

25

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

26

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

27

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

28

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

29

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

30

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

31

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

32

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

33

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

34

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

35

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

36

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

37

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

38

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

39

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

40

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

Note: This page contains sample records for the topic "heavy naphtha boiling" 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

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

42

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

43

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

44

HEAVY WATER MODERATED NEUTRONIC REACTOR  

DOE Patents (OSTI)

A nuclear reactor of the type which utilizes uranium fuel elements and a liquid coolant is described. The fuel elements are in the form of elongated tubes and are disposed within outer tubes extending through a tank containing heavy water, which acts as a moderator. The ends of the fuel tubes are connected by inlet and discharge headers, and liquid bismuth is circulated between the headers and through the fuel tubes for cooling. Helium is circulated through the annular space between the outer tubes in the tank and the fuel tubes to cool the water moderator to prevent boiling. The fuel tubes are covered with a steel lining, and suitable control means, heat exchange means, and pumping means for the coolants are provided to complete the reactor assembly.

Szilard, L.

1958-04-29T23:59:59.000Z

45

Heavy Oil Projects  

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

Select Reports from Heavy Oil Projects Project Number Performer Title Heavy Oil Recovery US (NIPERBDM-0225) BDM-Oklahoma, Inc. Feasibility Study of Heavy Oil Recovery in the...

46

Heavy Oil Upgrading from Electron Beam (E-Beam) Irradiation  

E-Print Network (OSTI)

Society's growing demands for energy results in rapid increase in oil consumption and motivates us to make unconventional resources conventional resources. There are enormous amounts of heavy oil reserves in the world but the lack of cost effective technologies either for extraction, transportation, or refinery upgrading hinders the development of heavy oil reserves. One of the critical problems with heavy oil and bitumen is that they require large amounts of thermal energy and expensive catalysts to upgrade. This thesis demonstrates that electron beam (E-Beam) heavy oil upgrading, which uses unique features of E-Beam irradiation, may be used to improve conventional heavy oil upgrading. E-Beam processing lowers the thermal energy requirements and could sharply reduce the investment in catalysts. The design of the facilities can be simpler and will contribute to lowering the costs of transporting and processing heavy oil and bitumen. E-Beam technology uses the high kinetic energy of fast electrons, which not only transfer their energy but also interact with hydrocarbons to break the heavy molecules with lower thermal energy. In this work, we conducted three major stages to evaluate the applicability of E-Beam for heavy oil upgrading. First, we conducted laboratory experiments to investigate the effects of E-Beam on hydrocarbons. To do so, we used a Van de Graff accelerator, which generates the high kinetic energy of electrons, and a laboratory scale apparatus to investigate extensively how radiation effects hydrocarbons. Second, we studied the energy transfer mechanism of E-Beam upgrading to optimize the process. Third, we conducted a preliminary economic analysis based on energy consumption and compared the economics of E-Beam upgrading with conventional upgrading. The results of our study are very encouraging. From the experiments we found that E-Beam effect on hydrocarbon is significant. We used less thermal energy for distillation of n-hexadecane (n-C16) and naphtha with E-Beam. The results of experiments with asphaltene indicate that E-Beam enhances the decomposition of heavy hydrocarbon molecules and improves the quality of upgraded hydrocarbon. From the study of energy transfer mechanism, we estimated heat loss, fluid movement, and radiation energy distribution during the reaction. The results of our economic evaluation show that E-Beam upgrading appears to be economically feasible in petroleum industry applications. These results indicate significant potential for the application of E-Beam technology throughout the petroleum industry, particularly near production facilities, transportation pipelines, and refining industry.

Yang, Daegil

2009-12-01T23:59:59.000Z

47

Cooling and solidification of heavy hydrocarbon liquid streams  

DOE Patents (OSTI)

A process and apparatus for cooling and solidifying a stream of heavy hydrocarbon material normally boiling above about 850.degree. F., such as vacuum bottoms material from a coal liquefaction process. The hydrocarbon stream is dropped into a liquid bath, preferably water, which contains a screw conveyor device and the stream is rapidly cooled, solidified and broken therein to form discrete elongated particles. The solid extrudates or prills are then dried separately to remove substantially all surface moisture, and passed to further usage.

Antieri, Salvatore J. (Trenton, NJ); Comolli, Alfred G. (Yardley, PA)

1983-01-01T23:59:59.000Z

48

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

49

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

50

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

51

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

52

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

53

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

54

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

55

Catalytic two-stage coal hydrogenation process using extinction recycle of heavy liquid fraction  

DOE Patents (OSTI)

A process is described for catalytic two-stage hydrogenation and liquefaction of coal with selective extinction recycle of all heavy liquid fractions boiling above a distillation cut point of about 600--750 F to produce increased yields of low-boiling hydrocarbon liquid and gas products. In the process, the particulate coal feed is slurried with a process-derived liquid solvent normally boiling above about 650 F and fed into a first stage catalytic reaction zone operated at conditions which promote controlled rate liquefaction of the coal, while simultaneously hydrogenating the hydrocarbon recycle oils. The first stage reactor is maintained at 710--800 F temperature, 1,000--4,000 psig hydrogen partial pressure, and 10-90 lb/hr per ft[sup 3] catalyst space velocity. Partially hydrogenated material withdrawn from the first stage reaction zone is passed directly to the second stage catalytic reaction zone maintained at 760--860 F temperature for further hydrogenation and hydroconversion reactions. A 600--750 F[sup +] fraction containing 0--20 W % unreacted coal and ash solids is recycled to the coal slurrying step. If desired, the cut point lower boiling fraction can be further catalytically hydrotreated. By this process, the coal feed is successively catalytically hydrogenated and hydroconverted at selected conditions, to provide significantly increased yields of desirable low-boiling hydrocarbon liquid products and minimal production of hydrocarbon gases, and no net production of undesirable heavy oils and residuum materials. 2 figs.

MacArthur, J.B.; Comolli, A.G.; McLean, J.B.

1989-10-17T23:59:59.000Z

56

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

57

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

58

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

59

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

60

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.

Note: This page contains sample records for the topic "heavy naphtha boiling" 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

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

62

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

63

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

64

Product Supplied for Special Naphthas  

U.S. Energy Information Administration (EIA)

-No Data Reported; --= Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Notes: Data may not add to ...

65

Special Naphthas Imports from Turkey  

U.S. Energy Information Administration (EIA)

... Iran, Iraq, Kuwait, Qatar, Saudi Arabia, and United Arab Emirates. Totals may not equal sum of components due to independent rounding.

66

Special Naphthas Imports from Peru  

U.S. Energy Information Administration (EIA)

-No Data Reported; --= Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Notes: *Countries listed under ...

67

Special Naphthas Imports from Ecuador  

U.S. Energy Information Administration (EIA)

-No Data Reported; --= Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Notes: *Countries listed under ...

68

Special Naphthas Imports from Chile  

U.S. Energy Information Administration (EIA)

-No Data Reported; --= Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Notes: *Countries listed under ...

69

Special Naphthas Imports from Angola  

U.S. Energy Information Administration (EIA)

-No Data Reported; --= Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Notes: *Countries listed under ...

70

Special Naphthas Imports from Netherlands  

U.S. Energy Information Administration (EIA)

-No Data Reported; --= Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Notes: *Countries listed under ...

71

Special Naphthas Imports from Colombia  

U.S. Energy Information Administration (EIA)

PAD District Imports by Country of Origin ... Crude oil includes imports for storage in the Stategic Petroleum Reserve. The Persian Gulf includes Bahrain, ...

72

Special Naphthas Imports from Mexico  

U.S. Energy Information Administration (EIA)

-No Data Reported; --= Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Notes: *Countries listed under ...

73

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.

74

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

75

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

76

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

77

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

78

HEAVY-ION RADIOGRAPHY AND HEAVY-ION COMPUTED TOMOGRAPHY  

E-Print Network (OSTI)

In: Biological and Medical Research with Accelerated Heavyeds. Biological and Medical Research with Accelerated HeavyIn: Biological and Medical Research with Accelerated Heavy

Fabrikant, J.I.

2010-01-01T23:59:59.000Z

79

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

80

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 "heavy naphtha boiling" 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

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

82

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":""}]}

83

Block Heavy Hitters  

E-Print Network (OSTI)

e study a natural generalization of the heavy hitters problem in thestreaming context. We term this generalization *block heavy hitters* and define it as follows. We are to stream over a matrix$A$, and report all *rows* ...

Andoni, Alexandr

2008-05-02T23:59:59.000Z

84

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

85

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

86

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

87

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

88

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

89

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

90

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

91

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

92

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

93

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

94

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

95

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

96

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

97

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

98

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

99

HEAVY-WATER-MODERATED POWER REACTORS ENGINEERING AND ECONOMIC EVALUATIONS. VOLUME I. SUMMARY REPORT  

SciTech Connect

Capital investments and the cost of power were estimated for 21 heavy- water-moderated, natural-uraniumfueled power-reactor plants, ranging in capacity from 100 to 460 Mw(e). Comparisons were made of hot- and coldmoderator reactors and of the relative merits of pressuretube and pressure-vessel designs. Reactors cooled with liquid D/sub 2/O, boiling D/sub 2/O, /sub 2/O steam, and helium were evalunted. A cold-moderator pressure-tube reactor cooled with boiling D/sub 2/O shows the most economic promise of the D/sub 2/Omoderated reactor systems studied to date. Reactors of this type have sufficient reactivity to permit satisfactory fuel exposures, but the development of additional technology is a prerequisite for optimum designs. At capacities of 300 and 400 Mw(e), the estimated power costs from the current designs of boiling-D/sub 2/O pressure-tabe reactor plants are 11.3 and 9.8 mills/kwh, respectively. From liquid-D/sub 2/-cooled concepts of comparable capacities the indicated power costs are 7 to 20% higher. With an active development program, a power cost of 8.0 to 8.5 mills/kwh may be attained in a 300 Mw(e) boiling-D/sub 2/O reactor plant within the next decade. (auth)

1960-06-01T23:59:59.000Z

100

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

Note: This page contains sample records for the topic "heavy naphtha boiling" 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

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

102

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

103

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

104

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

105

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

106

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

107

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

108

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

109

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

110

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

111

HEAVY ION INERTIAL FUSION  

E-Print Network (OSTI)

Accelerators as Drivers for Inertially Confined Fusion, W.B.LBL-9332/SLAC-22l (1979) Fusion Driven by Heavy Ion Beams,OF CALIFORNIA f Accelerator & Fusion Research Division

Keefe, D.

2008-01-01T23:59:59.000Z

112

Relativistic Heavy Ion Collider  

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

at the same time. Capable of accelerating 70 trillion protons with every pulse, and heavy ions such as gold and iron, the AGS receives protons and other ions from the AGS...

113

Process for removing heavy metal compounds from heavy crude oil  

DOE Patents (OSTI)

A process is provided for removing heavy metal compounds from heavy crude oil by mixing the heavy crude oil with tar sand; preheating the mixture to a temperature of about 650.degree. F.; heating said mixture to up to 800.degree. F.; and separating tar sand from the light oils formed during said heating. The heavy metals removed from the heavy oils can be recovered from the spent sand for other uses.

Cha, Chang Y. (Golden, CO); Boysen, John E. (Laramie, WY); Branthaver, Jan F. (Laramie, WY)

1991-01-01T23:59:59.000Z

114

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

115

HEAVY WATER MODERATED POWER REACTORS PROGRESS REPORT, SEPTEMBER 1961  

DOE Green Energy (OSTI)

At the end of September l961, construction of the Heavy Water Components Test Reactor was about 90% complete. Thirty-two compacted tubes of crushed, fused uranium oxide in Zircaloy sheaths were fabricated for irradiation tests and destructive evaluation. lrradiation tests of the tubes were started in the Vallecitos Boiling Water Reactor and at Savannah River. The fabrication process for the tubes included steps designed to exclude hydrogenous material from the oxide cores, thereby eliminating the probable cause of sheath failures in previous irradiations. Additional experimental data on heat transfer burnout of tubes in subcooled water at pressures of about 100 to 1000 psi showed that the burnout heat flux is not affected significantiy by pressure in this range. The data were correlated in terms of water velocity and subcooling. (auth)

Hood, R.R. comp.

1961-11-01T23:59:59.000Z

116

Super Heavy Element Discovery | ornl.gov  

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

Super Heavy Element Discovery SHARE Super Heavy Element Discovery The location of the Transactinides (super-heavy elements) shown on the Periodic Table. ORNL is internationally...

117

Solenoid transport for heavy ion fusion  

E-Print Network (OSTI)

Transport for Heavy Ion Fusion* Edward Lee** LawrenceHm Heavy Ion Inertial Fusion Abstract Solenoid transport ofseveral stages of a heavy ion fusion driver. In general this

Lee, Edward

2004-01-01T23:59:59.000Z

118

Identifying heavy Higgs bosons  

SciTech Connect

Two techniques for identifying heavy Higgs bosons produced at SSC energies are discussed. In the first, the Higgs boson decays into ZZ, with one Z decaying into an e-pair or ..mu..-pair and the other into a neutrino pair. In the second, the production of the Higgs boson by WW fusion is tagged by detecting the quarks that produced the bremsstrahlung virtual W's. The associated Higgs decay is identified by one leptonic and one hadronic decay. Both methods appear capable of finding a heavy Higgs boson provided the SSC design parameters are achieved. 16 refs., 2 figs., 2 tabs.

Cahn, R.N.

1986-06-01T23:59:59.000Z

119

Heavy ion fusion--Using heavy ions to make electricity  

E-Print Network (OSTI)

in Proc. of the Inertial Fusion Science and ApplicationsP. Abbott, P. F. Peterson, Fusion Science and Technology 44March 15–20, 2004 Heavy Ion Fusion– Using Heavy Ions to Make

Celata, C.M.

2004-01-01T23:59:59.000Z

120

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

Note: This page contains sample records for the topic "heavy naphtha boiling" 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

Exploiting heavy oil reserves  

E-Print Network (OSTI)

the behaviour of oil and gas prices and the fruits of future exploration. The rate of technological progress. How optimistic are you that the North Sea remains a viable source of oil and gas? A) Our new researchNorth Sea investment potential Exploiting heavy oil reserves Beneath the waves in 3D Aberdeen

Levi, Ran

122

Heavy Vehicle Systems  

Science Conference Proceedings (OSTI)

Heavy Vehicle (HV) systems are a necessary component of achieving OHVT goals. Elements are in place for a far-ranging program: short, intermediate, and long-term. Solicitation will bring industrial input and support. Future funding trend is positive, outlook for HV systems is good.

Sid Diamond; Richard Wares; Jules Routbort

2000-04-11T23:59:59.000Z

123

DEVELOPMENTS IN HEAVY QUARKONIUM SPECTROSCOPY  

E-Print Network (OSTI)

­ 1­ DEVELOPMENTS IN HEAVY QUARKONIUM SPECTROSCOPY Written May 2012 by S. Eidelman (Budker Inst. Navas (Univ. Granada), and C. Patrignani (Univ. Genova, INFN). A golden age for heavy quarkonium physics at HERA and the Tevatron matured; and heavy-ion collisions at RHIC opened a window on the deconfinement

124

Gulf Coast (PADD 3) Special Naphthas Imports  

U.S. Energy Information Administration (EIA)

Import Area: Download Series History: Definitions ... 51: 81: 136: 1995-2012: Netherlands Antilles : 1995-2004: Philippines : 14 : 2010-2010: Portugal: 6: 12

125

Catalytic Hydrotreating Naphtha/Reformer Feed Downstream ...  

U.S. Energy Information Administration (EIA)

-No Data Reported; --= Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Notes: Idle refineries ...

126

Naphtha for Petrochemical Feedstock Use Exports  

U.S. Energy Information Administration (EIA)

-No Data Reported; --= Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Notes: Crude oil exports are ...

127

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

128

HEAVY-WATER-MODERATED POWER REACTORS ENGINEERING AND ECONOMIC EVALUATIONS. VOLUME II. ENGINEERING STUDIES AND TECHNICAL DATA  

SciTech Connect

The results of preliminary design and evaluation studies of various concepts of a power reactor that is moderated by heavy water and fueled with natural uranium are presented. Twenty-nine conceptal designs were developed for reactors ranging in capacity from 100 Mwe to 460 Mwe. Resigns were prepared for hot- and cold-moderator reac tors of the pressure vessel type, with liquid D/sub 2/O, boiling D/sub 2/O, E/sub 2/O steam, and helium as coolants. Also studied were cold-moderator pressure tube reactors cooled with liquid D/sub 2/O and boiling D/sub 2/O. The repont includes the results of engineering studies of the reactor systems, electrical generation facilities, and auxiliary equipment. (auth)

1960-12-01T23:59:59.000Z

129

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

130

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

131

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

132

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

133

Method of producing a colloidal fuel from coal and a heavy petroleum fraction  

DOE Patents (OSTI)

A method is provided for combining coal as a colloidal suspension within a heavy petroleum fraction. The coal is broken to a medium particle size and is formed into a slurry with a heavy petroleum fraction such as a decanted oil having a boiling point of about 300.degree.-550.degree. C. The slurry is heated to a temperature of 400.degree.-500.degree. C. for a limited time of only about 1-5 minutes before cooling to a temperature of less than 300.degree. C. During this limited contact time at elevated temperature the slurry can be contacted with hydrogen gas to promote conversion. The liquid phase containing dispersed coal solids is filtered from the residual solids and recovered for use as a fuel or feed stock for other processes. The residual solids containing some carbonaceous material are further processed to provide hydrogen gas and heat for use as required in this process.

Longanbach, James R. (Columbus, OH)

1983-08-09T23:59:59.000Z

134

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

135

Method for production of hydrocarbon diluent from heavy crude oil  

Science Conference Proceedings (OSTI)

This patent describes a method of producing a hydrocarbon diluent from a heavy crude oil extracted from an underground petroleum formation via a production well. It comprises: preheating a quantity of heavy crude oil extracted from the production well to yield a heated crude oil; separating in a separator vessel by flashing the heated crude oil to produce a first vapor fraction and a first liquid fraction; thermally cracking in a cracking unit at least a portion of the first liquid fraction to produce a first liquid effluent; quenching the first liquid effluent; introducing at least a portion of the quenched fist liquid effluent into a separator; condensing the first vapor fraction; separating in a separator vessel the condensed vapor fraction to produce a liquid hydrocarbon diluent middle fraction characterized in having a boiling range between about 400{degrees}-700{degrees}F. and a gas; and, directing the liquid hydrocarbon diluent into the formation via an injection well for enhancing production of petroleum from the formation via the production well.

McCants, M.F.

1992-05-05T23:59:59.000Z

136

Relativistic Heavy Ion Collider  

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

Relativistic Heavy Ion Collider Relativistic Heavy Ion Collider managed for the U.S. Department of Energy by Brookhaven Science Associates, founded by Stony Brook University and Battelle. managed for the U.S. Department of Energy by Brookhaven Science Associates, a company founded by Stony Brook University and Battelle 07/07 Brookhaven National Laboratory Funded by the U.S. Department of Energy, Brookhaven National Laboratory is a multipurpose research institution located on a 5,300-acre site on Long Island, New York. Six Nobel Prize-winning discoveries have been made at Brookhaven Lab. The Laboratory operates large-scale scientific facilities and performs research in physics, chemistry, biology, medicine, applied science, and

137

Characterizing Heavy Ion  

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

Heavy Ion Heavy Ion Reactions in the 1980's Is there Treasure at the end of the Rainbow? & What happens and how do different modes compete? John Schiffer One of the three research areas for ATLAS, as stated in a 1984 document to Congress: Are there some new marvelous symmetries, hidden in resonances in heavier nuclei, beyond 12 C+ 12 C and its immediate vicinity? (s.c. linac work, pre-ATLAS) Other attempts to chase the rainbow 180 o elastic scattering of 12 C on 40 Ca shows structure Fusion of 16 O on 40 Ca does not. In the end, it seemed that these structures were sometimes present in alpha-particle nuclei, but almost never in others. Some optimists, continued the pursuit. We also looked at the total fusion cross section in systems that showed resonances in scattering.

138

Computing Heavy Elements  

E-Print Network (OSTI)

Reliable calculations of the structure of heavy elements are crucial to address fundamental science questions such as the origin of the elements in the universe. Applications relevant for energy production, medicine, or national security also rely on theoretical predictions of basic properties of atomic nuclei. Heavy elements are best described within the nuclear density functional theory (DFT) and its various extensions. While relatively mature, DFT has never been implemented in its full power, as it relies on a very large number (~ 10^9-10^12) of expensive calculations (~ day). The advent of leadership-class computers, as well as dedicated large-scale collaborative efforts such as the SciDAC 2 UNEDF project, have dramatically changed the field. This article gives an overview of the various computational challenges related to the nuclear DFT, as well as some of the recent achievements.

Schunck, N; Kortelainen, M; McDonnell, J; Moré, J; Nazarewicz, W; Pei, J; Sarich, J; Sheikh, J; Staszczak, A; Stoitsov, M; Wild, S M

2011-01-01T23:59:59.000Z

139

Computing Heavy Elements  

E-Print Network (OSTI)

Reliable calculations of the structure of heavy elements are crucial to address fundamental science questions such as the origin of the elements in the universe. Applications relevant for energy production, medicine, or national security also rely on theoretical predictions of basic properties of atomic nuclei. Heavy elements are best described within the nuclear density functional theory (DFT) and its various extensions. While relatively mature, DFT has never been implemented in its full power, as it relies on a very large number (~ 10^9-10^12) of expensive calculations (~ day). The advent of leadership-class computers, as well as dedicated large-scale collaborative efforts such as the SciDAC 2 UNEDF project, have dramatically changed the field. This article gives an overview of the various computational challenges related to the nuclear DFT, as well as some of the recent achievements.

N. Schunck; A. Baran; M. Kortelainen; J. McDonnell; J. Moré; W. Nazarewicz; J. Pei; J. Sarich; J. Sheikh; A. Staszczak; M. Stoitsov; S. M. Wild

2011-07-25T23:59:59.000Z

140

Heavy Vehicle Propulsion Materials  

DOE Green Energy (OSTI)

The objectives are to Provide Key Enabling Materials Technologies to Increase Energy Efficiency and Reduce Exhaust Emissions. The following goals are listed: Goal 1: By 3rd quarter 2002, complete development of materials enabling the maintenance or improvement of fuel efficiency {ge} 45% of class 7-8 truck engines while meeting the EPA/Justice Department ''Consent Decree'' for emissions reduction. Goal 2: By 4th quarter 2004, complete development of enabling materials for light-duty (class 1-2) diesel truck engines with efficiency over 40%, over a wide range of loads and speeds, while meeting EPA Tier 2 emission regulations. Goal 3: By 4th quarter 2006, complete development of materials solutions to enable heavy-duty diesel engine efficiency of 50% while meeting the emission reduction goals identified in the EPA proposed rule for heavy-duty highway engines.''

Ray Johnson

2000-01-31T23:59:59.000Z

Note: This page contains sample records for the topic "heavy naphtha boiling" 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

Heavy Ions - Cyclotron  

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

Heavy Ions Heavy Ions Heavy ions used at the BASE Facility are accelerated in the form of "cocktails," named because of the fact that several heavy ions with the same mass-to-charge ratio are sent into the Cyclotron, which accelerates the ions while acting as a precision mass separator. The Control Room Operator then uses Cyclotron frequency to select only the desired ion, a process that takes about 2 minutes. We provide four standard cocktails: 4.5, 10, 16, and 30 MeV/nucleon. Depending on the cocktail, LETs from 1 to 100 MeV/(mg/cm^2) and flux levels of up to 1E7 ions/cm2-sec are available. Parts are tested in our vacuum chamber, and can be remotely positioned horizontally, vertically, or rotationally (y and z axes) with the motion table. An alignment laser is available to ensure the part is in the center of the beam. Mounting hardware is readily available. 12xBNC (F-F), 2x25-pin D (F-M or M-F), 4x40-pin flat ribbon (M-M), 4x50-pin flat ribbon (M-M), 12xSMA (F-F), and 2xEthernet vacuum feedthroughs are mounted upon request. (The 4x40-pin and 4x50-pin flat ribbon connectors are wired straight across, so you will need a F-F adapter to correct the pin numbers to normal.) Holes are provided through the cave shielding blocks for connecting additional test equipment, with a distance of approximately 10 feet from vacuum feedthrough to the top of the shielding block.

142

Utah Heavy Oil Program  

Science Conference Proceedings (OSTI)

The Utah Heavy Oil Program (UHOP) was established in June 2006 to provide multidisciplinary research support to federal and state constituents for addressing the wide-ranging issues surrounding the creation of an industry for unconventional oil production in the United States. Additionally, UHOP was to serve as an on-going source of unbiased information to the nation surrounding technical, economic, legal and environmental aspects of developing heavy oil, oil sands, and oil shale resources. UHOP fulGilled its role by completing three tasks. First, in response to the Energy Policy Act of 2005 Section 369(p), UHOP published an update report to the 1987 technical and economic assessment of domestic heavy oil resources that was prepared by the Interstate Oil and Gas Compact Commission. The UHOP report, entitled 'A Technical, Economic, and Legal Assessment of North American Heavy Oil, Oil Sands, and Oil Shale Resources' was published in electronic and hard copy form in October 2007. Second, UHOP developed of a comprehensive, publicly accessible online repository of unconventional oil resources in North America based on the DSpace software platform. An interactive map was also developed as a source of geospatial information and as a means to interact with the repository from a geospatial setting. All documents uploaded to the repository are fully searchable by author, title, and keywords. Third, UHOP sponsored Give research projects related to unconventional fuels development. Two projects looked at issues associated with oil shale production, including oil shale pyrolysis kinetics, resource heterogeneity, and reservoir simulation. One project evaluated in situ production from Utah oil sands. Another project focused on water availability and produced water treatments. The last project considered commercial oil shale leasing from a policy, environmental, and economic perspective.

J. Bauman; S. Burian; M. Deo; E. Eddings; R. Gani; R. Goel; C.K. Huang; M. Hogue; R. Keiter; L. Li; J. Ruple; T. Ring; P. Rose; M. Skliar; P.J. Smith; J.P. Spinti; P. Tiwari; J. Wilkey; K. Uchitel

2009-10-20T23:59:59.000Z

143

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

144

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.

145

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.

146

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

147

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

148

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

149

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

150

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

151

Heavy Truck Engine Program  

DOE Green Energy (OSTI)

The Heavy Duty Truck Engine Program at Cummins embodied three significant development phases. All phases of work strove to demonstrate a high level of diesel engine efficiency in the face of increasingly stringent emission requirements. Concurrently, aftertreatment system development and refinement was pursued in support of these efficiency demonstrations. The program's first phase focused on the demonstration in-vehicle of a high level of heavy duty diesel engine efficiency (45% Brake Thermal Efficiency) at a typical cruise condition while achieving composite emissions results which met the 2004 U.S. EPA legislated standards. With a combination of engine combustion calibration tuning and the development and application of Urea-based SCR and particulate aftertreatment, these demonstrations were successfully performed by Q4 of 2002. The second phase of the program directed efforts towards an in-vehicle demonstration of an engine system capable of meeting 2007 U.S. EPA legislated emissions requirements while achieving 45% Brake Thermal Efficiency at cruise conditions. Through further combustion optimization, the refinement of Cummins Cooled EGR architecture, the application of a high pressure common rail fuel system and the incorporation of optimized engine parasitics, Cummins Inc. successfully demonstrated these deliverables in Q2 of 2004. The program's final phase set a stretch goal of demonstrating 50% Brake Thermal Efficiency from a heavy duty diesel engine system capable of meeting 2010 U.S. EPA legislated emissions requirements. Cummins chose to pursue this goal through further combustion development and refinement of the Cooled EGR system architecture and also applied a Rankine cycle Waste Heat Recovery technique to convert otherwise wasted thermal energy to useful power. The engine and heat recovery system was demonstrated to achieve 50% Brake Thermal Efficiency while operating at a torque peak condition in second quarter, 2006. The 50% efficient engine system was capable of meeting 2010 emissions requirements through the application of NOx and particulate matter reduction techniques proven earlier in the program.

Nelson, Christopher

2009-01-08T23:59:59.000Z

152

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

153

Technology Analysis - Heavy Vehicle Technologies  

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

the GPRA benefits estimates for EERE's Vehicle Technologies Program's heavy vehicle technology research activities. Argonne researchers develop the benefits analysis using four...

154

DEDICATED HEAVY ION MEDICAL ACCELERATORS  

E-Print Network (OSTI)

et al. , ,8iolog·ical and Medical Research with Acceleratedet al. , "Biological and Medical Research with J\\cceleratedic Heavy Ions in Medical and Scientific Research, Edmonton,

Gough, R.A.

2013-01-01T23:59:59.000Z

155

Heavy Ion Fusion development plan  

SciTech Connect

Some general cnsiderations in the fusion development program are given. The various factors are considered that must be determined before heavy ion fusion can be assessed. (MOW)

Maschke, A.W.

1978-01-01T23:59:59.000Z

156

Very high energy heavy-ion accelerators  

SciTech Connect

A review is given of various programs for building heavy ion accelerators. Topics discussed are (1) options of reaching very high energies with heavy ions; (2) present performance of the superHILAC and the Bevalac; (3) heavy ion sources; (4) applications of heavy ion accelerators outside of basic research; and (5) reliability and operating costs of heavy ion sources. (PMA)

Grunder, H.A.

1975-10-01T23:59:59.000Z

157

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

158

Heavy Machine Shop | Central Fabrication Services | Brookhaven...  

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

Heavy Machine Shop Heavy Machine Shop The Heavy Machine Shop facility is located in building 479, and may be accessed by the main door on the north face or front of the building....

159

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

160

Heavy crude oil recovery  

SciTech Connect

The oil crisis of the past decade has focused most of the attention and effort of researchers on crude oil resources, which are accepted as unrecoverable using known technology. World reserves are estimated to be 600-1000 billion metric tons, and with present technology 160 billion tons of this total can be recovered. This book is devoted to the discussion of Enhanced Oil Recovery (EOR) techniques, their mechanism and applicability to heavy oil reservoirs. The book also discusses some field results. The use of numerical simulators has become important, in addition to laboratory research, in analysing the applicability of oil recovery processes, and for this reason the last section of the book is devoted to simulators used in EOR research.

Okandan, E.

1984-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "heavy naphtha boiling" 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

HEAVY ION LINEAR ACCELERATOR  

DOE Patents (OSTI)

A linear accelerator of heavy ions is described. The basic contributions of the invention consist of a method and apparatus for obtaining high energy particles of an element with an increased charge-to-mass ratio. The method comprises the steps of ionizing the atoms of an element, accelerating the resultant ions to an energy substantially equal to one Mev per nucleon, stripping orbital electrons from the accelerated ions by passing the ions through a curtain of elemental vapor disposed transversely of the path of the ions to provide a second charge-to-mass ratio, and finally accelerating the resultant stripped ions to a final energy of at least ten Mev per nucleon.

Van Atta, C.M.; Beringer, R.; Smith, L.

1959-01-01T23:59:59.000Z

162

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

163

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

164

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

165

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

166

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

167

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

168

SYNCHROTRONS FOR HEAVY IONS - BEVALAC EXPERIENCE  

E-Print Network (OSTI)

Heavy Ions ir. Medical and Scientific Research", Edmonton,Heavy Ions in Medical and Scientific Research" Edmonton,vigorous medical and nuclear science research groups. The

Grunder, H.A.

2010-01-01T23:59:59.000Z

169

Glimpse of heavy electrons reveals "hidden order"  

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

Glimpse of heavy electrons reveals "hidden order" Glimpse of heavy electrons reveals "hidden order" The remarkable breakthrough helps validate theory behind the observed increase...

170

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

171

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

172

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

173

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

174

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

175

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

176

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

177

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

178

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

179

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

180

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

Note: This page contains sample records for the topic "heavy naphtha boiling" 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

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

182

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

183

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

184

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

185

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

186

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

187

Heavy ion fusion--Using heavy ions to make electricity  

E-Print Network (OSTI)

for a practical fusion power reactor. HIF is the only fusionenter the reactor chamber, and focus Heavy Ion Fusion ontoengineering test reactor. The promise of fusion as a power

Celata, C.M.

2004-01-01T23:59:59.000Z

188

Heavy Ion Collisions at RHIC  

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

at Heavy Ion Colliders at Heavy Ion Colliders Theory Drivers & View from LHC Urs Achim Wiedemann CERN PH-TH NSAC Implementation Subcommittee Hearings 7 September 2012 Heavy Ion Physics - Main Tools of Theorists Understanding properties of hot and dense matter from the elementary interactions in QCD High Energy Physics String Theory Computational Physics Fluid Dynamics Dissipative fluid dynamic description * Based on: E-p conservation: 2 nd law of thermodynamics: * Sensitive to properties of matter that are calculated from first principles in quantum field theory - EOS: and sound velocity - transport coefficients: shear , bulk viscosity, conductivities ...

189

Development of the Write Process for Pipeline-Ready Heavy Oil  

DOE Green Energy (OSTI)

Work completed under this program advances the goal of demonstrating Western Research Institute's (WRI's) WRITE{trademark} process for upgrading heavy oil at field scale. MEG Energy Corporation (MEG) located in Calgary, Alberta, Canada supported efforts at WRI to develop the WRITE{trademark} process as an oil sands, field-upgrading technology through this Task 51 Jointly Sponsored Research project. The project consisted of 6 tasks: (1) optimization of the distillate recovery unit (DRU), (2) demonstration and design of a continuous coker, (3) conceptual design and cost estimate for a commercial facility, (4) design of a WRITE{trademark} pilot plant, (5) hydrotreating studies, and (6) establish a petroleum analysis laboratory. WRITE{trademark} is a heavy oil and bitumen upgrading process that produces residuum-free, pipeline ready oil from heavy material with undiluted density and viscosity that exceed prevailing pipeline specifications. WRITE{trademark} uses two processing stages to achieve low and high temperature conversion of heavy oil or bitumen. The first stage DRU operates at mild thermal cracking conditions, yielding a light overhead product and a heavy residuum or bottoms material. These bottoms flow to the second stage continuous coker that operates at severe pyrolysis conditions, yielding light pyrolyzate and coke. The combined pyrolyzate and mildly cracked overhead streams form WRITE{trademark}'s synthetic crude oil (SCO) production. The main objectives of this project were to (1) complete testing and analysis at bench scale with the DRU and continuous coker reactors and provide results to MEG for process evaluation and scale-up determinations and (2) complete a technical and economic assessment of WRITE{trademark} technology to determine its viability. The DRU test program was completed and a processing envelope developed. These results were used for process assessment and for scaleup. Tests in the continuous coker were intended to determine the throughput capability of the coker so a scaled design could be developed that maximized feed rate for a given size of reactor. These tests were only partially successful because of equipment problems. A redesigned coker, which addressed the problems, has been build but not operated. A preliminary economic analysis conducted by MEG and an their engineering consultant concluded that the WRITE{trademark} process is a technically feasible method for upgrading bitumen and that it produces SCO that meets pipeline specifications for density. When compared to delayed coking, the industry benchmark for thermal upgrading of bitumen, WRITE{trademark} produced more SCO, less coke, less CO{sub 2} per barrel of bitumen fed, and had lower capital and operating costs. On the other hand, WRITE{trademark}'s lower processing severity yielded crude with higher density and a different product distribution for naphtha, light gas oil and vacuum oil that, taken together, might reduce the value of the SCO. These issues plus the completion of more detailed process evaluation and economics need to be resolved before WRITE{trademark} is deployed as a field-scale pilot.

Lee Brecher; Charles Mones; Frank Guffey

2009-03-07T23:59:59.000Z

190

The physics of heavy flavors  

SciTech Connect

We review the physics of heavy quark flavors, including weak decays, onium, tau leptons, mixing, the Kobayashi-Maskawa matrix, and CP violation in B decay. 36 refs., 12 figs.

Gilman, F.J.

1987-12-01T23:59:59.000Z

191

RHIC | Relativistic Heavy Ion Collider  

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

indicate that collisions of small particles with large gold nuclei at the Relativistic Heavy Ion Collider may be serving up miniscule servings of hot quark-gluon plasma. RHIC...

192

Relativistic Heavy Ion Collider, RHIC  

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

The Relativistic Heavy Ion Collider website has moved to www.bnl.govrhicdefault.asp Sponsored by the U.S. Department of Energy Office of Science, Office of Nuclear Physics. Last...

193

RHIC | Relativistic Heavy Ion Collider  

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

Relativistic Heavy Ion Collider Relativistic Heavy Ion Collider Photo of LINAC The Relativistic Heavy Ion Collider (RHIC) is a world-class particle accelerator at Brookhaven National Laboratory where physicists are exploring the most fundamental forces and properties of matter and the early universe. RHIC accelerates beams of particles (e.g., the nuclei of heavy atoms such as gold) to nearly the speed of light, and smashes them together to recreate a state of matter thought to have existed immediately after the Big Bang some 13.8 billion years ago. STAR and PHENIX, two large detectors located around the 2.4-mile-circumference accelerator, take "snapshots" of these collisions to reveal a glimpse of the basic constituents of visible matter, quarks and gluons. Understanding matter at

194

LCLS Heavy Met Outgassing Tests  

Science Conference Proceedings (OSTI)

A Heavy Met that is 95% tungsten, 3% nickel and 2% iron and sintered to 100% density and is Ultra High Vacuum (UHV) compatible is proposed for use as the X-ray slit in the Front End Enclosure and the Fixed Mask for the Linac Coherent Light Source (LCLS). The Heavy Met was tested in the LLNL Vacuum Sciences and Engineering Lab (VSEL) to determine its outgassing rate and its overall compatibility with the vacuum requirements for LCLS.

Kishiyama, K. I.

2010-12-01T23:59:59.000Z

195

EXPERIMENTAL AND THEORETICAL DETERMINATION OF HEAVY OIL VISCOSITY UNDER RESERVOIR CONDITIONS  

Science Conference Proceedings (OSTI)

The USA deposits of heavy oils and tar sands contain significant energy reserves. Thermal methods, particularly steam drive and steam soak, are used to recover heavy oils and bitumen. Thermal methods rely on several displacement mechanisms to recover oil, but the most important is the reduction of crude viscosity with increasing temperature. The main objective of this research is to propose a simple procedure to predict heavy oil viscosity at reservoir conditions as a function of easily determined physical properties. This procedure will avoid costly experimental testing and reduce uncertainty in designing thermal recovery processes. First, we reviewed critically the existing literature choosing the most promising models for viscosity determination. Then, we modified an existing viscosity correlation, based on the corresponding states principle in order to fit more than two thousand commercial viscosity data. We collected data for compositional and black oil samples (absence of compositional data). The data were screened for inconsistencies resulting from experimental error. A procedure based on the monotonic increase or decrease of key variables was implemented to carry out the screening process. The modified equation was used to calculate the viscosity of several oil samples where compositional data were available. Finally, a simple procedure was proposed to calculate black oil viscosity from common experimental information such as, boiling point, API gravity and molecular weight.

Dr. Jorge Gabitto; Maria Barrufet

2003-05-01T23:59:59.000Z

196

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

197

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

198

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

199

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

200

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

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


201

Chemical and biological effects of heavy distillate recycle in the SRC-II process  

DOE Green Energy (OSTI)

Recent work from the Merriam Laboratory continuous coal liquefaction units shows that heavy distillate from the SRC-II process can be recycled to extinction, and hence a distillate product boiling entirely below 310/sup 0/C (590/sup 0/F) (or other selected boiling points) is feasible. In these runs distillate yield was not reduced; gas make was unaffected; and hydrogen consumption was increased only slightly, in keeping with the generally higher hydrogen content of lighter end products. Total distillate yield (C/sub 5/-590/sup 0/F) was 56 wt %, MAF coal in runs with subbituminous coal from the Amax Belle Ayr mine. Product endpoint is well below 371/sup 0/C (700/sup 0/F), the temperature above which coal distillates appear to become genotoxic; and the product was shown to be free of mutagenic activity in the Ames test. Chemical analyses showed both the < 270/sup 0/C (< 518/sup 0/F) and the < 310/sup 0/C (< 590/sup 0/F) distillates to be essentially devoid of several reference polycyclic compounds known to be carcinogenic in laboratory animals. Tests for tumorigenic or carcinogenic activity were not carried out on these materials. However, a comparison of chemical data from the Merriam heavy distillate samples with data on the other SRC-II distillates where carcinogenesis or tumorigenesis data is available leads to the expectation that < 371/sup 0/C (< 700/sup 0/F) materials from the Merriam Laboratory will have greatly reduced tumorigenic and carcinogenic activity in skin painting tests. Other studies suggest the product should be more readily upgraded than full-range (C/sub 5/-900/sup 0/F) distillate.

Wilson, B.W.; Pelroy, R.A.; Anderson, R.P.; Freel, J.

1983-12-01T23:59:59.000Z

202

RHIC | Relativistic Heavy Ion Collider  

NLE Websites -- All DOE Office Websites

Brookhaven National Laboratory Brookhaven National Laboratory search U.S. Department of Energy logo Home RHIC Science News Images Videos For Scientists Björn Schenke 490th Brookhaven Lecture, 12/18 Join Björn Schenke of Brookhaven Lab's Physics Department for the 490th Brookhaven Lecture, titled 'The Shape and Flow of Heavy Ion Collisions,' on Wednesday, Dec. 18, at 4 p.m. in Berkner Hall. droplets Tiny Drops of Hot Quark Soup-How Small Can They Be? New analyses indicate that collisions of small particles with large gold nuclei at the Relativistic Heavy Ion Collider may be serving up miniscule servings of hot quark-gluon plasma. RHIC Physics RHIC is the first machine in the world capable of colliding ions as heavy as gold. The Spin Puzzle RHIC is the world's only machine capable of colliding beams of polarized

203

CMVRTC: Heavy Truck Duty Cycle  

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

heavy truck duty cycle (HTDC) project heavy truck duty cycle (HTDC) project OVERVIEW The Heavy Truck Duty Cycle (HTDC) Project was initiated in 2004 and is sponsored by the US Department of Energy's (DOE's) Office of FreedomCar and Vehicle Technologies Program. ORNL designed the research program to generate real-world-based duty cycle data from trucks operating in long-haul operations and was designed to be conducted in three phases: identification of parameters to be collected, instrumentation and pilot testing, identification of a real-world fleet, design of the data collection suite and fleet instrumentation, and data collection, analysis, and development of a duty cycle generation tool (DCGT). ANL logo dana logo michelin logo Schrader logo This type of data will be useful for supporting energy efficiency

204

Jet quenching and heavy quarks  

E-Print Network (OSTI)

Jet quenching and more generally physics at high transverse momentum P_T scales is a cornerstone of the heavy-ion physics program at the LHC. In this work, the current understanding of jet quenching in terms of a QCD shower evolution being modified by the surrounding medium is reviewed along with the evidence for this picture from light parton high P_T observables. Conceptually, the same QCD shower description should also be relevant for heavy quarks, but with several important modifications introduced by the quark masses. Thus especially in the limit of small jet energy over quark mass E_jet/m_q, the relevant physics may be rather different from light quark jets, and several attempts to explain the observed phenomenology of heavy quarks at high P_T are discussed here.

Thorsten Renk

2013-09-12T23:59:59.000Z

205

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

206

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

207

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

208

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

209

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

210

Accelerators for heavy ion fusion  

SciTech Connect

Large fusion devices will almost certainly produce net energy. However, a successful commercial fusion energy system must also satisfy important engineering and economic constraints. Inertial confinement fusion power plants driven by multi-stage, heavy-ion accelerators appear capable of meeting these constraints. The reasons behind this promising outlook for heavy-ion fusion are given in this report. This report is based on the transcript of a talk presented at the Symposium on Lasers and Particle Beams for Fusion and Strategic Defense at the University of Rochester on April 17-19, 1985.

Bangerter, R.O.

1985-10-01T23:59:59.000Z

211

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

212

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

213

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

214

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

215

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

216

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

Science Conference Proceedings (OSTI)

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

Vinson, Dennis

2010-06-01T23:59:59.000Z

217

Hadron Production in Heavy Ion Collisions  

E-Print Network (OSTI)

2A GeV 3 Hadron Production from AGS to RHIC 3.1 SystematicsHadron Production in Heavy Ion Collisions Hans Georg RitterAC02- 05CH11231. Hadron Production in Heavy Ion Collisions

Ritter, Hans Georg

2009-01-01T23:59:59.000Z

218

Heavy Vehicle and Engine Resource Guide  

DOE Green Energy (OSTI)

The Heavy Vehicle and Engine Resource Guide is a catalog of medium- and heavy-duty engines and vehicles with alternative fuel and advanced powertrain options. This edition covers model year 2003 engines and vehicles.

Not Available

2004-03-01T23:59:59.000Z

219

Proton Distribution in Heavy Nuclei  

DOE R&D Accomplishments (OSTI)

It is reasoned that, from considerations connected with beta-decay stability and Coulomb repulsion forces, a neutron excess is developed on the surface of heavy nuclei. Several consequences of this qualitative analysis in nucleon interactions are briefly noted. (K.S.)

Johnson, M. H; Teller, E.

1953-11-13T23:59:59.000Z

220

Light-Heavy Price Difference Varies  

U.S. Energy Information Administration (EIA)

Light-Heavy Price Difference Varies ; Function of Crude Market Factors ; Function of Conversion Capacity ; Function of Product Market Factors

Note: This page contains sample records for the topic "heavy naphtha boiling" 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

Summary of the Heavy Flavours Working Group  

E-Print Network (OSTI)

This is a summary of the contributions presented in the Heavy Flavours Working Group of the DIS2006 Workshop.

U. Karshon; I. Schienbein; P. Thompson

2006-08-10T23:59:59.000Z

222

Oklahoma Refinery Catalytic Hydrotreating, Heavy Gas Oil ...  

U.S. Energy Information Administration (EIA)

Cat. Hydro. Heavy Gas Oil Downstream Charge Capacity (B/SD)y ; Oklahoma Downstream Charge Capacity of Operable Petroleum Refineries ...

223

Heavy Vehicle and Engine Resource Guide  

DOE Green Energy (OSTI)

A comprehensive product catalog of medium and heavy-duty engines and vehicles with alternative fuel and advanced powertrain options.

Not Available

2001-10-01T23:59:59.000Z

224

Mississippi Refinery Catalytic Hydrotreating, Heavy Gas Oil ...  

U.S. Energy Information Administration (EIA)

Cat. Hydro. Heavy Gas Oil Downstream Charge Capacity (B/SD)y ; Mississippi Downstream Charge Capacity of Operable Petroleum Refineries ...

225

Heavy Tails: Performance Models and Scheduling Disciplines  

E-Print Network (OSTI)

Heavy Tails: Performance Models and Scheduling Disciplines Sindo N´u~nez-Queija based on joint ITC´u~nez-Queija CWI & TU/e #12;Heavy Tails: Performance Models and Scheduling Disciplines Part I ­ Introduction and Methodology Tales to tell: · traffic measurements and statistical analysis · traffic modeling · heavy

Núñez-Queija, Rudesindo

226

Finding Interesting Correlations with Conditional Heavy Hitters  

E-Print Network (OSTI)

Finding Interesting Correlations with Conditional Heavy Hitters Katsiaryna Mirylenka, Themis Srivastava AT&T Labs, Florham Park, NJ, USA {graham, divesh}@research.att.com Abstract-- The notion of heavy of Conditional Heavy Hitters to identify such items, with applications in network monitoring, and Markov chain

Palpanas, Themis

227

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

228

HEAVY BARYONS: A COMBINED LARGE Nc AND HEAVY QUARK EXPANSION FOR ELECTROWEAK CURRENTS  

E-Print Network (OSTI)

The combined large Nc and heavy quark limit for baryons containing a single heavy quark is discussed. The combined large Nc and heavy quark expansion of the heavy quark bilinear operators is obtained. In the combined expansion the corrections proportional to mN/mQ are summed to all orders. In particular, the combined expansion can be used to determine semileptonic form factors of heavy baryons in the combined limit. 1

Boris A. Gelman

2002-01-01T23:59:59.000Z

229

Bounds on Heavy-to-Heavy Weak Decay Form Factors  

E-Print Network (OSTI)

We provide upper and lower bounds on the semileptonic weak decay form factors for $B \\to D^(*)$ and $\\Lambda_b \\to \\Lambda_c$ decays by utilizing inclusive heavy quark effective theory sum rules. These bounds are calculated to second order in $\\Lambda_{QCD}/m_Q$ and first order in $\\alpha_s$. The $O(\\alpha_s^2 \\beta_0)$ corrections to the bounds at zero recoil are also presented.

Chiang, C W

2001-01-01T23:59:59.000Z

230

Bounds on Heavy-to-Heavy Weak Decay Form Factors  

E-Print Network (OSTI)

We provide upper and lower bounds on the semileptonic weak decay form factors for $B \\to D^(*)$ and $\\Lambda_b \\to \\Lambda_c$ decays by utilizing inclusive heavy quark effective theory sum rules. These bounds are calculated to second order in $\\Lambda_{QCD}/m_Q$ and first order in $\\alpha_s$. The $O(\\alpha_s^2 \\beta_0)$ corrections to the bounds at zero recoil are also presented.

Cheng-Wei Chiang

2000-09-18T23:59:59.000Z

231

Bounds on Heavy-to-Heavy Baryonic Form Factors  

E-Print Network (OSTI)

Upper and lower bounds are established on the Lambda_b -> Lambda_c semileptonic decay form factors by utilizing inclusive heavy-quark-effective-theory sum rules. These bounds are calculated to leading order in Lambda_QCD/m_Q and alpha_s. The O(alpha_s^2 beta_0) corrections to the bounds at zero recoil are also presented. Several form factor models used in the literature are compared with our bounds.

Cheng-Wei Chiang

1999-07-29T23:59:59.000Z

232

Bounds on Heavy-to-Heavy Baryonic Form Factors  

E-Print Network (OSTI)

Upper and lower bounds are established on the Lambda_b -> Lambda_c semileptonic decay form factors by utilizing inclusive heavy-quark-effective-theory sum rules. These bounds are calculated to leading order in Lambda_QCD/m_Q and alpha_s. The O(alpha_s^2 beta_0) corrections to the bounds at zero recoil are also presented. Several form factor models used in the literature are compared with our bounds.

Chiang, C W

2000-01-01T23:59:59.000Z

233

Method of producing a colloidal fuel from coal and a heavy petroleum fraction. [partial liquefaction of coal in slurry, filtration and gasification of residue  

DOE Patents (OSTI)

A method is provided for combining coal as a colloidal suspension within a heavy petroleum fraction. The coal is broken to a medium particle size and is formed into a slurry with a heavy petroleum fraction such as a decanted oil having a boiling point of about 300 to 550/sup 0/C. The slurry is heated to a temperature of 400 to 500/sup 0/C for a limited time of only about 1 to 5 minutes before cooling to a temperature of less than 300/sup 0/C. During this limited contact time at elevated temperature the slurry can be contacted with hydrogen gas to promote conversion. The liquid phase containing dispersed coal solids is filtered from the residual solids and recovered for use as a fuel or feed stock for other processes. The residual solids containing some carbonaceous material are further processed to provide hydrogen gas and heat for use as required in this process.

Longanbach, J.R.

1981-11-13T23:59:59.000Z

234

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

235

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

236

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

237

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

238

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

239

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

240

Heavy flavor production from photons and hadrons  

Science Conference Proceedings (OSTI)

The present state of the production and observation of hadrons containing heavy quarks or antiquarks as valence constituents, in reactions initiated by real and (space-like) virtual photon or by hadron beams is discussed. Heavy flavor production in e/sup +/e/sup -/ annihilation, which is well covered in a number of recent review papers is not discussed, and similarly, neutrino production is omitted due to the different (flavor-changing) mechanisms that are involved in those reactions. Heavy flavors from spacelike photons, heavy flavors from real photons, and heavy flavors from hadron-hadron collisions are discussed. (WHK)

Heusch, C.A.

1982-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "heavy naphtha boiling" 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

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

242

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

243

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

244

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

245

Heavy Vehicle Propulsion Materials Program  

DOE Green Energy (OSTI)

The objective of the Heavy Vehicle Propulsion Materials Program is to develop the enabling materials technology for the clean, high-efficiency diesel truck engines of the future. The development of cleaner, higher-efficiency diesel engines imposes greater mechanical, thermal, and tribological demands on materials of construction. Often the enabling technology for a new engine component is the material from which the part can be made. The Heavy Vehicle Propulsion Materials Program is a partnership between the Department of Energy (DOE), and the diesel engine companies in the United States, materials suppliers, national laboratories, and universities. A comprehensive research and development program has been developed to meet the enabling materials requirements for the diesel engines of the future. Advanced materials, including high-temperature metal alloys, intermetallics, cermets, ceramics, amorphous materials, metal- and ceramic-matrix composites, and coatings, are investigated for critical engine applications.

Sidney Diamond; D. Ray Johnson

1999-04-26T23:59:59.000Z

246

CIVILIAN POWER REACTOR PROGRAM. PART II. ECONOMIC POTENTIAL AND DEVELOPMENT PROGRAM. HEAVY WATER-MODERATED POWER REACTOR  

SciTech Connect

The reactor design which forms the base for the current economic status of D/sub 2/O-moderated reactors was estimated from developments in several reactor programs. However, since a heavy water-moderated reactor was not operated on natural U fuel at power reactor conditions, considerable improvement from this current status can be foreseen. A summary of improvements is presented concerning the concept which would result solely from operation of succeeding generation plants without a parallel development program, and improvements which would result from the successful completion of the development program as presented. One plant size was used in the evaluation of plant potential, with a 300 Mw/sub e/ nominal rating. The boiling D/sub 2/O-cooled, pressure tube direct cycle plant design was used. The current development program is outlined; this work includes several items leading to the long-range development of the concept. (auth)

Hutton, J.H.; Davis, S.A.; Graves, C.C.; Duffy, J.G. comps.

1960-08-19T23:59:59.000Z

247

Heavy-Ion Physics with CMS  

E-Print Network (OSTI)

This article presents a brief overview of the CMS experiment capabilities to study the hot and dense matter created in relativistic heavy-ion collisions. The CERN Large Hadron Collider will provide collisions of Pb nuclei at 5.5 TeV per nucleon. The CMS heavy ion group has developed a plethora of physics analyses addressing many important aspects of heavy-ion physics in preparation for a competitive and successful program.

Aneta Iordanova

2008-06-06T23:59:59.000Z

248

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

249

Heavy ions and string theory  

E-Print Network (OSTI)

We review a selection of recent developments in the application of ideas of string theory to heavy ion physics. Our topics divide naturally into equilibrium and non-equilibrium phenomena. On the non-equilibrium side, we discuss generalizations of Bjorken flow, numerical simulations of black hole formation in asymptotically anti-de Sitter geometries, equilibration in the dual field theory, and hard probes. On the equilibrium side, we summarize improved holographic QCD, extraction of transport coefficients, inclusion of chemical potentials, and approaches to the phase diagram. We close with some possible directions for future research.

Oliver DeWolfe; Steven S. Gubser; Christopher Rosen; Derek Teaney

2013-04-29T23:59:59.000Z

250

Factorization for hadronic heavy quarkonium production  

E-Print Network (OSTI)

We briefly review several models of heavy quarkonium production in hadronic collisions, and discuss the status of QCD factorization for these production models.

Jian-Wei Qiu

2006-10-31T23:59:59.000Z

251

Recent Heavy Flavor Results at RHIC  

E-Print Network (OSTI)

We summarize the recent experimental results of heavy favor physics from the Relativistic Heavy Ion Collider (RHIC) in Brookhaven National Lab (BNL) at Long Island, New York, USA.We will discuss the directly reconstructed open charm mesons as well as electrons from heavy favor hadron decays. The charm and bottom quark production cross-sections have also been measured. We will also discuss JPsi and Upsilon states in p+p and heavy ion collisions. The studies described here were carried out and reported by the STAR and PHENIX collaborations at RHIC.

Wenqin Xu

2011-10-13T23:59:59.000Z

252

Isospin Splittings of Doubly Heavy Baryons  

SciTech Connect

The SELEX Collaboration has reported a very large isospin splitting of doubly charmed baryons. We show that this effect would imply that the doubly charmed baryons are very compact. One intriguing possibility is that such baryons have a linear geometry Q-q-Q where the light quark q oscillates between the two heavy quarks Q, analogous to a linear molecule such as carbon dioxide. However, using conventional arguments, the size of a heavy-light hadron is expected to be around 0.5 fm, much larger than the size needed to explain the observed large isospin splitting. Assuming the distance between two heavy quarks is much smaller than that between the light quark and a heavy one, the doubly heavy baryons are related to the heavy mesons via heavy quark-diquark symmetry. Based on this symmetry, we predict the isospin splittings for doubly heavy baryons including {Xi}{sub cc}, {Xi}{sub bb} and {Xi}{sub bc}. The prediction for the {Xi}{sub cc} is much smaller than the SELEX value. On the other hand, the {Xi}{sub bb} baryons are predicted to have an isospin splitting as large as (6.3 {+-} 1.7) MeV. An experimental study of doubly bottomed baryons is therefore very important to better understand the structure of baryons with heavy quarks.

Brodsky, Stanley J.; /SLAC; Guo, Feng-Kun; /Bonn U., HISKP /Bonn U.; Hanhart, Christoph; /Julich, Forschungszentrum /JCHP, Julich /IAS, Julich; Meissner, Ulf-G.; /Julich, Forschungszentrum /JCHP, Julich /IAS, Julich /Bonn U., HISKP /Bonn U.

2011-08-18T23:59:59.000Z

253

Heavy Duty Truck Engine Advancement Adoption  

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

petroleum consumption. According to the DOE Energy Information Administration's Annual Energy Outlook (AEO) 2009, U.S. heavy truck fuel consumption will increase 23 percent between...

254

Heavy ion physics at the LHC  

E-Print Network (OSTI)

Heavy Ion Physics at the LHC ? R. VogtLaboratory, Berkeley, CA USA Physics Department, Universityfor addressing unique physics issues in a completely new

Vogt, R.

2004-01-01T23:59:59.000Z

255

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

256

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

257

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

258

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

259

Heavy Squarks at the LHC  

E-Print Network (OSTI)

The LHC, with its seven-fold increase in energy over the Tevatron, is capable of probing regions of SUSY parameter space exhibiting qualitatively new collider phenomenology. Here we investigate one such region in which first generation squarks are very heavy compared to the other superpartners. We find that the production of these squarks, which is dominantly associative, only becomes rate-limited at mSquark > 4(5) TeV for L~10(100) fb-1. However, discovery of this scenario is complicated because heavy squarks decay primarily into a jet and boosted gluino, yielding a dijet-like topology with missing energy (MET) pointing along the direction of the second hardest jet. The result is that many signal events are removed by standard jet/MET anti-alignment cuts designed to guard against jet mismeasurement errors. We suggest replacing these anti-alignment cuts with a measurement of jet substructure that can significantly extend the reach of this channel while still removing much of the background. We study a selection of benchmark points in detail, demonstrating that mSquark= 4(5) TeV first generation squarks can be discovered at the LHC with L~10(100)fb-1.

JiJi Fan; David Krohn; Pablo Mosteiro; Arun M. Thalapillil; Lian-Tao Wang

2011-02-01T23:59:59.000Z

260

Heavy Flavour results from Tevatron  

SciTech Connect

The CDF and D0 experiments finalize the analysis of their full statistics collected in the p{bar p} collisions at a center-of-mass energy of {radical}s = 1.96 TeV at the Fermilab Tevatron collider. This paper presents several new results on the properties of hadrons containing heavy b- and c-quarks obtained by both collaborations. These results include the search for the rare decays B{sup 0}, B{sub s}{sup 0} {yields} {mu}{sup +}{mu}{sup -} (CDF), the study of CP asymmetry in B{sub s} {yields} J{psi}{phi} decay (CDF, D0), the measurement of the like-sign dimuon charge asymmetry (D0), the measurement of CP asymmetry in D{sup 0} {yields} K{sup +}K{sup -} and D{sup 0} {yields} {pi}{sup +}{pi}{sup -} decays (CDF), and the new measurement of the B{sub s} {yields} D{sub s}{sup (*)+} D{sub s}{sup (*)-} branching fraction (CDF). Both experiments still expect to produce more results on the properties of heavy flavours.

Borissov, G.; /Lancaster U.

2012-06-01T23:59:59.000Z

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261

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

262

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

263

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

264

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

265

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

266

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

267

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

268

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

269

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

270

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

271

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

272

Heavy metals hazardous components of Eaf dust  

Science Conference Proceedings (OSTI)

Electric arc furnace (EAF) dust is a waste generated in the EAF during the steel production process. Among different wastes, EAF dust represents one of the most hazardous, since it contains heavy metals such as Zn, Fe, Cr, Cd and Pb. The goal of the ... Keywords: electric arc furnace (EAF), furnace additives, hazard components, heavy metals, scrap composition, x-ray fluorescence spectroscopy

Cristiana-Zizi Rizescu; Zorica Bacinschi; Elena Valentina Stoian; Aurora Poinescu; Dan Nicolae Ungureanu

2011-02-01T23:59:59.000Z

273

Heavy metals in suspended powders from steelmaking  

Science Conference Proceedings (OSTI)

Motivations for controlling heavy metal concentrations in gas streams are diverse. Some of them are dangerous to health or to the environment (e.g. Hg, Cd, As, Pb, Cr), some may cause corrosion (e.g. Zn, Pb), some are harmful in other ways (e.g. Arsenic ... Keywords: anthropogenic sources, emissions, heavy metals, human health, pollution of ecosystem, toxic

Cristiana-Zizi Rizescu; Elena-Valentina Stoian; Aurora-Anca Poinescu; Sofia Teodorescu

2010-07-01T23:59:59.000Z

274

UNITAR boosts cogeneration for heavy crude production  

SciTech Connect

The UNITAR/UNDP Information Center for Heavy Crude and Tar Sands publicized the favorable effect of cogeneration on the economics of generating steam for in situ recovery of heavy oil. Although cogeneration of electricity with the production of steam for heavy crude production is a rapidly growing activity in California, it is still unknown in other countries where heavy crude is produced. The study concentrated on two specific cases: a heavy crude cogeneration plant in Kern County in California and a heavy crude production plant at Wolf Lake in Alberta, Canada. A comparison of the two cases showed that due to the specific conditions in California, cogeneration can reduce, in this specific case, the cost of production of heavy crude by $4.80 per barrel whereas in the case of Wolf Lake, cogeneration would not be economic (electricity prices in relation to natural gas prices are much lower in Canada). One of the purposes of the UNITAR study was to direct attention in other countries producing heavy crude to the advantages of cogeneration.

Not Available

1987-03-01T23:59:59.000Z

275

Heavy Vehicle Technologies Program Retrospective and Outlook  

DOE Green Energy (OSTI)

OHVT Mission is to conduct, in collaboration with our heavy vehicle industry partners and their suppliers, a customer-focused national program to research and develop technologies that will enable trucks and other heavy vehicles to be more energy efficient and able to use alternative fuels while simultaneously reducing emissions.

James J. Eberhardt

1999-04-10T23:59:59.000Z

276

Electron-State Hybridization in Heavy-Fermion Systems  

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

Electron-State Hybridization in Heavy-Fermion Systems Electron-State Hybridization in Heavy-Fermion Systems Print Wednesday, 27 September 2006 00:00 Heavy-fermion systems are...

277

Heavy photon search experiment at JLAB  

SciTech Connect

The Heavy Photon Search (HPS) experiment in Hall-B at Jefferson Lab will search for new heavy vector boson(s), aka "heavy photons", in the mass range of 20 MeV/c{sup 2} to 1000 MeV/c{sup 2} using the scattering of high energy, high intensity electron beams off a high Z target. The proposed measurements will cover the region of parameter space favored by the muon g-2 anomaly, and will explore a significant region of parameter space, not only at large couplings ({alpha}'/{alpha} > 10{sup -7}), but also in the regions of small couplings, down to {alpha}'/{alpha}~10{sup -10}. The excellent vertexing capability of the Si-tracker uniquely enables HPS to cover the small coupling region. Also, HPS will search for heavy photons in an alternative to the e{sup +} e{sup -} decay mode, in the heavy photon's decay to {mu}{sup +}{mu}{sup -}.

Stepanyan, Stepan [JLAB

2013-11-01T23:59:59.000Z

278

Research and Development Opportunities for Heavy Trucks  

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

1] 1] Introduction Heavy-duty long-haul trucks are critical to the movement of the Nation's freight. These vehicles, which currently consume about 10 percent of the Nation's oil, are characterized by high fuel consumption, fast market turnover, and rapid uptake of new technologies. Improving the fuel economy of Class 8 trucks will dramatically impact both fuel and cost savings. This paper describes the importance of heavy trucks to the Nation's economy, and its potential for fuel efficiency gains. Why Focus on Heavy Trucks? Large and Immediate Impact Investments in improving the fuel economy of heavy Class 8 trucks will result in large reduction in petroleum consumption within a short timeframe. While heavy-duty vehicles make up only 4% of the

279

Helicity probabilities for heavy quark fragmentation into heavy-light excited mesons  

E-Print Network (OSTI)

After a brief review on how heavy quark symmetry constraints the helicity fragmentation probabilities for a heavy quark hadronizes into heavy-light hadrons, we present a heavy quark fragmentation model to extract the value for the Falk-Peskin probability $w_{3/2}$ describing the fragmentation of a heavy quark into a heavy-light meson whose light degrees of freedom have angular momentum ${3 \\over 2}$. We point out that this probability depends on the longitudinal momentum fraction $z$ of the meson and on its transverse momentum $p_\\bot$ relative to the jet axis. In this model, the light degrees of freedom prefer to have their angular momentum aligned transverse to, rather than along, the jet axis. Implications for the production of excited heavy mesons, like $D^{**}$ and $B^{**}$, are briefly discussed.

Tzu Chiang Yuan

1995-03-08T23:59:59.000Z

280

Spectroscopy of Very Heavy Elements  

Science Conference Proceedings (OSTI)

Advances in spectroscopic techniques have meant that heavy nuclei in the upper right-hand corner of the nuclear chart have become amenable to detailed study. This detailed spectroscopic data can provide a stringent test for current nuclear structure theories. Experiments to investigate the structure of nuclei in the region of {sup 254}No can yield information concerning moments of inertia, stability against fission with rotation, single-particle properties, excitation energies of two quasi-particle states, and so on. A brief overview of the techniques used and recent results from studies in the region of {sup 254}No are presented, along with a summary of future developments which will allow further advances to be made.

Greenlees, P. T.; Herzberg, R.-D.; Ketelhut, S.; Eeckhaudt, S.; Jakobsson, U.; Jones, P.; Julin, R.; Juutinen, S.; Leino, M.; Nyman, M.; Peura, P.; Rahkila, P.; Saren, J.; Scholey, C.; Sorri, J.; Uusitalo, J. [Department of Physics, University of Jyvaeskylae, FIN-40014 Jyvaeskylae (Finland); Ackermann, D.; Hessberger, F.-P. [GSI, D-64291 Darmstadt (Germany); Butler, P. A.; Gray-Jones, C. [Department of Physics, University of Liverpool, Oxford Street, Liverpool, L69 7ZE (United Kingdom)] (and others)

2008-05-12T23:59:59.000Z

Note: This page contains sample records for the topic "heavy naphtha boiling" 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

SUPRI heavy oil research program  

SciTech Connect

The 14th Annual Report of the SUPRI Heavy Oil Research Program includes discussion of the following topics: (1) A Study of End Effects in Displacement Experiments; (2) Cat Scan Status Report; (3) Modifying In-situ Combustion with Metallic Additives; (4) Kinetics of Combustion; (5) Study of Residual Oil Saturation for Steam Injection and Fuel Concentration for In-Situ Combustion; (6) Analysis of Transient Foam Flow in 1-D Porous Media with Computed Tomography; (7) Steam-Foam Studies in the Presence of Residual Oil; (8) Microvisualization of Foam Flow in a Porous Medium; (9) Three- Dimensional Laboratory Steam Injection Model; (10) Saturation Evaluation Following Water Flooding; (11) Numerical Simulation of Well-to-Well Tracer Flow Test with Nonunity Mobility Ratio.

Aziz, K.; Ramey, H.J. Jr.; Castanier, L.M.

1991-12-01T23:59:59.000Z

282

Heavy oil/plastic co-processing - subtask 4.1. Topical report, February 1, 1994--February 1, 1995  

DOE Green Energy (OSTI)

Western Research Institute (WRI) is developing a low-temperature thermal decomposition process to alleviate the problems associated with disposal of waste plastics and at the same time generate a product stream in the gasoline boiling range for use in the refining and petrochemical industries. The technology being developed by WRI is significantly different from conventional thermal decomposition processes used to recover distillates from waste plastics. The key to this difference is the application of a decomposition initiator concept that allows operation of the process at temperatures below those used in other thermal decomposition processes. The WRI technology utilizes the decomposition initiator to enhance thermal decomposition of waste plastics in the presence of a low-value heavy oil at temperatures below those normally used for thermal decomposition. Operation of the process at lower temperatures produces higher yields of distillate product and lower yields of gaseous and char products than conventional processes. The activity of the initiator was identified in earlier research studying the thermal decomposition of polymers. This activity was observed to result in a decrease in the temperature required to thermally decompose plastics in the presence of a heavy oil. These early experiments indicated that the initiator was native to the plastics matrix, but the identity and possible mode of action were not determined. This study was undertaken to identify the active initiator in the plastics matrix and define its activity. The experiments performed in this study were conducted in a batch-type reactor. The particular elements of the activity that were addressed included: (1) the kinetics of the reaction, (2) the effects of diluting the plastics with the heavy oil, and (3) the effects of using different types of heavy oil.

NONE

1998-12-31T23:59:59.000Z

283

Electron-State Hybridization in Heavy-Fermion Systems  

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

Electron-State Hybridization in Heavy-Fermion Systems Print Heavy-fermion systems are characterized by electrons with extremely large effective masses. The corresponding...

284

Deformation Prediction of a Heavy Hydro Turbine Blade During ...  

Science Conference Proceedings (OSTI)

Presentation Title, Deformation Prediction of a Heavy Hydro Turbine Blade During ... Abstract Scope, Heavy hydro turbine castings are made of martensitic ...

285

Ferroelectric Plasma Source for Heavy Ion Beam Charge Neutralization  

E-Print Network (OSTI)

Heavy Ion Beam Driven Fusion Reactor Study”, KfK-3480,a possible heavy ion fusion reactor design [1]. The final

2005-01-01T23:59:59.000Z

286

Experimental Research on Recovery of Heavy Metals from EAF ...  

Science Conference Proceedings (OSTI)

To recycle these heavy metals, it is quite important to know the reactivity and metallurgical behavior of these heavy metals contained in EAF stainless steel dust.

287

Assessment of heavy metal contamination of roadside soils in ...  

Science Conference Proceedings (OSTI)

Feb 16, 2008 ... heavy metals was found using factor analysis. Keywords Heavy metals Á Roadside soils Á. Transportation period Á Contamination index Á.

288

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

289

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

290

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

291

Dynamics of neutralizing electrons during the focusing of intense heavy ions beams inside a heavy fusion reactor chamber  

E-Print Network (OSTI)

beams inside a heavy ion fusion reactor chamber * Agustin F.of a Heavy Ion Fusion reactor heavily depends on the maximum

Lifschitz, Agustin F.; Maynard, Gilles; Vay, Jean-Luc; Lenglet, Andrian

2006-01-01T23:59:59.000Z

292

Dynamics of neutralizing electrons during the focusing of intense heavy ions beams inside a heavy fusion reactor chamber  

E-Print Network (OSTI)

beams inside a heavy ion fusion reactor chamber * Agustin F.efficiency of a Heavy Ion Fusion reactor heavily depends on

Lifschitz, Agustin F.; Maynard, Gilles; Vay, Jean-Luc; Lenglet, Andrian

2006-01-01T23:59:59.000Z

293

Naphtha for Petrochem. Feedstock Use Imports from Yemen  

U.S. Energy Information Administration (EIA)

... Iran, Iraq, Kuwait, Qatar, Saudi Arabia, and United Arab Emirates. Totals may not equal sum of components due to independent rounding.

294

Naphtha for Petrochem. Feedstock Use Imports from Azerbaijan  

U.S. Energy Information Administration (EIA)

... Iran, Iraq, Kuwait, Qatar, Saudi Arabia, and United Arab Emirates. Totals may not equal sum of components due to independent rounding.

295

Naphtha for Petrochem. Feedstock Use Imports from Burma  

U.S. Energy Information Administration (EIA)

... Iran, Iraq, Kuwait, Qatar, Saudi Arabia, and United Arab Emirates. Totals may not equal sum of components due to independent rounding.

296

Naphtha for Petrochem. Feedstock Use Imports from Australia  

U.S. Energy Information Administration (EIA)

... Iran, Iraq, Kuwait, Qatar, Saudi Arabia, and United Arab Emirates. Totals may not equal sum of components due to independent rounding.

297

Refinery Yield of Naphtha for Petrochemical Feedstock Use  

U.S. Energy Information Administration (EIA)

-No Data Reported; --= Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Notes: Totals may not equal ...

298

Naphtha for Petrochem. Feedstock Use Imports from Peru  

U.S. Energy Information Administration (EIA)

-No Data Reported; --= Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Notes: *Countries listed under ...

299

Product Supplied for Naphtha for Petrochemical Feedstock Use  

U.S. Energy Information Administration (EIA)

-No Data Reported; --= Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Notes: Data may not add to ...

300

Reforming naphtha with boron-containing large-pore zeolites  

Science Conference Proceedings (OSTI)

This patent describes a catalytic reforming process. It comprises contacting a hydrocarbonaceous feedstream under catalytic reforming conditions with a composition comprising larger-pore borosilicate zeolites having a pore size greater than 6 and less than 8 angstroms containing less that 1000 parts per million aluminum.

Zones, S.I.; Holtermann, D.L.; Rainis, A.

1992-05-19T23:59:59.000Z

Note: This page contains sample records for the topic "heavy naphtha boiling" 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

Prime Supplier Sales Volumes of Naphtha-Type Jet Fuel  

U.S. Energy Information Administration (EIA)

-No Data Reported; --= Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Notes: Values shown for the ...

302

Naphtha for Petrochem. Feedstock Use Imports from Indonesia  

U.S. Energy Information Administration (EIA)

-No Data Reported; --= Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Notes: *Countries listed under ...

303

Naphtha for Petrochem. Feedstock Use Imports from Venezuela  

U.S. Energy Information Administration (EIA)

-No Data Reported; --= Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Notes: *Countries listed under ...

304

Special Naphthas Imports from Venezuela - U.S. Energy Information ...  

U.S. Energy Information Administration (EIA)

-No Data Reported; --= Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Notes: *Countries listed under ...

305

Naphtha for Petrochem. Feedstock Use Imports from Pakistan  

U.S. Energy Information Administration (EIA)

-No Data Reported; --= Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Notes: *Countries listed under ...

306

Naphtha for Petrochemical Feedstock Use Total Stocks Stocks by Type  

U.S. Energy Information Administration (EIA)

Stock Type: Download Series History: Definitions, Sources & Notes: Show Data By: Product: Stock Type: Area: Jan-13 Feb-13 Mar-13 Apr-13 May-13 Jun-13 View History; U ...

307

Unfinished Oils - Naphthas and Lighter Total Stocks Stocks by Type  

U.S. Energy Information Administration (EIA)

-No Data Reported; --= Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Notes: Crude oil stocks in the ...

308

Naphtha for Petrochem. Feedstock Use Imports from Mexico  

U.S. Energy Information Administration (EIA)

-No Data Reported; --= Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Notes: *Countries listed under ...

309

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

310

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

311

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

312

A 3 MEGAJOULE HEAVY ION FUSION DRIVER  

E-Print Network (OSTI)

Research, Office of Inertia! Fusion, Research Division ofA 3 MEGAJOULE HEAVY ION FUSION DRIVER* A. Faltens, E. Hoyer,Research, Office of Inertial Fusion, Research Division of

Faltens, A.

2010-01-01T23:59:59.000Z

313

NUCLEAR STRUCTURE AND HEAVY-ION FUSION  

E-Print Network (OSTI)

Nuclear Structure and Heavy-Ton Fusion* A series of lecturesthe cross section for fusion in the experiments consideredEffects g in III. Subharrier Fusion Cross Sections for Light

Stokstad, R.G.

2010-01-01T23:59:59.000Z

314

Magnetism and superconductivity of heavy fermion matter  

E-Print Network (OSTI)

The interplay of magnetism and unconventional superconductivity (d singlet wave or p triplet wave) in strongly correlated electronic system (SCES) is discussed with recent examples found in heavy fermion compounds. A short presentation is given on the formation of the heavy quasiparticle with the two sources of a local and intersite enhancement for the effective mass. Two cases of the coexistence or repulsion of antiferromagnetism and superconductivity are given with CeIn3 and CeCoIn5. A spectacular example is the emergence of superconductivity in relatively strong itinerant ferromagnets UGe2 and URhGe. The impact of heavy fermion matter among other SCES as organic conductor or high TC oxide is briefly pointed out. Key words: heavy fermion, superconductivity, antiferromagnetism, ferromagnetism

J. Flouquet A; G. Knebel A; D. Braithwaite A; D. Aoki B; J. P. Brison C; F. Hardy A; A. Huxley A; S. Raymond A; B. Salce A; I. Sheikin D

2005-01-01T23:59:59.000Z

315

Hadron Production in Heavy Ion Collisions  

E-Print Network (OSTI)

We review hadron production in heavy ion collisions with emphasis on pion and kaon production at energies below 2 AGeV and on partonic collectivity at RHIC energies.

Helmut Oeschler; Hans Georg Ritter; Nu Xu

2009-08-12T23:59:59.000Z

316

Statistics of Heavy Rainfall Occurrences in Taiwan  

Science Conference Proceedings (OSTI)

The seasonal variations of heavy rainfall days over Taiwan are analyzed using 6-yr (1997–2002) hourly rainfall data from about 360 rainfall stations, including high-spatial-resolution Automatic Rainfall and Meteorological Telemetry System ...

Ching-Sen Chen; Yi-Leng Chen; Che-Ling Liu; Pay-Liam Lin; Wan-Chin Chen

2007-10-01T23:59:59.000Z

317

An Early History of Heavy Water  

E-Print Network (OSTI)

Since 1945 Canada has had a nuclear power industry based on reactor design which uses natural uranium and heavy water. The tortuous and improbable sequence of events which led to this situation is examined. 1 1

Chris Waltham

1998-01-01T23:59:59.000Z

318

Heavy hadrons in quark-gluon plasma  

SciTech Connect

We use the nonperturbative quark-antiquark potential derived within the Field Correlator Method and the screened Coulomb potential to calculate binding energies and melting temperatures of heavy mesons and baryons in the deconfined phase of quark-gluon plasma.

Narodetskii, I. M., E-mail: naro@itep.ru; Simonov, Yu. A.; Veselov, A. I. [Institute of Theoretical and Experimental Physics (Russian Federation)

2011-03-15T23:59:59.000Z

319

The search for a heavy Higgs boson  

SciTech Connect

Theoretical limits on the mass of the Higgs boson from vacuum stability and perturbative unitarity are examined. Search techniques for heavy Higgs bosons, M/sub H/ > 200 GeV, are also reviewed. 8 refs., 5 figs.

Dawson, S.

1989-02-01T23:59:59.000Z

320

Light-Heavy Crude & Product Price Differences  

U.S. Energy Information Administration (EIA)

Similar light-heavy price difference trends are seen in both the crude oil and the product markets. However, there are some short-term product market changes that ...

Note: This page contains sample records for the topic "heavy naphtha boiling" 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

Status of Heavy-lepton Searches  

DOE R&D Accomplishments (OSTI)

Searches for heavy leptons using e{sup +}e{sup -} annihilation, lepton-hadron collisions, photon-hadron collisions, hadron-hadron collisions, and studies of macroscopic matter are reviewed. The present experimental status and future possibilities are summarized.

Perl, M. L.

1981-06-00T23:59:59.000Z

322

Updated Satellite Technique to Forecast Heavy Snow  

Science Conference Proceedings (OSTI)

Certain satellite interpretation techniques have proven quite useful in the heavy snow forecast process. Those considered best are briefly reviewed, and another technique is introduced. This new technique was found to be most valuable in cyclonic ...

Edward C. Johnston

1995-06-01T23:59:59.000Z

323

Current status of nonthermal heavy oil recovery  

Science Conference Proceedings (OSTI)

Heavy oils are an important resource worldwide, and yet two-thirds of the heavy oil deposits cannot be exploited by means of thermal recovery methods, because the effective energy production approaches energy input for reasons of formation thickness, depth, oil saturation and/or porosity. In such instances, especially if the heavy oil is not too viscous (below ca 1000 cp), it may be economical to employ nonthermal recovery methods. These include polymer flooding, alkaline flooding, CO/sub 2/ (gaseous) floods, solvent floods, and other more specialized recovery methods, such as emulsion flooding, and combination techniques. This work discusses nonthermal heavy oil recovery methods, based upon their application in the field. The processes and their mechanistic features are discussed in the light of laboratory observations, which tend to be more optimistic than field results. 48 references.

Alikhan, A.A.; Farouq Ali, S.M.

1983-01-01T23:59:59.000Z

324

Treatment of Heavy Metal Wastes - III - TMS  

Science Conference Proceedings (OSTI)

Ltd., Flin Fion, Manitoba, Canada R8A 1N9. 3:15 pm BREAK. 3:30 pm. An Integrated Bioremediation Route for Heavy Metal Contaminated Land Based on the ...

325

Dispersion of Heavy Particles by Turbulent Motion  

Science Conference Proceedings (OSTI)

Accurate prediction of heavy particle dispersion in turbulent flows requires a simultaneous consideration of particle's inertia and particle's drift velocity. A mathematically simple and physically comprehensive analysis was developed to solve ...

Lian-Ping Wang; Davd E. Stock

1993-07-01T23:59:59.000Z

326

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

327

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

328

Optimal Tracking of Distributed Heavy Hitters and Hong Kong, China  

E-Print Network (OSTI)

Optimal Tracking of Distributed Heavy Hitters and Quantiles Ke Yi HKUST Hong Kong, China yike heavy hitters and quantiles in the distributed streaming model. The heavy hitters and quantiles are two the universe U = {1, . . . , u}. For a given 0 1, the -heavy hitters are those elements of A whose frequency

Yi, Ke "Kevin"

329

Anomalous Radiative Decay of Heavy Higgs Boson  

E-Print Network (OSTI)

The radiative decay width of a heavy Higgs boson $H \\rightarrow W^+W^-\\gamma$ for a {\\it hard} photon is calculated in the Standard Model and its extension with anomalous $\\gamma WW$ couplings. Its dependence on the Higgs mass, the two unknown anomalous couplings, and the photon energy cutoff are studied in detail. We show that this radiative decay of a heavy Higgs is not very sensitive to a wide range of the anomalous couplings compared to the Standard Model result.

Tzu Chiang Yuan

1992-05-27T23:59:59.000Z

330

Definition of heavy oil and natural bitumen  

Science Conference Proceedings (OSTI)

Definition and categorization of heavy oils and natural bitumens are generally based on physical or chemical attributes or on methods of extraction. Ultimately, the hydrocarbon's chemical composition will govern both its physical state and the extraction technique applicable. These oils and bitumens closely resemble the residuum from wholecrude distillation to about 1,000/degree/F; if the residuum constitutes at least 15% of the crude, it is considered to be heavy. In this material is concentrated most of the trace elements, such as sulfur, oxygen, and nitrogen, and metals, such as nickel and vanadium. A widely used definition separates heavy oil from natural bitumen by viscosity, crude oil being less, and bitumen more viscous than 10,000 cp. Heavy crude then falls in the range 10/degree/-20/degree/ API inclusive and extra-heavy oil less than 10/degree/ API. Most natural bitumen is natural asphalt (tar sands, oil sands) and has been defined as rock containing hydrocarbons more viscous than 10,000 cp or else hydrocarbons that may be extracted from mined or quarried rock. Other natural bitumens are solids, such as gilsonite, grahamite, and ozokerite, which are distinguished by streak, fusibility, and solubility. The upper limit for heavy oil may also be set at 18/degree/ API, the approximate limit for recovery by waterflood.

Meyer, R.F.

1988-08-01T23:59:59.000Z

331

Alternative Fuels Data Center: Heavy-Duty Idle Reduction Requirement  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Heavy-Duty Idle Heavy-Duty Idle Reduction Requirement to someone by E-mail Share Alternative Fuels Data Center: Heavy-Duty Idle Reduction Requirement on Facebook Tweet about Alternative Fuels Data Center: Heavy-Duty Idle Reduction Requirement on Twitter Bookmark Alternative Fuels Data Center: Heavy-Duty Idle Reduction Requirement on Google Bookmark Alternative Fuels Data Center: Heavy-Duty Idle Reduction Requirement on Delicious Rank Alternative Fuels Data Center: Heavy-Duty Idle Reduction Requirement on Digg Find More places to share Alternative Fuels Data Center: Heavy-Duty Idle Reduction Requirement on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Heavy-Duty Idle Reduction Requirement Heavy-duty vehicles with a gross vehicle weight rating greater than 8,500

332

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

333

Matching heavy-light currents with NRQCD and HISQ quarks  

E-Print Network (OSTI)

We calculate the one loop renormalisation parameters for the heavy-light axial-vector and vector currents using lattice perturbation theory. We use NonRelativistic QCD (NRQCD) heavy quarks and the Highly Improved Staggered Quark (HISQ) action for the light quarks. We present results for heavy-light currents with massless HISQ quarks and briefly discuss the extension to heavy-heavy currents with massive HISQ quarks.

Christopher Monahan; Christine Davies; Ron Horgan; G. Peter Lepage; Heechang Na; Junko Shigemitsu

2012-10-25T23:59:59.000Z

334

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

335

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

336

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

337

Water issues associated with heavy oil production.  

Science Conference Proceedings (OSTI)

Crude oil occurs in many different forms throughout the world. An important characteristic of crude oil that affects the ease with which it can be produced is its density and viscosity. Lighter crude oil typically can be produced more easily and at lower cost than heavier crude oil. Historically, much of the nation's oil supply came from domestic or international light or medium crude oil sources. California's extensive heavy oil production for more than a century is a notable exception. Oil and gas companies are actively looking toward heavier crude oil sources to help meet demands and to take advantage of large heavy oil reserves located in North and South America. Heavy oil includes very viscous oil resources like those found in some fields in California and Venezuela, oil shale, and tar sands (called oil sands in Canada). These are described in more detail in the next chapter. Water is integrally associated with conventional oil production. Produced water is the largest byproduct associated with oil production. The cost of managing large volumes of produced water is an important component of the overall cost of producing oil. Most mature oil fields rely on injected water to maintain formation pressure during production. The processes involved with heavy oil production often require external water supplies for steam generation, washing, and other steps. While some heavy oil processes generate produced water, others generate different types of industrial wastewater. Management and disposition of the wastewater presents challenges and costs for the operators. This report describes water requirements relating to heavy oil production and potential sources for that water. The report also describes how water is used and the resulting water quality impacts associated with heavy oil production.

Veil, J. A.; Quinn, J. J.; Environmental Science Division

2008-11-28T23:59:59.000Z

338

Ratios of heavy baryons to heavy mesons in relativistic nucleus-nucleus collisions  

E-Print Network (OSTI)

Heavy baryon/meson ratios Lambda(c)/D(0) and Lambda(b)/(B) over bar (0) in relativistic heavy ion collisions are studied in the quark coalescence model. For heavy baryons, we include production from coalescence of heavy quarks with free light quarks as well as with bounded light diquarks that might exist in the strongly coupled quark-gluon plasma produced in these collisions. Including the contribution from decays of heavy hadron resonances and also that due to fragmentation of heavy quarks that are left in the system after coalescence, the resulting Lambda(c)/D(0) and Lambda(b)/(B) over bar (0) ratios in midrapidity (vertical bar y vertical bar heavy baryon/meson ratios is found to be sensitive to the heavy quark mass, with the Lambda(b)/(B) over bar (0) ratio being much flatter than the Lambda(c)/D(0) ratio. The latter peaks at the transverse momentum p(T) similar or equal to 0.8 GeV but the peak shifts to p(T) similar or equal to 2 GeV in the absence of diquarks.

Oh, Yongseok; Ko, Che Ming; Lee, Su Houng; Yasui, Shigehiro.

2009-01-01T23:59:59.000Z

339

HEAVY ELEMENT ISOTOPIC ANALYSIS OF UO$sub 2$ FUEL IRRADIATED IN THE VBWR. Report No. 1  

SciTech Connect

Slightly enriched UO/sub 2/ fuel, irradiated in the Vallecitos Boiling Water Reactor (VBWR), with exposures ranging from 100 Mwd/t to 3200 Mwd/t was analyzed for heavy element isotopic composition and compared with computed data. The primary objective of this program is to obtain improved data on the changes in nuclear characteristics with burnup of UO/sub 2/ fuel in a boiling water reactor. This information is important in both evaluating the economics of a given reactor design and also in providing a sounder physics basis for improving reactor designs to minimize the resuiting fuel costs. Uranium oxide pellets, with an enrichment of 2.8 atom percent, were analyzed at several axial positions along the fuel rod, spanning the void (steam fraction) range of 0 to 30%. The isotopic composition for each pellet was computed, utilizing a general fuel cycle depletion code. Results of the analysis of the comparison of the measured and computed data indicate that the total amount of Pu computed is consistently lower than that implied from the measurement by approximately 10%, and the percentage difference between the measured and computed data increases slightly with exposure. One rod was irradiated near a control rod which was approximately 25% inserted. As expected, since no control rod effects were included in the calcuiation, the measured data in that region of the rod shows a greater Pu production per Mwd/t than computed. Physical effects which might explain the small, but apparentiy consistent, differences between the measured and computed data were postulated. It is concluded that the observed differences are the result of a substantial underestimate of void fraction and small uncertainties in fuel exposure and cross sections. (auth)

Hackney, M.R.; Ruiz, C.P.

1962-12-28T23:59:59.000Z

340

Magnetic Process For Removing Heavy Metals From Water Employing Magnetites  

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

Magnetic Process For Removing Heavy Metals From Water Employing Magnetic Process For Removing Heavy Metals From Water Employing Magnetites Magnetic Process For Removing Heavy Metals From Water Employing Magnetites A process for removing heavy metals from water is provided. The process includes the steps of introducing magnetite to a quantity of water containing heavy metal. Available for thumbnail of Feynman Center (505) 665-9090 Email Magnetic Process For Removing Heavy Metals From Water Employing Magnetites A process for removing heavy metals from water is provided. The process includes the steps of introducing magnetite to a quantity of water containing heavy metal. The magnetite is mixed with the water such that at least a portion of, and preferably the majority of, the heavy metal in the water is bound to the magnetite. Once this occurs the magnetite and

Note: This page contains sample records for the topic "heavy naphtha boiling" 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

Alternative Fuels Data Center: Heavy-Duty Vehicle Emissions Reduction  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Heavy-Duty Vehicle Heavy-Duty Vehicle Emissions Reduction Grants to someone by E-mail Share Alternative Fuels Data Center: Heavy-Duty Vehicle Emissions Reduction Grants on Facebook Tweet about Alternative Fuels Data Center: Heavy-Duty Vehicle Emissions Reduction Grants on Twitter Bookmark Alternative Fuels Data Center: Heavy-Duty Vehicle Emissions Reduction Grants on Google Bookmark Alternative Fuels Data Center: Heavy-Duty Vehicle Emissions Reduction Grants on Delicious Rank Alternative Fuels Data Center: Heavy-Duty Vehicle Emissions Reduction Grants on Digg Find More places to share Alternative Fuels Data Center: Heavy-Duty Vehicle Emissions Reduction Grants on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Heavy-Duty Vehicle Emissions Reduction Grants

342

Advanced Vehicle Testing Activity: Medium- and Heavy-Duty Vehicles  

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

Medium- and Medium- and Heavy-Duty Vehicles to someone by E-mail Share Advanced Vehicle Testing Activity: Medium- and Heavy-Duty Vehicles on Facebook Tweet about Advanced Vehicle Testing Activity: Medium- and Heavy-Duty Vehicles on Twitter Bookmark Advanced Vehicle Testing Activity: Medium- and Heavy-Duty Vehicles on Google Bookmark Advanced Vehicle Testing Activity: Medium- and Heavy-Duty Vehicles on Delicious Rank Advanced Vehicle Testing Activity: Medium- and Heavy-Duty Vehicles on Digg Find More places to share Advanced Vehicle Testing Activity: Medium- and Heavy-Duty Vehicles on AddThis.com... Home Overview Light-Duty Vehicles Medium- and Heavy-Duty Vehicles Transit Vehicles Trucks Idle Reduction Oil Bypass Filter Airport Ground Support Equipment Medium and Heavy Duty Hybrid Electric Vehicles

343

Heavy Quarks, QCD, and Effective Field Theory  

SciTech Connect

The research supported by this OJI award is in the area of heavy quark and quarkonium production, especially the application Soft-Collinear E#11;ective Theory (SCET) to the hadronic production of quarkonia. SCET is an e#11;ffective theory which allows one to derive factorization theorems and perform all order resummations for QCD processes. Factorization theorems allow one to separate the various scales entering a QCD process, and in particular, separate perturbative scales from nonperturbative scales. The perturbative physics can then be calculated using QCD perturbation theory. Universal functions with precise fi#12;eld theoretic de#12;nitions describe the nonperturbative physics. In addition, higher order perturbative QCD corrections that are enhanced by large logarithms can be resummed using the renormalization group equations of SCET. The applies SCET to the physics of heavy quarks, heavy quarkonium, and similar particles.

Thomas Mehen

2012-10-09T23:59:59.000Z

344

Pipelineable syncrude (synthetic crude) from heavy oil  

SciTech Connect

This patent describes a process for converting a metals-contaminated heavy crude oil characterized by an API gravity less than about 20{degrees} and a substantial Conradson Carbon Residue to a pipelineable and substantially upgraded syncrude with concomitant recovery of blown asphalt. It comprises: air-blowing at least the 650{degrees} F.{sup +} fraction of the heavy crude oil at a temperature of 390{degrees} to 600{degrees} F. under conditions effective to increase its combined oxygen content by at least 0.5 weight percent; deasphalting the air-blown crude oil with solvent whereby separately recovering a blown asphalt and an intermediate syncrude having a substantially lower concentration of metals and less Conradson Carbon residue than the heavy crude oil; and, visbreaking the intermediate syncrude at 800{degrees} to 950{degrees} F. and at a severity effective to impart to it pipelineable viscosity characteristics.

Rankel, L.A.

1989-06-12T23:59:59.000Z

345

Heavy Truck Clean Diesel Cooperative Research Program  

DOE Green Energy (OSTI)

This report is the final report for the Department of Energy on the Heavy Truck Engine Program (Contract No. DE-FC05-00OR22806) also known as Heavy Truck Clean Diesel (HTCD) Program. Originally, this was scoped to be a $38M project over 5 years, to be 50/50 co-funded by DOE and Caterpillar. The program started in June 2000. During the program the timeline was extended to a sixth year. The program completed in December 2006. The program goal was to develop and demonstrate the technologies required to enable compliance with the 2007 and 2010 (0.2g/bhph NOx, 0.01g/bhph PM) on-highway emission standards for Heavy Duty Trucks in the US with improvements in fuel efficiency compared to today's engines. Thermal efficiency improvement from a baseline of 43% to 50% was targeted.

Milam, David

2006-12-31T23:59:59.000Z

346

Recent developments in heavy flavour production  

E-Print Network (OSTI)

We review one-particle inclusive production of heavy-flavoured hadrons in a framework which resums the large collinear logarithms through the evolution of the FFs and PDFs and retains the full dependence on the heavy-quark mass without additional theoretical assumptions. We focus on presenting results for the inclusive cross section for the production of charmed mesons in p anti-p collisions and the comparison with CDF data from the Tevatron as well as on inclusive B-meson production and comparison with recent CDF data. The third topic is the production of D^* mesons in photoproduction and comparison with recent H1 data from HERA.

G. Kramer

2007-07-12T23:59:59.000Z

347

Heavy Nuclei from RHIC to the Cosmos  

E-Print Network (OSTI)

Ultra-relativistic heavy ion collisions produce a high-temperature, thermalized system that may mimic the conditions present shortly after the big bang. This writeup will given an overview of early results from the Relativistic Heavy Ion Collider (RHIC), and discuss what we have learned about hot, strongly interacting nuclear systems. The thermal and chemical composition of the system will be discussed, along with observables that are sensitive to the early evolution of the system. I will also discuss the implications of the RHIC results for cosmic ray air showers.

Spencer R. Klein

2002-11-01T23:59:59.000Z

348

1 Heavy-light physics with NRQCD  

E-Print Network (OSTI)

First results are obtained for B mesons using a heavy propagator calculated using NRQCD, and a light Wilson propagator. Results from 13 quenched configurations of size 16 3 × 48 at ? = 6.0 give a value for fB of less than 200 MeV and a B ? ?B splitting of 32(8) MeV. Superior signal/noise behaviour is observed over static propagators on the same configurations. No extrapolation to the b mass for the heavy quark is required. 1.

unknown authors

1993-01-01T23:59:59.000Z

349

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

350

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

351

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

352

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

353

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

354

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

355

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

356

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

357

YEAR-END REPORT: HEAVY ION FUSION PROGRAM  

E-Print Network (OSTI)

1978-Mar. 1979, Heavy Ion Fusion Program, Lawrence BerkeleyOlson, Proceedings of the Heavy Ion Fusion Workshop, ArgonneUniversity Ravi N. Sudan KMS Fusion, Inc. Stanford Linear

Fusion Staff, Heavy Ion

2010-01-01T23:59:59.000Z

358

INERTIAL FUSION DRIVEN BY INTENSE HEAVY-ION BEAMS  

E-Print Network (OSTI)

HIFAN 1830 INERTIAL FUSION DRIVEN BY INTENSE HEAVY-ION BEAMSAC02-05CH11231. INERTIAL FUSION DRIVEN BY INTENSE HEAVY-ION467 (1992). [38] R. W. Moir, Fusion Tech. 25, 5 (1994) [39

Sharp, W. M.

2011-01-01T23:59:59.000Z

359

Analysis of a Heavy Rainfall Event during TAMEX  

Science Conference Proceedings (OSTI)

A heavy rainfall event during the Taiwan Area Mesoscale Experiment intensive observing period 13 has been studied using upper-air, surface mesonet, and dual-Doppler radar data. The heavy rainfall (?231 mm day?1) occurred over northwestern Taiwan ...

Jun Li; Yi-Leng Chen; Wen-Chau Lee

1997-06-01T23:59:59.000Z

360

Twisted mass QCD and the FNAL heavy quark formalism  

E-Print Network (OSTI)

At tree level, I discuss modifying the FNAL heavy quark formalism to include a twisted mass term. I find that at maximal twist the so called KLM factor is independent of the heavy mass.

Craig McNeile

2008-10-21T23:59:59.000Z

Note: This page contains sample records for the topic "heavy naphtha boiling" 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

Texas Refinery Catalytic Hydrotreating, Heavy Gas Oil Downstream ...  

U.S. Energy Information Administration (EIA)

Hydro. Heavy Gas Oil Downstream Charge Capacity (B/SD)y ; Cat. Hydro. Heavy Gas Oil Downstream Charge Capacity (B/SD)y ; Texas Downstream Charge Capacity of Operable ...

362

Vehicle Technologies Office: Fact #363: March 14, 2005 Heavy...  

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

3: March 14, 2005 Heavy Truck Miles by Age to someone by E-mail Share Vehicle Technologies Office: Fact 363: March 14, 2005 Heavy Truck Miles by Age on Facebook Tweet about...

363

The high current transport experiment for heavy ion inertial fusion  

E-Print Network (OSTI)

on Heavy Ion Inertial Fusion, Princeton, 1996, edited by J.Conference on Inertial Fusion Sciences and Applications (FOR HEAVY ION INERTIAL FUSION 1 L. R. Prost, D. Baca, F. M.

2004-01-01T23:59:59.000Z

364

The Modular Point Design for Heavy Ion Fusion  

E-Print Network (OSTI)

POINT DESIGN FOR HEAVY ION FUSION S.S. Yu 1 , J.J. BarnardUpdated Point Design for Heavy Ion Fusion,” Proc. 2002 Amer.Nucl. Soc. Fusion Topical Meeting, 17-21 November 2002,

2004-01-01T23:59:59.000Z

365

Heavy metals behaviour in a gasification reactor  

Science Conference Proceedings (OSTI)

Sludge coming from cleaning processes of wastewater, Municipal Solid Waste (MSW), and Refuse Derived Fuel (RDF) can be exploited for producing energy because of their heating value. Cleaning the produced syngas is important because of environmental troubles, ... Keywords: heavy metals, syngas, thermodynamic, waste gasification

Martino Paolucci; Carlo Borgianni; Paolo De Filippis

2011-07-01T23:59:59.000Z

366

Carbon foils as heavy ion strippers  

SciTech Connect

A discussion is given of the advantages and disadvantages of thin carbon foil strippers for heavy ion beams from tandem electrostatic accelerators. Foil lifetimes were increased by radiative heating and by the evaporation of a thin layer of gold on the foil. (PMA)

Yntema, J.L.

1975-01-01T23:59:59.000Z

367

Scaling in heavy-fermion systems  

SciTech Connect

Ambient pressure characteristics of heavy-fermion compounds, such as the ratio of the low temperature magnetic susceptibility to the electronic specific heat coefficient {gamma} and a simple relationship between the T{sup 2}-coefficient of resistivity and {gamma}{sup 2}, suggest that a single-energy scale T{sub o} dictates the physics of these materials. Such is the case for Kondo-impurity systems to which heavy-fermions are related. We consider the consequences of assuming that the electronic free energy is given by a universal function of T/T{sub o} (V) where V is the molar volume. We show that volume-dependent magnetic susceptibility, specific heat and electrical resistivity of some heavy-fermion compounds scale as T/T{sub o} (V), at least over a range in pressures and temperatures. A further consequence of the principle assumption is that Gruneisen parameters defined as - {partial_derivative}{ell}nX/{partial_derivative}nV, where X is some physical property, should be identical for all properties and equal to that determined from electronic contributions to the volume- thermal expansion coefficient and specific heat. In several materials, this equality holds, at least approximately. Although evidence is found for single-energy scaling in heavy-fermion materials, we cannot conclude unambiguously that the basic assumption is correct in detail.

Thompson, J.D.; Fisk, Z. [Los Alamos National Lab., NM (United States); Lawrence, J.M. [California Univ., Irvine, CA (United States). Dept. of Physics

1993-12-31T23:59:59.000Z

368

HEAVY AND THERMAL OIL RECOVERY PRODUCTION MECHANISMS  

Science Conference Proceedings (OSTI)

This technical progress report describes work performed from April 1 through June 30, 2002, for the project ''Heavy and Thermal Oil Recovery Production Mechanisms.'' We investigate a broad spectrum of topics related to thermal and heavy-oil recovery. Significant results were obtained in the areas of multiphase flow and rock properties, hot-fluid injection, improved primary heavy oil recovery, and reservoir definition. The research tools and techniques used are varied and span from pore-level imaging of multiphase fluid flow to definition of reservoir-scale features through streamline-based history-matching techniques. Briefly, experiments were conducted to image at the pore level matrix-to-fracture production of oil from a fractured porous medium. This project is ongoing. A simulation studied was completed in the area of recovery processes during steam injection into fractured porous media. We continued to study experimentally heavy-oil production mechanisms from relatively low permeability rocks under conditions of high pressure and high temperature. High temperature significantly increased oil recovery rate and decreased residual oil saturation. Also in the area of imaging production processes in laboratory-scale cores, we use CT to study the process of gas-phase formation during solution gas drive in viscous oils. Results from recent experiments are reported here. Finally, a project was completed that uses the producing water-oil ratio to define reservoir heterogeneity and integrate production history into a reservoir model using streamline properties.

Anthony R. Kovscek

2002-07-01T23:59:59.000Z

369

Joint resummation for heavy quark production  

E-Print Network (OSTI)

We present joint threshold and recoil resummed transverse momentum distributions for heavy quark hadroproduction, at next-to-leading logarithmic accuracy. We study the dependence of these distributions on the production channel, the color configurations and the differences with the pure threshold-resummed distribution.

Andrea Banfi; Eric Laenen

2004-11-18T23:59:59.000Z

370

A cost analysis model for heavy equipment  

Science Conference Proceedings (OSTI)

Total cost is one of the most important factors for a heavy equipment product purchase decision. However, the different cost views and perspectives of performance expectations between the different involved stakeholders may cause customer relation problems ... Keywords: Cost responsibilities, Operating costs, Ownership costs, Post-Manufacturing Product Cost (PMPC), System life-cycle cost

Shibiao Chen; L. Ken Keys

2009-05-01T23:59:59.000Z

371

Some Common Ingredients for Heavy Orographic Rainfall  

Science Conference Proceedings (OSTI)

The purpose of this paper is to synthesize some common synoptic and mesoscale environments conducive to heavy orographic rainfall. Previous studies of U.S. and Alpine cases and new analyses of some Alpine and east Asian cases have shown the ...

Yuh-Lang Lin; Sen Chiao; Ting-An Wang; Michael L. Kaplan; Ronald P. Weglarz

2001-12-01T23:59:59.000Z

372

Thermal processes for heavy oil recovery  

Science Conference Proceedings (OSTI)

This status report summarizes the project BE11B (Thermal Processes for Heavy Oil Recovery) research activities conducted in FY93 and completes milestone 7 of this project. A major portion of project research during FY93 was concentrated on modeling and reservoir studies to determine the applicability of steam injection oil recovery techniques in Texas Gulf Coast heavy oil reservoirs. In addition, an in-depth evaluation of a steamflood predictive model developed by Mobil Exploration and Production Co. (Mobil E&P) was performed. Details of these two studies are presented. A topical report (NIPER-675) assessing the NIPER Thermal EOR Research Program over the past 10 years was also written during this fiscal year and delivered to DOE. Results of the Gulf Coast heavy oil reservoir simulation studies indicated that though these reservoirs can be successfully steamflooded and could recover more than 50% of oil-in-place, steamflooding may not be economical at current heavy oil prices. Assessment of Mobil E&P`s steamflood predictive model capabilities indicate that the model in its present form gives reasonably good predictions of California steam projects, but fails to predict adequately the performance of non-California steam projects.

Sarkar, A.K.; Sarathi, P.S.

1993-11-01T23:59:59.000Z

373

Talon Heavy Hoist and Safety Latch  

Engineers at the Savannah River Site (SRS) have devised a new design for a latching hoist hook with remote unlatching capabilities.  The TalonTM hoist hook and safety latch is designed for lifting heavy loads as well as locking the load in place with ...

374

Towards Heavy Fermions in Europium Intermetallic Compounds  

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

Towards Heavy Fermions in Towards Heavy Fermions in Europium Intermetallic Compounds Towards Heavy Fermions in Europium Intermetallic Compounds Print Wednesday, 29 July 2009 00:00 For decades, intermetallic compounds of rare-earth metals have been favorite systems of the research community studying strong electron correlations in solids. Nowadays rare-earth intermetallics are often treated as model systems for studies of zero-temperature quantum critical phase transitions, since heavy-fermion rare-earth compounds (in which the electron effective mass is orders of magnitude larger than the bare electron mass) have provided the clearest evidence for these continuous phase transitions, which are controlled by such parameters as chemical composition, magnetic field, and pressure, rather than temperature. A new study of a europium-based compound by an international team led by researchers from the Technische Universität Dresden in Germany hints that this compound could join well-known compounds of cerium, ytterbium, and uranium as a new material suitable for research on quantum critical transitions. This finding is exciting, since physicists hope that the use of a new material will give an additional degree of freedom for researching quantum critical behavior.

375

HEAVY AND THERMAL OIL RECOVERY PRODUCTION MECHANISMS  

SciTech Connect

The Stanford University Petroleum Research Institute (SUPRI-A) studies oil recovery mechanisms relevant to thermal and heavy-oil production. The scope of work is relevant across near-, mid-, and long-term time frames. In August of 2000 we received funding from the U. S. DOE under Award No. DE-FC26-00BC15311 that completed December 1, 2003. The project was cost shared with industry. Heavy oil (10 to 20{sup o} API) is an underutilized energy resource of tremendous potential. Heavy oils are much more viscous than conventional oils. As a result, they are difficult to produce with conventional recovery methods. Heating reduces oil viscosity dramatically. Hence, thermal recovery is especially important because adding heat, usually via steam injection generally improves displacement efficiency. The objectives of this work were to improve our understanding of the production mechanisms of heavy oil under both primary and enhanced modes of operation. The research described spanned a spectrum of topics related to heavy and thermal oil recovery and is categorized into: (1) multiphase flow and rock properties, (2) hot fluid injection, (3) improved primary heavy-oil recovery, (4) in-situ combustion, and (5) reservoir definition. Technology transfer efforts and industrial outreach were also important to project effort. The research tools and techniques used were quite varied. In the area of experiments, we developed a novel apparatus that improved imaging with X-ray computed tomography (CT) and high-pressure micromodels etched with realistic sandstone roughness and pore networks that improved visualization of oil-recovery mechanisms. The CT-compatible apparatus was invaluable for investigating primary heavy-oil production, multiphase flow in fractured and unfractured media, as well as imbibition. Imbibition and the flow of condensed steam are important parts of the thermal recovery process. The high-pressure micromodels were used to develop a conceptual and mechanistic picture of primary heavy-oil production by solution gas drive. They allowed for direct visualization of gas bubble formation, bubble growth, and oil displacement. Companion experiments in representative sands and sandstones were also conducted to understand the mechanisms of cold production. The evolution of in-situ gas and oil saturation was monitored with CT scanning and pressure drop data. These experiments highlighted the importance of depletion rate, overburden pressure, and oil-phase chemistry on the cold production process. From the information provided by the experiments, a conceptual and numerical model was formulated and validated for the heavy-oil solution gas drive recovery process. Also in the area of mechanisms, steamdrive for fractured, low permeability porous media was studied. Field tests have shown that heat injected in the form of steam is effective at unlocking oil from such reservoir media. The research reported here elucidated how the basic mechanisms differ from conventional steamdrive and how these differences are used to an advantage. Using simulations of single and multiple matrix blocks that account for details of heat transfer, capillarity, and fluid exchange between matrix and fracture, the importance of factors such as permeability contrast between matrix and fracture and oil composition were quantified. Experimentally, we examined the speed and extent to which steam injection alters the permeability and wettability of low permeability, siliceous rocks during thermal recovery. Rock dissolution tends to increase permeability moderately aiding in heat delivery, whereas downstream the cooled fluid deposits silica reducing permeability. Permeability reduction is not catastrophic. With respect to wettability, heat shifts rock wettability toward more water wet conditions. This effect is beneficial for the production of heavy and medium gravity oils as it improves displacement efficiency. A combination of analytical and numerical studies was used to examine the efficiency of reservoir heating using nonconventional wells such as horizontal and multi

Anthony R. Kovscek; Louis M. Castanier

2003-12-31T23:59:59.000Z

376

Abstract: Isochoric Heat Capacity of Light and Heavy Water at ...  

Science Conference Proceedings (OSTI)

Isochoric Heat Capacity of Light and Heavy Water at Subcritical and Supercritical Conditions. IM Abdulagatov, JW Magee ...

377

U.S. Refinery Catalytic Hydrotreating, Heavy Gas Oil ...  

U.S. Energy Information Administration (EIA)

U.S. Refinery Catalytic Hydrotreating, Heavy Gas Oil Downstream Charge Capacity as of January 1 (Barrels per Stream Day)

378

HEAVY WATER PRODUCTION: A REVIEW OF PROCESSES.  

SciTech Connect

Methods of heavy water production are examined in detail. Processes based on chemical exchange have the greatest potential for further development but distillation, electrolytic and chromatographic methods are also discussed. In the immediate future most of the world output of heavy water will be produced by hydrogen sulphide/water exchange (the GS process) but there is limited scope for further reduction in GS production costs. Recent advances in process development make the ammonia/hydrogen route an attractive alternative since the enrichment obtainable in each stage is greater while the energy consumption is less. A variation of the ammonia/hydrogen scheme involving the use of amines as additives to, or substitutes for ammonia also appears promising. The greatest obstacle to the development of either the ammonia/hydrogen or amine/hydrogen schemes on a large scale is the limitation on the supply of hydrogen. Ammonia synthesis gas is currently the most plentiful supply available but 1500 tonnes/day of ammonia capacity is needed for each 100 tonnes of heavy water produced annually. Unlimited production could be achieved using an equilibration stage in which hydrogen depleted in deuterium is exchanged with water at high temperature. The economics of this scheme depend on the development of a satisfactory catalyst for water/hydrogen equilibration. Distillation of water, methane and hydrogen have been proposed as econmic routes to heavy water production but design studies and experimental data would need to be clarified if optimistic forecasts are to be substantiated. Processes based on chromatography or selective adsorption have received scant attention in the past. Many problems would need to be overcome before such processes could be adapted to large scale production of heavy water, but in view of recent advances in plant scale chromatography, they should be re-examined. (auth)

Levins, D.M.

1970-09-15T23:59:59.000Z

379

Catalytic multi-stage process for hydroconversion and refining hydrocarbon feeds  

DOE Green Energy (OSTI)

A multi-stage catalytic hydrogenation and hydroconversion process for heavy hydrocarbon feed materials such as coal, heavy petroleum fractions, and plastic waste materials. In the process, the feedstock is reacted in a first-stage, back-mixed catalytic reactor with a highly dispersed iron-based catalyst having a powder, gel or liquid form. The reactor effluent is pressure-reduced, vapors and light distillate fractions are removed overhead, and the heavier liquid fraction is fed to a second stage back-mixed catalytic reactor. The first and second stage catalytic reactors are operated at 700-850.degree. F. temperature, 1000-3500 psig hydrogen partial pressure and 20-80 lb./hr per ft.sup.3 reactor space velocity. The vapor and light distillates liquid fractions removed from both the first and second stage reactor effluent streams are combined and passed to an in-line, fixed-bed catalytic hydrotreater for heteroatom removal and for producing high quality naphtha and mid-distillate or a full-range distillate product. The remaining separator bottoms liquid fractions are distilled at successive atmospheric and vacuum pressures, low and intermediate-boiling hydrocarbon liquid products are withdrawn, and heavier distillate fractions are recycled and further upgraded to provide additional low-boiling hydrocarbon liquid products. This catalytic multistage hydrogenation process provides improved flexibility for hydroprocessing the various carbonaceous feedstocks and adjusting to desired product structures and for improved economy of operations.

Comolli, Alfred G. (Yardley, PA); Lee, Lap-Keung (Cranbury, NJ)

2001-01-01T23:59:59.000Z

380

LYSINE, METHIONINE AND CYSTINE REQUIREMENTS OF SEMI-HEAVY LAYERS  

E-Print Network (OSTI)

LYSINE, METHIONINE AND CYSTINE REQUIREMENTS OF SEMI-HEAVY LAYERS M. PICARD S. BERTRAND J. SALVERT Service zootechnique, A. E. C., 03600 Commentry Two different strains of commercial semi-heavy layers of lysine. This trial confirms our previous works. A semi-heavy layer is largely satisfied by a feed

Recanati, Catherine

Note: This page contains sample records for the topic "heavy naphtha boiling" 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

BUCSTR2000017 1 TCP Congestion Control and Heavy Tails  

E-Print Network (OSTI)

BUCS­TR­2000­017 1 TCP Congestion Control and Heavy Tails LIANG GUO MARK CROVELLA IBRAHIM MATTA­ ies have shown that there is a close relationship between heavy­tailed distribution of various traffic traffic with heavy­tailed OFF, or idle, periods, and therefore introduces long­range de­ pendence

Texas at Arlington, University of

382

Efficient Algorithms for Heavy-Tail Analysis under Interval Uncertainty  

E-Print Network (OSTI)

Efficient Algorithms for Heavy-Tail Analysis under Interval Uncertainty Vladik Kreinovich1 heavy-tailed distri- butions, i.e., distributions in which (x) decreases as (x) x- . To properly take for computing these ranges. Keywords: heavy-tailed distributions, interval uncertainty, efficient algorithms

Kreinovich, Vladik

383

RADIATION RESEARCH 153, 220238 (2000) 0033-7587/00 $5.00  

E-Print Network (OSTI)

): the light water reactor [(LWR) in both pressurized and boil- ing versions]; heavy water (CANDU) reactor

384

16. Heavy-Quark and Soft-Collinear Effective Theory 1 16. Heavy-Quark and Soft-Collinear Effective Theory  

E-Print Network (OSTI)

16. Heavy-Quark and Soft-Collinear Effective Theory 1 16. Heavy-Quark and Soft-Collinear Effective the quantum fluctuations of such heavy particles are "integrated out" from the generating functional integral.lbl.gov) February 16, 2012 14:07 #12;2 16. Heavy-Quark and Soft-Collinear Effective Theory 16.2. Heavy

385

Vehicle Technologies Office: FY 2003 Progress Report for Heavy Vehicle  

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

3 Progress Report 3 Progress Report for Heavy Vehicle Propulsion Materials Program to someone by E-mail Share Vehicle Technologies Office: FY 2003 Progress Report for Heavy Vehicle Propulsion Materials Program on Facebook Tweet about Vehicle Technologies Office: FY 2003 Progress Report for Heavy Vehicle Propulsion Materials Program on Twitter Bookmark Vehicle Technologies Office: FY 2003 Progress Report for Heavy Vehicle Propulsion Materials Program on Google Bookmark Vehicle Technologies Office: FY 2003 Progress Report for Heavy Vehicle Propulsion Materials Program on Delicious Rank Vehicle Technologies Office: FY 2003 Progress Report for Heavy Vehicle Propulsion Materials Program on Digg Find More places to share Vehicle Technologies Office: FY 2003 Progress Report for Heavy Vehicle Propulsion Materials Program on

386

Plant rhamnogalacturonan II complexation of heavy metal cations  

DOE Patents (OSTI)

The present invention provides rhamnogalacturonan-II (RG-II) and relates to its ability to complex specific multivalent heavy metal cations. In the presence of boric acid, RG-II monomers form dimers that are cross-linked by a borate ester. The yield of such borate ester cross-linked dimers of RG-II is enhanced in the presence of specific heavy metal cations. The present invention further relates to the utility of RG-II in assays for the detection of specific heavy metal contamination; as a reagent useful in the removal of specific heavy metal cations contaminating foods and liquids, for example, fish, wines, etc.; as a pharmaceutical composition useful as an antidote in specific heavy metal cation poisoning; as a treatment for the detoxification of specific heavy metal cations from blood and/or tissues; and in a method of remediation of waters and soils contaminated with specific heavy metal cations.

O' Neill, Malcolm A. (Winterville, GA); Pellerin, Patrice J. M. (Montpellier, FR); Warrenfeltz, Dennis (Athens, GA); Vidal, Stephane (Combaillaux, FR); Darvill, Alan G. (Athens, GA); Albersheim, Peter (Athens, GA)

1999-01-01T23:59:59.000Z

387

Plant rhamnogalacturonan II complexation of heavy metal cations  

DOE Patents (OSTI)

The present invention provides rhamnogalacturonan-II (RG-II) and relates to its ability to complex specific multivalent heavy metal cations. In the presence of boric acid, RG-II monomers form dimers that are cross-linked by a borate ester. The yield of such borate ester cross-linked dimers of RG-II is enhanced in the presence of specific heavy metal cations. The present invention further relates to the utility of RG-II in assays for the detection of specific heavy metal contamination; as a reagent useful in the removal of specific heavy metal cations contaminating foods and liquids, for example, fish, wines, etc.; as a pharmaceutical composition useful as an antidote in specific heavy metal cation poisoning; as a treatment for the detoxification of specific heavy metal cations from blood and/or tissues; and in a method of remediation of waters and soils contaminated with specific heavy metal cations. 15 figs.

O`Neill, M.A.; Pellerin, P.J.M.; Warrenfeltz, D.; Vidal, S.; Darvill, A.G.; Albersheim, P.

1999-03-02T23:59:59.000Z

388

Vehicle Technologies Office: FY 2004 Progress Report for Heavy Vehicle  

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

4 Progress Report 4 Progress Report for Heavy Vehicle Propulsion Materials Program to someone by E-mail Share Vehicle Technologies Office: FY 2004 Progress Report for Heavy Vehicle Propulsion Materials Program on Facebook Tweet about Vehicle Technologies Office: FY 2004 Progress Report for Heavy Vehicle Propulsion Materials Program on Twitter Bookmark Vehicle Technologies Office: FY 2004 Progress Report for Heavy Vehicle Propulsion Materials Program on Google Bookmark Vehicle Technologies Office: FY 2004 Progress Report for Heavy Vehicle Propulsion Materials Program on Delicious Rank Vehicle Technologies Office: FY 2004 Progress Report for Heavy Vehicle Propulsion Materials Program on Digg Find More places to share Vehicle Technologies Office: FY 2004 Progress Report for Heavy Vehicle Propulsion Materials Program on

389

Implications to Heavy-Duty Diesel Emissions  

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

ORNL/TM-200015 ORNL/TM-200015 MANAGED BY UT-BATTELLE FOR THE DEPARTMENT OF ENERGY A Vector Approach to Regression Analysis and Its Implications to Heavy-Duty Diesel Emissions November 2000 Prepared by H. 1. McAdams AccaMath Services Carrolton, Illinois R. W. Crawford R.W. Crawford Energy Systems Tucson, Arizona G. R. Hadder Oak Ridge National Laboratory Oak Ridge, Tennessee - UT-BATTELLE -. ORNL-27 (4.00) II ORNL/TM-200015 A VECTOR APPROACH TO REGRESSION ANALYSIS AND ITS APPLICATION TO HEAVY-DUTY DIESEL EMISSIONS H. T. McAdams AccaMath Services Carrollton, Illinois R. W. Crawford RWCrawford Energy Systems Tucson, Arizona G. R. Hadder Oak Ridge National Laboratory Oak Ridge, Tennessee November 2000 Prepared for Office of Energy Effkiency and Renewable Energy

390

Lifecycle-analysis for heavy vehicles.  

DOE Green Energy (OSTI)

Various alternative fuels and improved engine and vehicle systems have been proposed in order to reduce emissions and energy use associated with heavy vehicles (predominantly trucks). For example, oil companies have proposed improved methods for converting natural gas to zero-aromatics, zero-sulfur diesel fuel via the Fischer-Tropsch process. Major heavy-duty diesel engine companies are working on ways to simultaneously reduce particulate-matter and NOX emissions. The trend in heavy vehicles is toward use of lightweight materials, tires with lower rolling resistance, and treatments to reduce aerodynamic drag. In this paper, we compare the Mecycle energy use and emissions from trucks using selected alternatives, such as Fisher-Tropsch diesel fuel and advanced fuel-efficient engines. We consider heavy-duty, Class 8 tractor-semitrailer combinations for this analysis. The total life cycle includes production and recycling of the vehicle itself, extraction, processing, and transportation of the fuel itself, and vehicle operation and maintenance. Energy use is considered in toto, as well as those portions that are imported, domestic, and renewable. Emissions of interest include greenhouse gases and criteria pollutants. Angonne's Greenhouse Gases, Regulated Emissions, and Energy Use in Transportation (GREET) model is used to generate per-vehicle fuel cycle impacts. Energy use and emissions for materials manufacturing and vehicle disposal are estimated by means of materials information from Argonne studies. We conclude that there are trade-offs among impacts. For example, the lowest fossil energy use does not necessarily result in lowest total energy use, and lower tailpipe emissions may not necessarily result in lower lifecycle emissions of all criteria pollutants.

Gaines, L.

1998-04-16T23:59:59.000Z

391

A Radiographic Technique With Heavy Ion Microbeams  

SciTech Connect

In this work, we introduce a new technique to perform densitometric and multielemental analysis of samples at the same time using a simple detector with heavy ion micro-beams. It consists in the simultaneous analysis of X-rays induced in the sample and in a secondary target arranged behind the specimen. The X-rays originated in the secondary target are attenuated when crossing the specimen producing a radiographic image with a monochromatic source.

Muscio, J. [ECyT, UNSAM, 1650 San Martin, Buenos Aires (Argentina); Somacal, H.; Burlon, A. A.; Debray, M. E.; Valda, A. A. [ECyT, UNSAM, 1650 San Martin, Buenos Aires (Argentina); U.A. Fisica, Laboratorio TANDAR, CNEA, 1650 San Martin, Buenos Aires (Argentina); Kreiner, A. J. [U.A. Fisica, Laboratorio TANDAR, CNEA, 1650 San Martin, Buenos Aires (Argentina); ECyT, UNSAM, 1650 San Martin, Buenos Aires (Argentina); CONICET (Argentina); Kesque, J. M.; Minsky, D. M. [U.A. Fisica, Laboratorio TANDAR, CNEA, 1650 San Martin, Buenos Aires (Argentina)

2007-02-12T23:59:59.000Z

392

Medium energy heavy ion operations at RHIC  

Science Conference Proceedings (OSTI)

As part of the search for a phase transition or critical point on the QCD phase diagram, an energy scan including 5 different energy settings was performed during the 2010 RHIC heavy ion run. While the top beam energy for heavy ions is at 100 GeV/n and the lowest achieved energy setpoint was significantly below RHICs injection energy of approximately 10 GeV/n, we also provided beams for data taking in a medium energy range above injection energy and below top beam energy. This paper reviews RHIC experience and challenges for RHIC medium energy operations that produced full experimental data sets at beam energies of 31.2 GeV/n and 19.5 GeV/n. The medium energy AuAu run covered two beam energies, both above the RHIC injection energy of 9.8 GeV but well below the standard store energy of 100 GeV (see table 1). The low energy and full energy runs with heavy ions in FY10 are summarized in [1] and [2]. Stochastic Cooling ([3]) was only used for 100 GeV beams and not used in the medium energy run. The efficiency of the transition from 100 GeV operation to 31.2 GeV and then to 19.5 GeV was remarkable. Setup took 32 h and 19 h respectively for the two energy settings. The time in store, defined to be the percentage of time RHIC provides beams in physics conditions versus calendar time, was approximately 52% for the entire FY10 heavy ion run. In both medium energy runs it was well above this average, 68% for 31.5 GeV and 82% for 19.5 GeV. For both energies RHIC was filled with 111 bunches with 1.2 10{sup 9} and 1.3 10{sup 9} ions per bunch respectively.

Drees, K.A.; Ahrens, L.; Bai, M.; Beebe-Wang, J.; Blackler, I.M.C.; Blaskiewicz, M.; Brown, K.A.; Brennan, M.; Bruno, D.; Butler, J.; Carlson, C.; Connolly, R.; D'Ottavio, T.; Fischer, W.; Fu, W.; Gassner, D.; Harvey, M.; Hayes, T.; Huang, H.; Hulsart, R.; Ingrassia, P.; Kling, N.; Lafky, M.; Laster, J.; Lee, R.C.; Litvinenko, V.; Luo, Y.; MacKay, W.W.; Marr, G.; Mapes. M.; Marusic, A.; Mernick, K.; Michnoff, R.; Minty, M.; Montag, C.; Morris, J.; Naylor, C.; Nemesure, S.; Pilat, F.; Ptitsyn, V.; Robert-Demolaize, G.; Roser, T.; Sampson, P.; Satogata, T.; Schoefer, V.; Schultheiss, C.; Severino, F.; Shrey, T.; Smith, K.S.; Tepikian, S.; Thieberger, P.; Trbojevic, D.; Tsoupas, N.; Tuozzolo, J.; van Kuik, B.; Wilinski, M.; Zaltsman, A.; Zeno, K.; Zhang, S.Y.

2011-03-28T23:59:59.000Z

393

Heavy flavour physics from top to bottom  

SciTech Connect

We review the status of heavy flavour physics at the Fermilab Tevatron collider by summarizing recent top quark and B physics results from CDF and D0. In particular we discuss the measurement of the top quark mass and top production cross section as well as B meson lifetimes and time dependent B{anti B} mixing results. An outlook of perspectives for top and B physics in Run II starting in 1999 is also given.

Paulini, M. [Lawrence Berkeley National Lab., CA (United States); CDF and D0 Collaboration

1998-02-01T23:59:59.000Z

394

Heavy Ion Fusion Systems Assessment study  

SciTech Connect

The Heavy Ion Fusion Systems Assessment (HIFSA) study was conducted with the specific objective of evaluating the prospects of using induction linac drivers to generate economical electrical power from inertial confinement fusion. The study used algorithmic models of representative components of a fusion system to identify favored areas in the multidimensional parameter space. The resulting cost-of-electricity (COE) projections are comparable to those from other (magnetic) fusion scenarios, at a plant size of 100 MWe.

Dudziak, D.J.; Herrmannsfeldt, W.B.

1986-07-01T23:59:59.000Z

395

Towards Heavy Fermions in Europium Intermetallic Compounds  

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

Towards Heavy Fermions in Europium Intermetallic Compounds Print Towards Heavy Fermions in Europium Intermetallic Compounds Print For decades, intermetallic compounds of rare-earth metals have been favorite systems of the research community studying strong electron correlations in solids. Nowadays rare-earth intermetallics are often treated as model systems for studies of zero-temperature quantum critical phase transitions, since heavy-fermion rare-earth compounds (in which the electron effective mass is orders of magnitude larger than the bare electron mass) have provided the clearest evidence for these continuous phase transitions, which are controlled by such parameters as chemical composition, magnetic field, and pressure, rather than temperature. A new study of a europium-based compound by an international team led by researchers from the Technische Universität Dresden in Germany hints that this compound could join well-known compounds of cerium, ytterbium, and uranium as a new material suitable for research on quantum critical transitions. This finding is exciting, since physicists hope that the use of a new material will give an additional degree of freedom for researching quantum critical behavior.

396

Towards Heavy Fermions in Europium Intermetallic Compounds  

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

Towards Heavy Fermions in Europium Intermetallic Compounds Print Towards Heavy Fermions in Europium Intermetallic Compounds Print For decades, intermetallic compounds of rare-earth metals have been favorite systems of the research community studying strong electron correlations in solids. Nowadays rare-earth intermetallics are often treated as model systems for studies of zero-temperature quantum critical phase transitions, since heavy-fermion rare-earth compounds (in which the electron effective mass is orders of magnitude larger than the bare electron mass) have provided the clearest evidence for these continuous phase transitions, which are controlled by such parameters as chemical composition, magnetic field, and pressure, rather than temperature. A new study of a europium-based compound by an international team led by researchers from the Technische Universität Dresden in Germany hints that this compound could join well-known compounds of cerium, ytterbium, and uranium as a new material suitable for research on quantum critical transitions. This finding is exciting, since physicists hope that the use of a new material will give an additional degree of freedom for researching quantum critical behavior.

397

Towards Heavy Fermions in Europium Intermetallic Compounds  

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

Towards Heavy Fermions in Europium Intermetallic Compounds Print Towards Heavy Fermions in Europium Intermetallic Compounds Print For decades, intermetallic compounds of rare-earth metals have been favorite systems of the research community studying strong electron correlations in solids. Nowadays rare-earth intermetallics are often treated as model systems for studies of zero-temperature quantum critical phase transitions, since heavy-fermion rare-earth compounds (in which the electron effective mass is orders of magnitude larger than the bare electron mass) have provided the clearest evidence for these continuous phase transitions, which are controlled by such parameters as chemical composition, magnetic field, and pressure, rather than temperature. A new study of a europium-based compound by an international team led by researchers from the Technische Universität Dresden in Germany hints that this compound could join well-known compounds of cerium, ytterbium, and uranium as a new material suitable for research on quantum critical transitions. This finding is exciting, since physicists hope that the use of a new material will give an additional degree of freedom for researching quantum critical behavior.

398

Towards Heavy Fermions in Europium Intermetallic Compounds  

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

Towards Heavy Fermions in Europium Intermetallic Compounds Print Towards Heavy Fermions in Europium Intermetallic Compounds Print For decades, intermetallic compounds of rare-earth metals have been favorite systems of the research community studying strong electron correlations in solids. Nowadays rare-earth intermetallics are often treated as model systems for studies of zero-temperature quantum critical phase transitions, since heavy-fermion rare-earth compounds (in which the electron effective mass is orders of magnitude larger than the bare electron mass) have provided the clearest evidence for these continuous phase transitions, which are controlled by such parameters as chemical composition, magnetic field, and pressure, rather than temperature. A new study of a europium-based compound by an international team led by researchers from the Technische Universität Dresden in Germany hints that this compound could join well-known compounds of cerium, ytterbium, and uranium as a new material suitable for research on quantum critical transitions. This finding is exciting, since physicists hope that the use of a new material will give an additional degree of freedom for researching quantum critical behavior.

399

Towards Heavy Fermions in Europium Intermetallic Compounds  

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

Towards Heavy Fermions in Europium Intermetallic Compounds Print Towards Heavy Fermions in Europium Intermetallic Compounds Print For decades, intermetallic compounds of rare-earth metals have been favorite systems of the research community studying strong electron correlations in solids. Nowadays rare-earth intermetallics are often treated as model systems for studies of zero-temperature quantum critical phase transitions, since heavy-fermion rare-earth compounds (in which the electron effective mass is orders of magnitude larger than the bare electron mass) have provided the clearest evidence for these continuous phase transitions, which are controlled by such parameters as chemical composition, magnetic field, and pressure, rather than temperature. A new study of a europium-based compound by an international team led by researchers from the Technische Universität Dresden in Germany hints that this compound could join well-known compounds of cerium, ytterbium, and uranium as a new material suitable for research on quantum critical transitions. This finding is exciting, since physicists hope that the use of a new material will give an additional degree of freedom for researching quantum critical behavior.

400

Heavy Traffic Analysis for EDF Queues with  

E-Print Network (OSTI)

This paper presents a heavy-traffic analysis of the behavior of a single-server queue under an Earliest-Deadline-First (EDF) scheduling policy, in which customers have deadlines and are served only until their deadlines elapse. The performance of the system is measured by the fraction of reneged work (the residual work lost due to elapsed deadlines), which is shown to be minimized by the EDF policy. The evolution of the lead time distribution of customers in queue is described by a measure-valued process. The heavy traffic limit of this (properly scaled) process is shown to be a deterministic function of the limit of the scaled workload process, which, in turn, is identified to be a doubly reflected Brownian motion. This paper complements previous work by Doytchinov, Lehoczky and Shreve on the EDF discipline, in which customers are served to completion even after their deadlines elapse. The fraction of reneged work in a heavily loaded system and the fraction of late work in the corresponding system without reneging are compared using explicit formulas based on the heavy

John Lehoczky; Kavita Ramanan; Steven Shreve

2007-01-01T23:59:59.000Z

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401

HEAVY AND THERMAL OIL RECOVERY PRODUCTION MECHANISMS  

Science Conference Proceedings (OSTI)

This technical progress report describes work performed from January 1 through March 31, 2003 for the project ''Heavy and Thermal Oil Recovery Production Mechanisms,'' DE-FC26-00BC15311. In this project, a broad spectrum of research is undertaken related to thermal and heavy-oil recovery. The research tools and techniques span from pore-level imaging of multiphase fluid flow to definition of reservoir-scale features through streamline-based history matching techniques. During this period, previous analysis of experimental data regarding multidimensional imbibition to obtain shape factors appropriate for dual-porosity simulation was verified by comparison among analytic, dual-porosity simulation, and fine-grid simulation. We continued to study the mechanisms by which oil is produced from fractured porous media at high pressure and high temperature. Temperature has a beneficial effect on recovery and reduces residual oil saturation. A new experiment was conducted on diatomite core. Significantly, we show that elevated temperature induces fines release in sandstone cores and this behavior may be linked to wettability. Our work in the area of primary production of heavy oil continues with field cores and crude oil. On the topic of reservoir definition, work continued on developing techniques that integrate production history into reservoir models using streamline-based properties.

Anthony R. Kovscek

2003-04-01T23:59:59.000Z

402

HEAVY AND THERMAL OIL RECOVERY PRODUCTION MECHANISMS  

Science Conference Proceedings (OSTI)

This technical progress report describes work performed from October 1 through December 31, 2002 , for the project ''Heavy and Thermal Oil Recovery Production Mechanisms.'' In this project, a broad spectrum of research is undertaken related to thermal and heavy-oil recovery. The research tools and techniques used are varied and span from pore-level imaging of multiphase fluid flow to definition of reservoir-scale features through streamline-based history-matching techniques. During this period, experimental data regarding multidimensional imbibition was analyzed to obtain shape factors appropriate for dual-porosity simulation. It is shown that the usual assumption of constant, time-independent shape factors is incorrect. In other work, we continued to study the mechanisms by which oil is produced from fractured media at high pressure and high temperature. High temperature significantly increased the apparent wettability and affected water relative permeability of cores used in previous experiments. A phenomenological and mechanistic cause for this behavior is sought. Our work in the area of primary production of heavy oil continues with field cores and crude oil. On the topic of reservoir definition, work continued on developing techniques that integrate production history into reservoir models using streamline-based properties.

Anthony R. Kovscek

2003-01-01T23:59:59.000Z

403

Multiple Electron Stripping of Heavy Ion Beams  

DOE Green Energy (OSTI)

One approach being explored as a route to practical fusion energy uses heavy ion beams focused on an indirect drive target. Such beams will lose electrons while passing through background gas in the target chamber, and therefore it is necessary to assess the rate at which the charge state of the incident beam evolves on the way to the target. Accelerators designed primarily for nuclear physics or high energy physics experiments utilize ion sources that generate highly stripped ions in order to achieve high energies economically. As a result, accelerators capable of producing heavy ion beams of 10 to 40 Mev/amu with charge state 1 currently do not exist. Hence, the stripping cross-sections used to model the performance of heavy ion fusion driver beams have, up to now, been based upon theoretical calculations. We have investigated experimentally the stripping of 3.4 Mev/amu Kr 7+ and Xe +11 in N2; 10.2 MeV/amu Ar +6 in He, N2, Ar and Xe; 19 MeV/amu Ar +8 in He, N2, Ar and Xe; 30 MeV He 1 + in He, N2, Ar and Xe; and 38 MeV/amu N +6 in He, N2, Ar and Xe. The results of these measurements are compared with the theoretical calculations to assess their applicability over a wide range of parameters.

D. Mueller; L. Grisham; I. Kaganovich; R. L. Watson; V. Horvat; K. E. Zaharakis; Y. Peng

2002-06-25T23:59:59.000Z

404

Heavy fermions in an optical lattice  

Science Conference Proceedings (OSTI)

We employ a mean-field theory to study ground-state properties and transport of a two-dimensional gas of ultracold alkaline-earth-metal atoms governed by the Kondo lattice Hamiltonian plus a parabolic confining potential. In a homogenous system, this mean-field theory is believed to give a qualitatively correct description of heavy-fermion metals and Kondo insulators: It reproduces the Kondo-like scaling of the quasiparticle mass in the former and the same scaling of the excitation gap in the latter. In order to understand ground-state properties in a trap, we extend this mean-field theory via local-density approximation. We find that the Kondo insulator gap manifests as a shell structure in the trapped density profile. In addition, a strong signature of the large Fermi surface expected for heavy-fermion systems survives the confinement and could be probed in time-of-flight experiments. From a full self-consistent diagonalization of the mean-field theory, we are able to study dynamics in the trap. We find that the mass enhancement of quasiparticle excitations in the heavy-Fermi liquid phase manifests as slowing of the dipole oscillations that result from a sudden displacement of the trap center.

Foss-Feig, Michael [Department of Physics, University of Colorado, Boulder, Colorado 80309 (United States); JILA, Boulder, Colorado 80309 (United States); Hermele, Michael; Gurarie, Victor [Department of Physics, University of Colorado, Boulder, Colorado 80309 (United States); Rey, Ana Maria [Department of Physics, University of Colorado, Boulder, Colorado 80309 (United States); JILA, Boulder, Colorado 80309 (United States); National Institute of Standards and Technology, Boulder, Colorado 80309 (United States)

2010-11-15T23:59:59.000Z

405

Compositional changes in heavy oil steamflood simulators  

E-Print Network (OSTI)

The numerical simulation of heavy oil steamfloods has generally been conducted assuming that the oil is non-volatile. Reservoir simulation has traditionally ignored compositional effect s due to heat and steam and assumed that the hydrocarbon phase is non-volatile. This is equivalent to assuming that the equilibrium ratios, K-values, are zero. In order to properly model the mechanism of steamflooding, however, compositional effects need to be taken into account. In this study, laboratory data including distillation, vapor pressure, steam distillation and viscosity measurements, along with a commercial PVT simulator are used to tune equation-of-state (EOS) and viscosity parameters to properly model the PVT properties of the oil. The Peng-Robinson equation-of-state (PR-EOS) was used for all phase behavior calculations. Viscosity as a function of temperature and composition was modeled with the Pedersen correlation for heavy oils. Once a tuned equation-of-state, compositional fluid description was developed for the heavy oil, one-dimensional numerical simulations of the steamflooding process were performed. These simulations demonstrated the utility of the equation-of-state approach. In addition, it was concluded that compositional effects are essential for the proper modeling of low residual oil saturations seen in the field and the formation of an in-situ solvent bank at the steam-oil interface.

Lolley, Christopher Scott

1995-01-01T23:59:59.000Z

406

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

407

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

408

Bharat Heavy Electricals Ltd BHEL | Open Energy Information  

Open Energy Info (EERE)

Heavy Electricals Ltd BHEL Heavy Electricals Ltd BHEL Jump to: navigation, search Name Bharat Heavy Electricals Ltd. (BHEL) Place New Delhi, Delhi (NCT), India Zip 110049 Sector Biomass, Hydro, Renewable Energy, Solar, Wind energy Product Delhi-based power generation equipment manufacturer in the energy-related/infrastructure sector. The firm is also involved in renewable energy sector- small hydro, solar, biomass and wind. References Bharat Heavy Electricals Ltd. (BHEL)[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Bharat Heavy Electricals Ltd. (BHEL) is a company located in New Delhi, Delhi (NCT), India . References ↑ "Bharat Heavy Electricals Ltd. (BHEL)" Retrieved from

409

High-energy accelerator for beams of heavy ions  

DOE Patents (OSTI)

An apparatus for accelerating heavy ions to high energies and directing the accelerated ions at a target comprises a source of singly ionized heavy ions of an element or compound of greater than 100 atomic mass units, means for accelerating the heavy ions, a storage ring for accumulating the accelerated heavy ions and switching means for switching the heavy ions from the storage ring to strike a target substantially simultaneously from a plurality of directions. In a particular embodiment the heavy ion that is accelerated is singly ionized hydrogen iodide. After acceleration, if the beam is of molecular ions, the ions are dissociated to leave an accelerated singly ionized atomic ion in a beam. Extraction of the beam may be accomplished by stripping all the electrons from the atomic ion to switch the beam from the storage ring by bending it in magnetic field of the storage ring.

Martin, Ronald L. (La Grange, IL); Arnold, Richard C. (Chicago, IL)

1978-01-01T23:59:59.000Z

410

Sequential fissions of heavy nuclear systems  

E-Print Network (OSTI)

In Xe+Sn central collisions from 12 to 20 MeV/A measured with the INDRA 4$\\pi$ multidetector, the three-fragment exit channel occurs with a significant cross section. In this contribution, we show that these fragments arise from two successive binary splittings of a heavy composite system. Strong Coulomb proximity effects are observed in the three-fragment final state. By comparison with Coulomb trajectory calculations, we show that the time scale between the consecutive break-ups decreases with increasing bombarding energy, becoming compatible with quasi-simultaneous multifragmentation above 18 MeV/A.

Diego Gruyer; J. D. Frankland; E. Bonnet; M. Boisjoli; A. Chbihi; L. Manduci; P. Marini; K. Mazurek; P. N. Nadtochy

2013-08-24T23:59:59.000Z

411

Heavy Flavor Simplified Models at the LHC  

Science Conference Proceedings (OSTI)

We consider a comprehensive set of simplified models that contribute to final states with top and bottom quarks at the LHC. These simplified models are used to create minimal search strategies that ensure optimal coverage of new heavy flavor physics involving the pair production of color octets and triplets. We provide a set of benchmarks that are representative of model space, which can be used by experimentalists to perform their own optimization of search strategies. For data sets larger than 1 fb{sup -1}, same-sign dilepton and 3b search regions become very powerful. Expected sensitivities from existing and optimized searches are given.

Essig, Rouven; /YITP, Stony Brook /Princeton, Inst. Advanced Study /SLAC; Izaguirre, Eder; /SLAC /Stanford U., Phys. Dept.; Kaplan, Jared; Wacker, Jay G.; /SLAC

2012-04-03T23:59:59.000Z

412

Phenomenology of heavy vector-like leptons  

E-Print Network (OSTI)

We study the impact that a heavy generation of vector-like leptons can have on the value of the electric dipole moment of the electron, and the rates for the flavor violating processes mu --> e gamma and mu --> 3e. The smallness of the charged lepton masses suggests that at least some of the Yukawa coupling constants of the vector-like leptons to the ordinary leptons or amongst themselves are small, but even with such small couplings experiments trying to detect these quantities are sensitive to extra generation lepton masses up to about 100 TeV.

Koji Ishiwata; Mark B. Wise

2013-07-03T23:59:59.000Z

413

HEAVY WATER COMPONENTS TEST REACTOR DECOMMISSIONING  

Science Conference Proceedings (OSTI)

The Heavy Water Components Test Reactor (HWCTR) Decommissioning Project was initiated in 2009 as a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) Removal Action with funding from the American Recovery and Reinvestment Act (ARRA). This paper summarizes the history prior to 2009, the major D&D activities, and final end state of the facility at completion of decommissioning in June 2011. The HWCTR facility was built in 1961, operated from 1962 to 1964, and is located in the northwest quadrant of the Savannah River Site (SRS) approximately three miles from the site boundary. The HWCTR was a pressurized heavy water test reactor used to develop candidate fuel designs for heavy water power reactors. In December of 1964, operations were terminated and the facility was placed in a standby condition as a result of the decision by the U.S. Atomic Energy Commission to redirect research and development work on heavy water power reactors to reactors cooled with organic materials. For about one year, site personnel maintained the facility in a standby status, and then retired the reactor in place. In the early 1990s, DOE began planning to decommission HWCTR. Yet, in the face of new budget constraints, DOE deferred dismantlement and placed HWCTR in an extended surveillance and maintenance mode. The doors of the reactor facility were welded shut to protect workers and discourage intruders. In 2009 the $1.6 billion allocation from the ARRA to SRS for site footprint reduction at SRS reopened the doors to HWCTR - this time for final decommissioning. Alternative studies concluded that the most environmentally safe, cost effective option for final decommissioning was to remove the reactor vessel, both steam generators, and all equipment above grade including the dome. The transfer coffin, originally above grade, was to be placed in the cavity vacated by the reactor vessel and the remaining below grade spaces would be grouted. Once all above equipment including the dome was removed, a concrete cover was to be placed over the remaining footprint and the groundwater monitored for an indefinite period to ensure compliance with environmental regulations.

Austin, W.; Brinkley, D.

2011-10-13T23:59:59.000Z

414

Diamond Detectors for Heavy Ion Measurements  

E-Print Network (OSTI)

In 1999, the accelerator facility at GSI is scheduled to deliver beam intensities of about 10 10 particles/spill for all available ions up to 238 U. This necessitates the development of a new generation of radiation-resistant and ultra-fast detectors, in conjunction with new high-speed and low-noise electronics. Preliminary results confirm the suitability of CVD-diamond detectors for both, beam diagnostics, and heavy-ion experiments with projectiles in the energy region from 50 MeV/amu to 2 GeV/amu. Various test measurements

E. Berdermann; K. Blasche; P. Moritz; H. Stelzer; F. Zeytouni

1998-01-01T23:59:59.000Z

415

DOE - Office of Legacy Management -- Heavy Minerals Inc - IL...  

Office of Legacy Management (LM)

Subject: FUSRAP Considered Site Recommendation; July 9, 1990. IL.14-2 - Heavy Minerals Co. Letter; Wyatt to Faulkner; Subject: Crude Thorium Hydroxide Proposal; December 1, 1954...

416

Characterization of Heavy Clay Ceramic Mixed with Red Mud Waste  

Science Conference Proceedings (OSTI)

Presentation Title, Characterization of Heavy Clay Ceramic Mixed with Red Mud Waste. Author(s), Carlos Maurício Fontes Vieira, Michelle Pereira Babisk, ...

417

Flavor Physics Data from the Heavy Flavor Averaging Group (HFAG)  

DOE Data Explorer (OSTI)

The Heavy Flavor Averaging Group (HFAG) was established at the May 2002 Flavor Physics and CP Violation Conference in Philadelphia, and continues the LEP Heavy Flavor Steering Group's tradition of providing regular updates to the world averages of heavy flavor quantities. Data are provided by six subgroups that each focus on a different set of heavy flavor measurements: B lifetimes and oscillation parameters, Semi-leptonic B decays, Rare B decays, Unitarity triangle parameters, B decays to charm final states, and Charm Physics.

Heavy Flavor Averaging Group (HFAG)

418

RHIC | Physics of the Relativistic Heavy Ion Collider  

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

The Physics of RHIC Physicists from around the world are using the Relativistic Heavy Ion Collider to explore some of Nature's most basic -- and intriguing -- ingredients and...

419

Heavy Metals Behavior of Municiple Solid Waste Incineration ... - TMS  

Science Conference Proceedings (OSTI)

May 1, 2007 ... Heavy Metals Behavior of Municiple Solid Waste Incineration Bottom Ash with Magnetic Separation by Gi-Chun Han, Nam-Il Um, Kwang-Suk ...

420

Advanced Vehicle Testing Activity - Medium and Heavy Duty Hybrid...  

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

an electric vehicle. Medium and heavy duty HEV testing results to date are posted below. Vehicle Testing Reports INL Hybrid Shuttle Busses INL Hybrid Shuttle Busses INL Hybrid...

Note: This page contains sample records for the topic "heavy naphtha boiling" 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

Using Microwave Radiation for Removing Heavy Metal Ions and ...  

Science Conference Proceedings (OSTI)

Presentation Title, Using Microwave Radiation for Removing Heavy Metal Ions and Producing Biofuels. Author(s), Aharon Gedanken. On-Site Speaker (Planned ) ...

422

The Role of Batteries in Auxiliary Power for Heavy Trucks  

DOE Green Energy (OSTI)

The problem that this paper deals with is that Heavy trucks leave their engines on while they are stopped and the driver is sleeping, eating, etc.

D. Crouch

2001-12-12T23:59:59.000Z

423

Heavy Cycloadditions: Reactions of Diagailene with Cyclic Polyolefins...  

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

We are interested in investigating the interactions of low- * valent Group 13 heavy alkene analogues with a variety of small molecules. To investigate uncatalysed, room...

424

A Distributed Framework for Coordinated Heavy-duty Vehicle ...  

E-Print Network (OSTI)

Dec 28, 2013 ... Abstract: Heavy-duty vehicles traveling in a single file with small intervehicle distances experience a reduced aerodynamic drag and therefore ...

425

METHOD OF OPERATING A HEAVY WATER MODERATED REACTOR  

DOE Patents (OSTI)

A method of removing fission products from the heavy water used in a slurry type nuclear reactor is described. According to the process the slurry is steam distilled with carbon tetrachloride so that at least a part of the heavy water and carbon tetrachloride are vaporized; the heavy water and carbon tetrachloride are separated; the carbon tetrachloride is returned to the steam distillation column at different points in the column to aid in depositing the slurry particles at the bottom of the column; and the heavy water portion of the condensate is purified. (AEC)

Vernon, H.C.

1962-08-14T23:59:59.000Z

426

Mass Transfer Mechanisms during the Solvent Recovery of Heavy Oil.  

E-Print Network (OSTI)

??Canada has the second largest proven oil reserves next to Saudi Arabia which is mostly located in Alberta and Saskatchewan but is unconventional heavy oil… (more)

James, Lesley

2009-01-01T23:59:59.000Z

427

Combination process for the conversion of heavy distillates to LPG  

SciTech Connect

Maximum conversion of heavy distillates to LPG is achieved through a combination process involving two-stage hydrocracking. 9 claims, no drawings.

Hilfman, L.

1976-06-15T23:59:59.000Z

428

FY 2004 Annual Progress Report for Heavy Vehicle Systems Optimization  

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

HEAVY HEAVY VEHICLE SYSTEMS OPTIMIZATION FreedomCAR and Vehicle Technologies Program U.S. Department of Energy FreedomCAR and Vehicle Technologies Program 1000 Independence Avenue, S.W. Washington, D.C. 20585-0121 FY 2004 Annual Progress Report for Heavy Vehicle Systems Optimization Energy Efficiency and Renewable Energy FreedomCAR and Vehicle Technologies Program Approved by Dr. Sidney Diamond Technology Area Development Specialist February 2005 Heavy Vehicle Systems Optimization Program FY 2004 Annual Report iii Contents Foreword by Dr. Sidney Diamond, FreedomCAR and Vehicle Technologies Program, Energy Efficiency and Renewable Energy, U.S. Department of Energy ................................. 1 I. Aerodynamic Drag Reduction......................................................................................................

429

Citation: K. Nakamura et al. (Particle Data Group), JPG 37, 075021 (2010) (URL: http://pdg.lbl.gov) Heavy Neutral Leptons, Searches for  

E-Print Network (OSTI)

://pdg.lbl.gov) Heavy Neutral Leptons, Searches for (A) Heavy Neutral Leptons(A) Heavy Neutral Leptons(A) Heavy Neutral Leptons(A) Heavy Neutral Leptons Stable Neutral Heavy Lepton MASS LIMITSStable Neutral Heavy Lepton MASS LIMITSStable Neutral Heavy Lepton MASS LIMITSStable Neutral Heavy Lepton MASS LIMITS Note that LEP results

430

Citation: J. Beringer et al. (Particle Data Group), PR D86, 010001 (2012) (URL: http://pdg.lbl.gov) Heavy Neutral Leptons, Searches for  

E-Print Network (OSTI)

://pdg.lbl.gov) Heavy Neutral Leptons, Searches for (A) Heavy Neutral Leptons(A) Heavy Neutral Leptons(A) Heavy Neutral Leptons(A) Heavy Neutral Leptons Stable Neutral Heavy Lepton MASS LIMITSStable Neutral Heavy Lepton MASS LIMITSStable Neutral Heavy Lepton MASS LIMITSStable Neutral Heavy Lepton MASS LIMITS Note that LEP results

431

HEAVY AND THERMAL OIL RECOVERY PRODUCTION MECHANISMS  

Science Conference Proceedings (OSTI)

This technical progress report describes work performed from July 1 through September, 2003 for the project ''Heavy and Thermal Oil Recovery Production Mechanisms,'' DE-FC26-00BC15311. In this project, a broad spectrum of research is undertaken related to thermal and heavy-oil recovery. The research tools and techniques span from pore-level imaging of multiphase fluid flow to definition of reservoir-scale features through streamline-based history-matching techniques. During this period, work focused on completing project tasks in the area of multiphase flow and rock properties. The area of interest is the production mechanisms of oil from porous media at high temperature. Temperature has a beneficial effect on oil recovery and reduces residual oil saturation. Work continued to delineate how the wettability of reservoir rock shifts from mixed and intermediate wet conditions to more water-wet conditions as temperature increases. One mechanism for the shift toward water-wet conditions is the release of fines coated with oil-wet material from pore walls. New experiments and theory illustrate the role of temperature on fines release.

Anthony R. Kovscek; Louis M. Castanier

2004-03-01T23:59:59.000Z

432

HEAVY AND THERMAL OIL RECOVERY PRODUCTION MECHANISMS  

SciTech Connect

The Stanford University Petroleum Research Institute (SUPRI-A) conducts a broad spectrum of research intended to help improve the recovery efficiency from difficult to produce reservoirs including heavy oil and fractured low permeability systems. Our scope of work is relevant across near-, mid-, and long-term time frames. The primary functions of the group are to conduct direction-setting research, transfer research results to industry, and educate and train students for careers in industry. Presently, research in SUPRI-A is divided into 5 main project areas. These projects and their goals include: (1) Multiphase flow and rock properties--to develop better understanding of the physics of displacement in porous media through experiment and theory. This category includes work on imbibition, flow in fractured media, and the effect of temperature on relative permeability and capillary pressure. (2) Hot fluid injection--to improve the application of nonconventional wells for enhanced oil recovery and elucidate the mechanisms of steamdrive in low permeability, fractured porous media. (3) Mechanisms of primary heavy oil recovery--to develop a mechanistic understanding of so-called ''foamy oil'' and its associated physical chemistry. (4) In-situ combustion--to evaluate the effect of different reservoir parameters on the insitu combustion process. (5) Reservoir definition--to develop and improve techniques for evaluating formation properties from production information. What follows is a report on activities for the past year. Significant progress was made in all areas.

Anthony R. Kovscek; Louis M. Castanier

2002-09-30T23:59:59.000Z

433

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

434

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

435

Fuel and fuel blending components from biomass derived pyrolysis oil  

DOE Patents (OSTI)

A process for the conversion of biomass derived pyrolysis oil to liquid fuel components is presented. The process includes the production of diesel, aviation, and naphtha boiling point range fuels or fuel blending components by two-stage deoxygenation of the pyrolysis oil and separation of the products.

McCall, Michael J.; Brandvold, Timothy A.; Elliott, Douglas C.

2012-12-11T23:59:59.000Z

436

Platinum-, rhenium-, indium-containing catalysts for conversion of hydrocarbons  

Science Conference Proceedings (OSTI)

A process is described for the catalytic reforming of naphtha-boiling range charge stock at reforming conditions with a catalytic composite comprising: (a) a refractory inorganic oxide; (b) a first uniform dispersion of a platinum component and a rhenium component; (c) a second dispersion of an indium component thereover; (d) a halogen component; and (e) a sulfur component.

Antos, G.J.; Wang, L.

1986-12-16T23:59:59.000Z

437

16. Heavy-Quark and Soft-Collinear Effective Theory 1 16. Heavy-Quark and Soft-Collinear Effective Theory  

E-Print Network (OSTI)

16. Heavy-Quark and Soft-Collinear Effective Theory 1 16. Heavy-Quark and Soft-Collinear Effective the quantum fluctuations of such heavy particles are "integrated out" from the generating functional integral. Beringer et al.(PDG), PR D86, 010001 (2012) (http://pdg.lbl.gov) June 18, 2012 16:19 #12;2 16. Heavy

438

Fuel Oil Prepared by Blending Heavy Oil and Coal Tar  

Science Conference Proceedings (OSTI)

The effect of temperature, harmonic ration, surfactant and shearing to fuel oil prepared by blending heavy oil and coal tar were detailedly studied. The results show that the viscosity of the blended oil increases gradually with the increase of harmonic ... Keywords: coal tar, heavy oil, blending, surfactant

Guojie Zhang; Xiaojie Guo; Bo Tian; Yaling Sun; Yongfa Zhang

2009-10-01T23:59:59.000Z

439

Space-optimal heavy hitters with strong error bounds  

Science Conference Proceedings (OSTI)

The problem of finding heavy hitters and approximating the frequencies of items is at the heart of many problems in data stream analysis. It has been observed that several proposed solutions to this problem can outperform their worst-case guarantees ... Keywords: Frequency estimation, heavy hitters, streaming algorithms

Radu Berinde; Piotr Indyk; Graham Cormode; Martin J. Strauss

2010-11-01T23:59:59.000Z

440

Would Border Carbon Adjustments prevent carbon leakage and heavy industry  

E-Print Network (OSTI)

No 52-2013 Would Border Carbon Adjustments prevent carbon leakage and heavy industry halshs-00870689,version1-7Oct2013 #12;Would Border Carbon Adjustments prevent carbon leakage and heavy The efficiency of unilateral climate policies may be hampered by carbon leakage and competitiveness losses

Recanati, Catherine

Note: This page contains sample records for the topic "heavy naphtha boiling" 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

RECOVERY OF DEGRADED HEAVY WATER AT THE SAVANNAH RIVER PLANT  

SciTech Connect

Information is presented on purification and reconcentration of heavy water at the Savannah River Plant. Process and equipment descriptions, typical operating costs, procedures for control of health hazards, standard analytical methods, and specifications for receipt of degraded heavy water for recovery at the Savannah River Plant are included. (auth)

Scotten, W.C.

1960-07-01T23:59:59.000Z

442

Tons of Heavy Metals in Mill Creek Sediments Heather Freeman  

E-Print Network (OSTI)

with industries. Paper, woolen, flour, and cotton mills, starch factories, slaughterhouses, distilleriesTons of Heavy Metals in Mill Creek Sediments Heather Freeman 8/30/99 Geology Department Advisors: Dr. Kees DeJong Dr. Barry Manyard Dr. David Nash #12;Tons of heavy metals in Mill Creek sediments

Maynard, J. Barry

443

Microscopic Calculation of Fusion: Light to Heavy Systems  

E-Print Network (OSTI)

The density-constrained time-dependent Hartree-Fock (DC-TDHF) theory is a fully microscopic approach for calculating heavy-ion interaction potentials and fusion cross sections below and above the fusion barrier. We discuss recent applications of DC-TDHF method to fusion of light and heavy neutron-rich systems.

A. S. Umar; V. E. Oberacker; J. A. Maruhn; R. Keser

2013-10-02T23:59:59.000Z

444

Abstract This research investigates the requirements for proactive service delivery for heavy industrial equipment  

E-Print Network (OSTI)

Abstract ­ This research investigates the requirements for proactive service delivery for heavy. Keywords: Service contract, heavy industrial equipment, proactive service delivery, reference model. 1 Introduction Manufacturers of heavy industry are increasingly expanding into the service sector, not just

Hsu, Cheng

445

SEARCH FOR NEW YTTERBIUM-BASED HEAVY FERMION COMPOUNDS D. Bollinger, E. Morosan1  

E-Print Network (OSTI)

SEARCH FOR NEW YTTERBIUM-BASED HEAVY FERMION COMPOUNDS D. Bollinger, E on synthesizing Ytterbium-based heavy fermions that we believe will display these transitions compounds containing Ce have been found to be heavy fermions, one

Mellor-Crummey, John

446

Studies in ion source development for application in heavy ion fusion  

E-Print Network (OSTI)

Ion Sources for Heavy Ion Fusion Applications . Ph.D.Sources for Heavy Ion Fusion . Proceedings of the ParticleDevelopment for Heavy Ion Fusion. Wollnik, H. , Optics of

Kapica, Jonathan G.

2004-01-01T23:59:59.000Z

447

Comprehensive study of a heavy fuel oil spill : modeling and analytical approaches to understanding environmental weathering  

E-Print Network (OSTI)

Driven by increasingly heavy oil reserves and more efficient refining technologies, use of heavy fuel oils for power generation is rising. Unlike other refined products and crude oils, a large portion of these heavy oils ...

Lemkau, Karin Lydia

2012-01-01T23:59:59.000Z

448

Helicity Probabilities For Heavy Quark Fragmentation Into Excited Mesons  

E-Print Network (OSTI)

In the fragmentation of a heavy quark into a heavy meson whose light degrees of freedom have angular momentum $3/2$, all the helicity probabilities are completely determined in the heavy quark limit up to a single probability $w_{3/2}$. We point out that this probability depends on the longitudinal momentum fraction $z$ of the meson and on its transverse momentum $p_\\bot$ relative to the jet axis. We calculate $w_{3/2}$ as a function of scaling variables corresponding to $z$ and $p_\\bot$ for the heavy quark limit of the perturbative QCD fragmentation functions for $b$ quark to fragment into $(b \\bar c)$ mesons. In this model, the light degrees of freedom prefer to have their angular momentum aligned transverse to, rather than along, the jet axis. Implications for the production of excited heavy mesons, like $D^{**}$ and $B^{**}$, are discussed.

Tzu Chiang Yuan

1994-07-20T23:59:59.000Z

449

Heavy Oil Consumption Reduction Program (Quebec, Canada) | Department of  

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

Heavy Oil Consumption Reduction Program (Quebec, Canada) Heavy Oil Consumption Reduction Program (Quebec, Canada) Heavy Oil Consumption Reduction Program (Quebec, Canada) < Back Eligibility Commercial Agricultural Industrial Construction Savings Category Solar Buying & Making Electricity Maximum Rebate $5 million per site Program Info Funding Source Government of Quebec State Quebec Program Type Rebate Program Provider Agence de l'efficacité énergétique This program helps heavy oil consumers move toward sustainable development while improving their competitive position by reducing their consumption. Financial assistance is offered to carry out various analyses as well as implement energy efficient measures relating to heavy fuel oil or to switch to other forms of energy containing fewer pollutants, such as natural gas,

450

Bend ductility of tungsten heavy alloys  

SciTech Connect

A bend ductility test is used to indicate the formability of tungsten heavy alloys sheet. The primary test bends a notchless Charpy impact specimen to a bend angle of approximately 100C. This can be augmented by a bend-completion test. Finite element modeling as well as strain-gaged bend specimens elucidate the strain distribution in the specimen as a function of material thickness and bend angle. The bend ductilities of 70%W, 807.W and 90%W alloys are characterized. As expected, decreasing thickness or tungsten content enhances bend ductility. Oxidation is not detrimental; therefore, controlled atmosphere is not required for cooling. The potentially detrimental effects of mechanical working (e.g., rolling, roller-leveling, grit blasting, and peening) and machining (e.g., cutting and sanding) are illustrated.

Gurwell, W.E.; Garnich, M.R.; Dudder, G.B.; Lavender, C.A.

1992-11-01T23:59:59.000Z

451

Heavy Quark Production at the Tevatron  

E-Print Network (OSTI)

Results are presented from four CDF analyses involving heavy quark production in proton-antiproton collisions at center of mass energy 1.96 TeV. The shapes of b-jets are found to be broader than inclusive predictions and broader than both PYTHIA and HERWIG defaults. A measurement of the production cross section for psi(2S) is consistent with Run 1 results and with theoretical predictions associated with parton distribution function energy dependence. The inclusive b-jet production cross section is also consistent with theoretical predictions over six orders of magnitude. The b-bbar differential production cross section is compared to several theoretical models and found to be best described by MC@NLO + JIMMY.

Sally Seidel

2008-08-25T23:59:59.000Z

452

Search for new heavy charged gauge bosons  

SciTech Connect

Additional gauge bosons are introduced in many theoretical extensions to the Standard Model. A search for a new heavy charged gauge boson W{prime} decaying into an electron and a neutrino is presented. The data used in this analysis was taken with the D0 detector at the Fermilab proton-antiproton collider at a center-of-mass energy of 1.96 TeV and corresponds to an integrated luminosity of about 1 fb{sup -1}. Since no significant excess is observed in the data, an upper limit is set on the production cross section times branching fraction {sigma}{sub W{prime}}xBr (W{prime} {yields} e{nu}). Using this limit, a W{prime} boson with mass below {approx}1 TeV can be excluded at the 95% confidence level assuming that the new boson has the same couplings to fermions as the Standard Model W boson.

Magass, Carsten Martin; /RWTH Aachen U.

2007-11-01T23:59:59.000Z

453

HOW LINDE MAKES HEAVY WATER FROM HYDROGEN  

SciTech Connect

A heavy water plant to be operated in conjunction with an ammonium nitrate fertilizer plant is described. Initial electrolytic deuterium enrichment of hydrogen takes place in a three-stage water electrolysis plant. A part of the hydrogen produced for the ammonia synthesis plant is run through the hydrogen distillation plant, the deuterium drained off, and the hydrogen returned. Natural water is used to scrub deuterium from electrolytic hydrogen before feeding to the cells. Contaminants such as water, carbon dioxide, and nitrogen are frozen out, and the purified enriched hydrogen is fractionated following an interim step which catalyzes concentrated HD to an equilibrium mixture of D/sub 2/ , HD, and H/sub 2/. Pure oxygen burns the final fractionation product to water containing 99.8% deuterium oxide. (J.R.D.)

1959-02-23T23:59:59.000Z

454

Langevin dynamics of heavy flavors in relativistic heavy-ion collisions  

E-Print Network (OSTI)

We study the stochastic dynamics of c and b quarks, produced in hard initial processes, in the hot medium created after the collision of two relativistic heavy ions. This is done through the numerical solution of the relativistic Langevin equation. The latter requires the knowledge of the friction and diffusion coefficients, whose microscopic evaluation is performed treating separately the contribution of soft and hard collisions. The evolution of the background medium is described by ideal/viscous hydrodynamics. Below the critical temperature the heavy quarks are converted into hadrons, whose semileptonic decays provide single-electron spectra to be compared with the current experimental data measured at RHIC. We focus on the nuclear modification factor R_AA and on the elliptic-flow coefficient v_2, getting, for sufficiently large p_T, a reasonable agreement.

W. M. Alberico; A. Beraudo; A. De Pace; A. Molinari; M. Monteno; M. Nardi; F. Prino

2010-09-13T23:59:59.000Z

455

Langevin dynamics of heavy flavors in relativistic heavy-ion collisions  

E-Print Network (OSTI)

We study the stochastic dynamics of c and b quarks, produced in hard initial processes, in the hot medium created after the collision of two relativistic heavy ions. This is done through the numerical solution of the relativistic Langevin equation. The latter requires the knowledge of the friction and diffusion coefficients, whose microscopic evaluation is performed treating separately the contribution of soft and hard collisions. The evolution of the background medium is described by ideal/viscous hydrodynamics. Below the critical temperature the heavy quarks are converted into hadrons, whose semileptonic decays provide single-electron spectra to be compared with the current experimental data measured at RHIC. We focus on the nuclear modification factor R_AA and on the elliptic-flow coefficient v_2, getting, for sufficiently large p_T, a reasonable agreement.

Alberico, W M; De Pace, A; Molinari, A; Monteno, M; Nardi, M; Prino, F

2011-01-01T23:59:59.000Z

456

Tetraquark bound states in the heavy-light heavy-light system  

Science Conference Proceedings (OSTI)

A calculation of the interaction potential of a heavy-light heavy-light (HLHL) system in lattice QCD is used to study the existence of tetraquark bound states. The interaction potential of the tetraquark system is calculated on the lattice with 2+1 flavours of dynamical fermions with lattice interpolating fields constructed using colorwave propagators. These propagators provide a new method for constructing all-to-all spatially smeared the interpolating fields, a technique which allows for a better overlap with the ground state wavefunction as well as reduced statistical noise. Lattice HLHL potentials are extracted for 24 distinct channels, and are fit with a phenomenological non-relativistic quark model potential, from which a determination of the existence of bound states is made via numerical solution of the two body radial Schroedinger equation.

Konstantinos Orginos, Zachary Brown

2012-12-01T23:59:59.000Z

457

A Heavy Flavor Tracker for STAR  

Science Conference Proceedings (OSTI)

The STAR Collaboration proposes to construct a state-of-the-art microvertex detector,the Heavy Flavor Tracker (HFT), utilizing active pixel sensors and silicon strip technology. The HFT will significantly extend the physics reach of the STAR experiment for precision measurement of the yields and spectra of particles containing heavy quarks. This will be accomplished through topological identification of D mesons by reconstruction of their displaced decay vertices with a precision of approximately 50 mu m in p+p, d+A, and A+A collisions. The HFT consists of 4 layers of silicon detectors grouped into two sub-systems with different technologies, guaranteeing increasing resolution when tracking from the TPC and the Silicon Strip Detector (SSD) towards the vertex of the collision. The Intermediate Silicon Tracker (IST), consisting of two layers of single-sided strips, is located inside the SSD. Two layers of Silicon Pixel Detector (PIXEL) are inside the IST. The PIXEL detectors have the resolution necessary for a precision measurement of the displaced vertex. The PIXEL detector will use CMOS Active Pixel Sensors (APS), an innovative technology never used before in a collider experiment. The APSsensors are only 50 mu m thick and at a distance of only 2.5 cm from the interaction point. This opens up a new realm of possibilities for physics measurements. In particular, a thin detector (0.28percent radiation length per layer) in STAR makes it possible to do the direct topological reconstruction of open charm hadrons down to very low pT by the identification of the charged daughters of the hadronic decay.

Chasman, C.; Beavis, D.; Debbe, R.; Lee, J.H.; Levine, M.J.; Videbaek, F.; Xu, Z.; Kleinfelder, S.; Li, S.; Cendejas, R.; Huang, H.; Sakai, S.; Whitten, C.; Joseph, J.; Keane, D.; Margetis, S.; Rykov, V.; Zhang, W.M.; Bystersky, M.; Kapitan, J.; Kushpil, V.; Sumbera, M.; Baudot, J.; Hu-Guo, C.; Shabetai, A.; Szelezniak, M.; Winter, M.; Kelsey, J.; Milner, R.; Plesko, M.; Redwine, R.; Simon, F.; Surrow, B.; Van Nieuwenhuizen, G.; Anderssen, E.; Dong, X.; Greiner, L.; Matis, H.S.; Morgan, S.; Ritter, H.G.; Rose, A.; Sichtermann, E.; Singh, R.P.; Stezelberger, T.; Sun, X.; Thomas, J.H.; Tram, V.; Vu, C.; Wieman, H.H.; Xu, N.; Hirsch, A.; Srivastava, B.; Wang, F.; Xie, W.; Bichsel, H.

2008-02-25T23:59:59.000Z

458

Heavy Truck Duty Cycle (HTDC) Project OVERVIEW The Heavy Truck Duty Cycle (HTDC)  

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

(HTDC) Project (HTDC) Project OVERVIEW The Heavy Truck Duty Cycle (HTDC) Project is sponsored by the US Department of Energy's (DOE's) Office of FreedomCar and Vehicle Technologies. The project involves efforts to collect, analyze and archive data and information related to class -8 truck operation in real-world environments. Such data and information will be useful for supporting: energy efficiency technology evaluation efforts, the

459

The Heavy Ion Fusion Science Virtual National Laboratory Status of heavy-ion-beam-driven  

E-Print Network (OSTI)

and fusion Ranges given in table reflect options under study Table 4.1, page 43 of an HIF White Paper.E. Coleman et al., in Proc. of the 2007 Particle Accelerator Conf., Albuquerque, NM, 2007(IEEE catalog# 07CH-see http://videos.komando.com/2008/08/19/water-painting/]. #12;12/7/08 The Heavy Ion Fusion Science Virtual

460

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

Note: This page contains sample records for the topic "heavy naphtha boiling" 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

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

462

Analysis of heavy oils: Method development and application to Cerro Negro heavy petroleum  

Science Conference Proceedings (OSTI)

On March 6, 1980, the US Department of Energy (DOE) and the Ministry of Energy and Mines of Venezuela (MEMV) entered into a joint agreement which included analysis of heavy crude oils from the Venezuelan Orinoco oil belt.The purpose of this report is to present compositional data and describe new analytical methods obtained from work on the Cerro Negro Orinoco belt crude oil since 1980. Most of the chapters focus on the methods rather than the resulting data on Cerro Negro oil, and results from other oils obtained during the verification of the method are included. In addition, published work on analysis of heavy oils, tar sand bitumens, and like materials is reviewed, and the overall state of the art in analytical methodology for heavy fossil liquids is assessed. The various phases of the work included: distillation and determination of routine'' physical/chemical properties (Chapter 1); preliminary separation of >200{degree}C distillates and the residue into acid, base, neutral, saturated hydrocarbon and neutral-aromatic concentrates (Chapter 2); further separation of acid, base, and neutral concentrates into subtypes (Chapters 3-5); and determination of the distribution of metal-containing compounds in all fractions (Chapter 6).

Carbognani, L.; Hazos, M.; Sanchez, V. (INTEVEP, Filial de Petroleos de Venezuela, SA, Caracas (Venezuela)); Green, J.A.; Green, J.B.; Grigsby, R.D.; Pearson, C.D.; Reynolds, J.W.; Shay, J.Y.; Sturm, G.P. Jr.; Thomson, J.S.; Vogh, J.W.; Vrana, R.P.; Yu, S.K.T.; Diehl, B.H.; Grizzle, P.L.; Hirsch, D.E; Hornung, K.W.; Tang, S.Y.

1989-12-01T23:59:59.000Z

463

THE DEVELOPMENT OF HEAVY-ION ACCELERATORS AS DRIVERS FOR INERTIALLY CONFINED FUSION  

E-Print Network (OSTI)

29 The Fission-fusion Hybrid - iii - General DiscussionInteraction in Heavy Ion Fusion BIBLIOGRAPHY HEAVY IONReactor Designs . . . 27 Pure Fusion Power Reactor Tritium

Herrmannsfeldt, W.b.

2010-01-01T23:59:59.000Z

464

Develpoment of a one-meter plasma source for heavy ion beam charge neutralization  

E-Print Network (OSTI)

Heavy Ion Beam Driven Fusion Reactor Study”, KfK-3480,is a possible heavy ion fusion reactor design [1]. The final

2005-01-01T23:59:59.000Z

465

Report of the Ad Hoc Panel on heavy ion facilities  

SciTech Connect

In response to a request from the USAEC, the President of the National Academy of Sciences appointed an Ad Hoc Panel under the NAS-NRC Committee on Nuclear Science to make an intensive study of various aspects of the science and technology involved in heavy ion research in light of the needs of the national program in this field. In particular, the panel was asked to formulate and evaluate various options for the development of heavy ion facilities that would include an appropriate accelerator complex capable of producing heavy ion beams and the ancillary apparatus required for experimental exploitation. Also, the Panel was asked to evaluate the current status and potentialities of the Super HILAC and Bevalac accelerators of the Lawrence Radiation Laboratory, Berkeley. Results of the study are presented. Topics include heavy ions in nuclear physics and chemistry, atomic physics, heavy ions and astro and space physics, materials science and solid state, and biomedicine. The state of the technology related to the choice of a heavy ion accelerator system is reviewed, and the various possible choices are reviewed including the large tandem accelerator, tandem- cyclotron systems, and linear accelerators. The upgrading of existing facilities (Super HILAC, Bevalac, and PPA) is discussed. Cost estimates for various heavy ion facilities are briefly discussed. (WHK)

1974-01-01T23:59:59.000Z

466

Citation: K. Nakamura et al. (Particle Data Group), JPG 37, 075021 (2010) (URL: http://pdg.lbl.gov) Heavy Charged Lepton Searches  

E-Print Network (OSTI)

://pdg.lbl.gov) Heavy Charged Lepton Searches Charged Heavy Lepton MASS LIMITSCharged Heavy Lepton MASS LIMITSCharged Heavy Lepton MASS LIMITSCharged Heavy Lepton MASS LIMITS Sequential Charged Heavy Lepton (L±) MASS LIMITSSequential Charged Heavy Lepton (L±) MASS LIMITSSequential Charged Heavy Lepton (L±) MASS LIMITSSequential

467

Citation: J. Beringer et al. (Particle Data Group), PR D86, 010001 (2012) (URL: http://pdg.lbl.gov) Heavy Charged Lepton Searches  

E-Print Network (OSTI)

://pdg.lbl.gov) Heavy Charged Lepton Searches Charged Heavy Lepton MASS LIMITSCharged Heavy Lepton MASS LIMITSCharged Heavy Lepton MASS LIMITSCharged Heavy Lepton MASS LIMITS Sequential Charged Heavy Lepton (L±) MASS LIMITSSequential Charged Heavy Lepton (L±) MASS LIMITSSequential Charged Heavy Lepton (L±) MASS LIMITSSequential

468

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

469

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

470

Methods for natural gas and heavy hydrocarbon co-conversion  

DOE Patents (OSTI)

A reactor for reactive co-conversion of heavy hydrocarbons and hydrocarbon gases and includes a dielectric barrier discharge plasma cell having a pair of electrodes separated by a dielectric material and passageway therebetween. An inlet is provided for feeding heavy hydrocarbons and other reactive materials to the passageway of the discharge plasma cell, and an outlet is provided for discharging reaction products from the reactor. A packed bed catalyst may optionally be used in the reactor to increase efficiency of conversion. The reactor can be modified to allow use of a variety of light sources for providing ultraviolet light within the discharge plasma cell. Methods for upgrading heavy hydrocarbons are also disclosed.

Kong, Peter C. (Idaho Falls, ID); Nelson, Lee O. (Idaho Falls, ID); Detering, Brent A. (Idaho Falls, ID)

2009-02-24T23:59:59.000Z

471

Inertially confined fusion using heavy ion drivers  

Science Conference Proceedings (OSTI)

The various technical issues of HIF will be briefly reviewed in this paper. It will be seen that there are numerous areas in common in all the approaches to HIF. In the recent International Symposium on Heavy Ion Inertial Fusion, the attendees met in specialized workshop sessions to consider the needs for research in each area. Each of the workshop groups considered the key questions of this report: (1) Is this an appropriate time for international collaboration in HIF (2) Which problems are most appropriate for such collaboration (3) Can the sharing of target design information be set aside until other driver and systems issues are better resolved, by which time it might be supposed that there could be a relaxation of classification of target issues (4) What form(s) of collaboration are most appropriate, e.g., bilateral or multilateral (5) Can international collaboration be sensibly attempted without significant increases in funding for HIF The authors of this report share the conviction that collaboration on a broad scale is mandatory for HIF to have the resources, both financial and personnel, to progress to a demonstration experiment. Ultimately it may be possible for a single driver with the energy, power, focusibility, and pulse shape to satisfy the needs of the international community for target physics research. Such a facility could service multiple experimental chambers with a variety of beam geometries and target concepts.

Herrmannsfeldt, W.B. (Stanford Linear Accelerator Center, Menlo Park, CA (United States)); Bangerter, R.O. (Lawrence Berkeley Lab., CA (United States)); Bock, R. (Gesellschaft fuer Schwerionenforschung mbH, Darmstadt (Germany)); Hogan, W.J.; Lindl, J.D. (Lawrence Livermore National Lab., CA (United States))

1991-10-01T23:59:59.000Z

472

Inertially confined fusion using heavy ion drivers  

Science Conference Proceedings (OSTI)

The various technical issues of HIF will be briefly reviewed in this paper. It will be seen that there are numerous areas in common in all the approaches to HIF. In the recent International Symposium on Heavy Ion Inertial Fusion, the attendees met in specialized workshop sessions to consider the needs for research in each area. Each of the workshop groups considered the key questions of this report: (1) Is this an appropriate time for international collaboration in HIF? (2) Which problems are most appropriate for such collaboration? (3) Can the sharing of target design information be set aside until other driver and systems issues are better resolved, by which time it might be supposed that there could be a relaxation of classification of target issues? (4) What form(s) of collaboration are most appropriate, e.g., bilateral or multilateral? (5) Can international collaboration be sensibly attempted without significant increases in funding for HIF? The authors of this report share the conviction that collaboration on a broad scale is mandatory for HIF to have the resources, both financial and personnel, to progress to a demonstration experiment. Ultimately it may be possible for a single driver with the energy, power, focusibility, and pulse shape to satisfy the needs of the international community for target physics research. Such a facility could service multiple experimental chambers with a variety of beam geometries and target concepts.

Herrmannsfeldt, W.B. [Stanford Linear Accelerator Center, Menlo Park, CA (United States); Bangerter, R.O. [Lawrence Berkeley Lab., CA (United States); Bock, R. [Gesellschaft fuer Schwerionenforschung mbH, Darmstadt (Germany); Hogan, W.J.; Lindl, J.D. [Lawrence Livermore National Lab., CA (United States)

1991-10-01T23:59:59.000Z

473

Heavy Ion Physics at the ATLAS Detector  

E-Print Network (OSTI)

The ATLAS detector is one of the two large detectors built to carry on high pT physics  at the Large Hadron Collider. The detector is designed to perform optimally at the challenging nominal LHC machine luminosity of 10^34 cm-2s-1. ATLAS has a finely segmented electromagnetic and hadronic calorimeters covering 10 units of rapidity. The inner tracking system is composed of  sicilicon pixel detector, silicon central tracker, transition radiation tracker and a 2T solenoidal magnet, covering 5 units of rapidity. The muon spectrometer is located outside the calorimeter volume. Muon chambers and air core toroids are used to track muons of momentum larger than 4 GeV.  The ATLAS detector has a superb performance for jet physics because of its calorimeters. Simulation studies also indicate that it will be possible to tag b-jets in the heavy ion environment. Upsilon and J/Psi can be reconstructed through the di-muon decay channel. The detector is ideal for the study of global variables, namely total energy flow and ...

Takai, H; The ATLAS collaboration

2009-01-01T23:59:59.000Z

474

Recent PQCD calculations of heavy quark production  

E-Print Network (OSTI)

We summarize the results of a recent study of heavy quark production and attenuation in cold nuclear matter. In p+p collisions, we investigate the relative contribution of partonic sub-processes to $D$ meson production and $D$ meson-triggered inclusive di-hadrons to lowest order in perturbative QCD. While gluon fusion dominates the creation of large angle $D\\bar{D}$ pairs, charm on light parton scattering determines the yield of single inclusive $D$ mesons. The distinctly different non-perturbative fragmentation of $c$ quarks into $D$ mesons versus the fragmentation of quarks and gluons into light hadrons results in a strong transverse momentum dependence of anticharm content of the away-side charm-triggered jet. In p+A reactions, we calculate and resum the coherent nuclear-enhanced power corrections from the final-state partonic scattering in the medium. We find that single and double inclusive open charm production can be suppressed as much as the yield of neutral pions from dynamical high-twist shadowing. Effects of energy loss in p+A collisions are also investigated in the incoherent Bertsch-Gunion limit and may lead to significantly weaker transverse momentum dependence of the nuclear attenuation.

Ivan Vitev

2006-05-30T23:59:59.000Z

475

Heavy flavor in heavy-ion collisions at RHIC and RHIC II  

E-Print Network (OSTI)

In the initial years of operation, experiments at the Relativistic Heavy Ion Collider (RHIC) have identified a new form of matter formed in nuclei-nuclei collisions at energy densities more than 100 times that of a cold atomic nucleus. Measurements and comparison with relativistic hydrodynamic models indicate that the matter thermalizes in an unexpectedly short time, has an energy density at least 15 times larger than needed for color deconfinement, has a temperature about twice the critical temperature predicted by lattice QCD, and appears to exhibit collective motion with ideal hydrodynamic properties - a "perfect liquid" that appears to flow with a near-zero viscosity to entropy ratio - lower than any previously observed fluid and perhaps close to a universal lower bound. However, a fundamental understanding of the medium seen in heavy-ion collisions at RHIC does not yet exist. The most important scientific challenge for the field in the next decade is the quantitative exploration of the new state of nuclear matter. That will require new data that will, in turn, require enhanced capabilities of the RHIC detectors and accelerator. In this report we discuss the scientific opportunities for an upgraded RHIC facility - RHIC II - in conjunction with improved capabilities of the two large RHIC detectors, PHENIX and STAR. We focus solely on heavy flavor probes. Their production rates are calculable using the well-established techniques of perturbative QCD and their sizable interactions with the hot QCD medium provide unique and sensitive measurements of its crucial properties making them one of the key diagnostic tools available to us.

A. D. Frawley; T. Ullrich; R. Vogt

2008-06-05T23:59:59.000Z

476

NETL: Oil & Natural Gas Projects: Alaska Heavy Oils  

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

Fluid and Rock Property Controls On Production and Seismic Monitoring Alaska Heavy Oils Last Reviewed 12/20/2012 Fluid and Rock Property Controls On Production and Seismic Monitoring Alaska Heavy Oils Last Reviewed 12/20/2012 DE-NT0005663 Goal The goal of this project is to improve recovery of Alaskan North Slope (ANS) heavy oil resources in the Ugnu formation by improving our understanding of the formationÂ’s vertical and lateral heterogeneities via core evaluation, evaluating possible recovery processes, and employing geophysical monitoring to assess production and modify production operations. Performers Colorado School of Mines, Golden, CO 80401 University of Houston, Houston, TX 77204 Earthworks, Newtown, CT 06470 BP, Anchorage, AK 99519 Background Although the reserves of heavy oil on the North Slope of Alaska are enormous (estimates are up to 10 billion barrels in place), difficult

477

Heavy Liquid Metal Reactor Development - Nuclear Engineering Division  

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

> Heavy Liquid Metal Reactor Development > Heavy Liquid Metal Reactor Development Capabilities Nuclear Systems Modeling and Design Analysis Reactor Physics and Fuel Cycle Analysis Nuclear Data Program Advanced Reactor Development Overview Advanced Fast Reactor (AFR) Heavy Liquid Metal Reactor Development Generation IV Nuclear Waste Form and Repository Performance Modeling Nuclear Energy Systems Design and Development Other Capabilities Work with Argonne Contact us For Employees Site Map Help Advanced Reactor Development and Technology Heavy Liquid Metal Reactor Development Bookmark and Share STAR-LM: Simplified, Modular, Small Reactor Featuring Flow-thru Fuel Cartridge STAR-LM: Simplified, Modular, Small Reactor Featuring Flow-thru Fuel Cartridge. Click on image to view larger image. Argonne has traditionally been the foremost institute in the US for

478

Heavy-ion Accelerators for Testing Microelectronic Components at LBNL |  

Office of Science (SC) Website

Heavy-ion Accelerators for Testing Heavy-ion Accelerators for Testing Microelectronic Components at LBNL Nuclear Physics (NP) NP Home About Research Facilities Science Highlights Benefits of NP Spinoff Applications Spinoff Archives SBIR/STTR Applications of Nuclear Science and Technology Funding Opportunities Nuclear Science Advisory Committee (NSAC) News & Resources Contact Information Nuclear Physics U.S. Department of Energy SC-26/Germantown Building 1000 Independence Ave., SW Washington, DC 20585 P: (301) 903-3613 F: (301) 903-3833 E: sc.np@science.doe.gov More Information » Spinoff Archives Heavy-ion Accelerators for Testing Microelectronic Components at LBNL Print Text Size: A A A RSS Feeds FeedbackShare Page Application/instrumentation: Use of heavy-ion accelerators for testing microelectronic components for

479

Sandia National Labs: PCNSC: Heavy Ion Backscattering Spectrometry  

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

Heavy Ion Backscattering Spectrometry (HIBS) Heavy Ion Backscattering Spectrometry (HIBS) IBA Table (HTML) | IBA Table (135KB GIF) | IBA Table (1.2MB PDF) | IBA Table (33MB TIF) | Heavy Ion Backscattering Spectrometry (HIBS) | Virtual Lab Tour (6MB) Description of Technique: HIBS is used to detect ultra-trace levels of heavy impurities on the surface of a Si wafer. HIBS has advantages over TXRF, including: Improved sensitivity for most elements Quantifying composition without standards Measurement on rough surfaces. HIBS is accomplished by focusing a 120 keV beam of C+ions onto a small spot at the wafer's surface. The backscattered ions are collected by a time-of-flight (TOF) detector array with a large solid angle. The flight time of the backscattered C identifies the near-surface impurities and the

480

Brookhaven National Laboratory The Relativistic Heavy Ion Collider (RHIC)  

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

Relativistic Heavy Ion Collider (RHIC) Relativistic Heavy Ion Collider (RHIC) An Exciting Beginning and a Compelling Future At the Relativistic Heavy Ion Collider (RHIC), a world-class particle accelerator at Brookhaven National Laboratory, physicists are exploring the most fundamental forces and properties of matter and the early universe, with important implications for our understanding of the world around us. Operated with funding from the U.S. Department of Energy's Office of Science, the Relativistic Heavy Ion Collider (RHIC), was designed to recreate a state of matter thought to have existed immediately after the Big Bang some 13 billion years ago, and to investigate how the proton gets its spin and intrinsic magnetism from its quark and gluon constituents. Large detectors located

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481

2007 Heavy Vehicle Systems Optimization Program Annual Report  

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

HEAVY VEHiclE SYSTEMS HEAVY VEHiclE SYSTEMS OPTiMiZATiON PROGRAM V EH icl E T E c HNO l OG i ES P ROGRAM Less dependence on foreign oil today, and transition to a petroleum-free, emissions-free vehicle tomorrow. 2 0 0 7 a n n u a l p r o g r e s s r e p o r t U.S. Department of Energy Vehicle Technologies Program 1000 Independence Avenue, S.W. Washington, DC 20585-0121 FY 2007 Annual Progress Report for Heavy Vehicle Sys