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Note: This page contains sample records for the topic "naph tha 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

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

2

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

3

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...

Sriraman, Sharan Ram

2009-05-15T23:59:59.000Z

4

Boiling Radial Flow in Fractures of Varying  

E-Print Network [OSTI]

the surface, within the matrix. The depth of boiling was a function of injection rate, thermal power supplied 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

Stanford University

5

PACCAR CRADA: Experimental Investigation in Coolant Boiling in...  

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

PACCAR CRADA: Experimental Investigation in Coolant Boiling in a Half-Heated Circular Tube PACCAR CRADA: Experimental Investigation in Coolant Boiling in a Half-Heated Circular...

6

CRADA with PACCAR Experimental Investigation in Coolant Boiling...  

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

PACCAR Experimental Investigation in Coolant Boiling in a Half-Heated Circular Tube CRADA with PACCAR Experimental Investigation in Coolant Boiling in a Half-Heated Circular Tube...

7

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

8

Void volumes in subcooled boiling systems  

E-Print Network [OSTI]

Introduction: Knowledge of the pressure drop in a channel and the resulting flow redistribution is essential in predicting the performance of a nuclear reactor. The pressure drop in a channel which is experiencing boiling ...

Griffith, P.

1958-01-01T23:59:59.000Z

9

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

10

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

11

Pool boiling on nano-finned surfaces  

E-Print Network [OSTI]

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...). .................................................................................................68 Fig. 19. Plots comparing the heat flux through the enhanced test surfaces (qw”) with the heat flux through the bare test surface (qb”) under 10 °C sub-cooling condition for both nulceate and film boiling regimes. Heat flux data...

Sriraman, Sharan Ram

2008-10-10T23:59:59.000Z

12

Boiling water reactor control rod  

SciTech Connect (OSTI)

This patent describes a control rod for a boiling water type nuclear power reactor, the improvement comprising: (a) an elongated central stem defining a longitudinally extending internal central gas plenum; (b) blades connected to and extending along and radially outward from the stem, each blade including an elongated body portion extending along the stem and terminating in an end tip portion; (c) means defining a series of internal cavities in each of the blades, the cavities being arranged in columns and rows across the length and width of the body and tip portions of the blade; (d) pellets of neutron absorbing material, each disposed within one of the cavities with each of the cavities being oversized in relation to the size of the pellet disposed therein to allow extra space for swelling of the pellet. The cavities and the pellets disposed therein are arranged to define a longer, constant worth section generally coextensive with the body portion of the blade and a shorter, reduced worth section generally coextensive with the end tip portion of the blade; and (e) means defined within each blade communicating each of the cavities with the central gas plenum for allowing any gases generated by irradiation of the pellets to expand from the cavities into the plenum.

Wilson, J.F.; Doshi, P.K.

1986-12-23T23:59:59.000Z

13

Lattice Boltzmann modeling of boiling heat transfer: The boiling curve and the effects of wettability  

E-Print Network [OSTI]

A hybrid thermal lattice Boltzmann (LB) model is presented to simulate thermal multiphase flows with phase change based on an improved pseudopotential LB approach [Q. Li, K. H. Luo, and X. J. Li, Phys. Rev. E 87, 053301 (2013)]. The present model does not suffer from the spurious term caused by the forcing-term effect, which was encountered in some previous thermal LB models for liquid-vapor phase change. Using the model, the liquid-vapor boiling process is simulated. The boiling curve together with the three boiling stages (nucleate boiling, transition boiling, and film boiling) is numerically reproduced in the LB community for the first time. The numerical results show that the basic features and the fundamental characteristics of boiling heat transfer are well captured, such as the severe fluctuation of transient heat flux in the transition boiling and the feature that the maximum heat transfer coefficient lies at a lower wall superheat than that of the maximum heat flux. Furthermore, the effects of the he...

Li, Q; Francois, M M; He, Y L; Luo, K H

2015-01-01T23:59:59.000Z

14

E-Print Network 3.0 - automatic boiling water Sample Search Results  

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

boiling water Search Powered by Explorit Topic List Advanced Search Sample search results for: automatic boiling water Page: << < 1 2 3 4 5 > >> 1 Numerical Simulation of Boiling...

15

Genome Sequence of the Deltaproteobacterial Strain NaphS2 and Analysis of  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFun with Big Sky Learning Fun withGenepoolCrystals.Genome GenomeDifferential Gene

16

Hydrodynamics and heat transfer during flow boiling instabilities in a single microchannel  

E-Print Network [OSTI]

Hydrodynamics and heat transfer during flow boiling instabilities in a single microchannel July 2008 Keywords: Boiling Microchannels Visualisation Flow boiling instabilities Heat transfer a b intensification heat removal. Flow boiling heat transfer in microchannel geometry and the associated flow

Aussillous, Pascale

17

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

18

Boiling and condensation in a liquid-filled enclosure  

E-Print Network [OSTI]

A combined experimental and analytical investigation of boiling and condensation in a liquid-filled enclosure, with water and Freon- 113 as the working fluids, is described. The operating characteristics of a boiling system, ...

Bar-Cohen Avram

1971-01-01T23:59:59.000Z

19

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

E-Print Network [OSTI]

using boiling heat transfer, it opens up a new direction forusing boiling heat transfer. This opens up a new direction

Lu, Ming-Chang

2010-01-01T23:59:59.000Z

20

PNNL Enhanced Pool-Boiling Heat Transfer Using Nanostructured Surfaces  

ScienceCinema (OSTI)

Close-up video of boiling taking place on a nanostructured surface in a controlled laboratory experiment.

None

2012-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "naph tha 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

Boiling of nuclear liquid in the micro-canonical ensemble  

E-Print Network [OSTI]

-dependence of the nuclear symmetry energy and the critical temperature of 1 #12;Boiling of nuclear liquid in the microBoiling of nuclear liquid in the micro-canonical ensemble K. Miyazaki E-mail: miyazakiro@rio.odn.ne.jp Abstract New calculus of the liquid-gas phase transition is developed for the boiling of nuclear liquid

22

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

23

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

24

Boiling heat transfer in a vertical microchannel: Local estimation during flow boiling with a non intrusive method  

E-Print Network [OSTI]

Boiling heat transfer in a vertical microchannel: Local estimation during flow boiling with a non the results of experimental and numerical studies concerning boiling heat transfer inside vertical in minichannels for several gravity levels (µg, 1g, 2g). To fully understand the high heat transfer potential

25

Operational control of boiling water reactor stability  

SciTech Connect (OSTI)

Boiling water reactor cores are susceptible to instabilities, which generate power oscillations. Specific reactor operating practices can provide a mechanism for control of the instability phenomenon. An axial separation of the core into a single-phase region and a two-phase region resolves the influence of axial flux shapes on core stability. This separation provides the means to derive a core stability control that ensures significant reactor stability margin. The control is achieved by maintaining the core average bulk coolant saturation elevation above a predetermined axial plane. The control can be reliably and efficiently implemented during reactor operations. Analysis demonstrates that variations in parameters important to stability have only secondary influences on stability margin when the control is in effect. Actual plant experience with a large commercial boiling water reactor confirms the capabilities of this stability control in an operational setting.

Mowry, C.M. [PECO Energy, Wayne, PA (United States); Nir, I. [Entergy Operations, Jackson, MS (United States); Newkirk, D.W. [GE Nuclear Energy, San Jose, CA (United States)

1995-03-01T23:59:59.000Z

26

actual coolant boiling: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

27

abwr advanced boiling: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

28

advanced boiling curve: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

29

A TEN MEGAWATT BOILING HETEROGENEOUS PACKAGE POWER REACTOR. Reactor...  

Office of Scientific and Technical Information (OSTI)

A TEN MEGAWATT BOILING HETEROGENEOUS PACKAGE POWER REACTOR. Reactor Design and Feasibility Problem Re-direct Destination: Temp Data Fields Rosen, M. A.; Coburn, D. B.; Flynn, T....

30

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

31

EXPERIMENTAL INVESTIGATION OF BOILING HEAT CONVECTION IN A FRACTURE  

E-Print Network [OSTI]

EXPERIMENTAL INVESTIGATION OF BOILING HEAT CONVECTION IN A FRACTURE A REPORT SUBMITTED between heat conduction and heat convection with boiling flow in a rock fracture. An experimental coefficient. This coefficient is the proportionality factor between the heat flux to a fracture surface

Stanford University

32

Little low-power boiling never hurt anybody. [LMFBR  

SciTech Connect (OSTI)

Failures in the shutdown heat removal system of an LMFBR might lead to flow stagnation and coolant boiling in the reactor core. At normal operating power, the onset of sodium boiling will lead to film dryout and melting of the cladding and fuel within a few seconds. On the other hand, both calculations and currently available experimental data indicate that at heat fluxes corresponding to decay heat power levels, boiling leads to improved heat removal; and it limits the temperature rise in the fuel pins. Therefore, when setting safety criteria for decay heat removal systems, there is no reason to preclude sodium boiling per se because of heat removal considerations. As an example that illustrates the beneficial impact of coolant boiling, a case involving temporary loss of feedwater and staggered pump failures in a hypothetical, 1000-MWe loop-type reactor was run in the SASSYS-1 code.

Dunn, F.E.

1985-01-01T23:59:59.000Z

33

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

34

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

35

Suppression and Enhancement of Boiling Associated with Multiple Droplet Impingement  

E-Print Network [OSTI]

are at play simultaneously. Furthermore, experiments with single streams of droplets have not been able to elucidate the effects of the onset of boiling (ONB) during the droplet impingement process. Therefore, efforts have been undertaken to consider...

Yang, Yuxuan

2014-05-01T23:59:59.000Z

36

Pool boiling studies on nanotextured surfaces under highly subcooled conditions  

E-Print Network [OSTI]

Subcooled pool boiling on nanotextured surfaces is explored in this study. The experiments are performed in an enclosed viewing chamber. Two silicon wafers are coated with Multiwalled Carbon Nanotubes (MWCNT), 9 microns (Type-A) and 25 microns (Type...

Sathyamurthi, Vijaykumar

2009-05-15T23:59:59.000Z

37

Hydrodynamics, heat transfer and flow boiling instabilities in microchannels   

E-Print Network [OSTI]

Boiling in microchannels is a very efficient mode of heat transfer with high heat and mass transfer coefficients achieved. Less pumping power is required for two-phase flows than for single-phase liquid flows to achieve ...

Barber, Jacqueline Claire

2010-01-01T23:59:59.000Z

38

Determination of pool boiling Critical Heat Flux enhancement in nanofluids  

E-Print Network [OSTI]

Nanofluids are engineered colloids composed of nano-size particles dispersed in common fluids such as water or refrigerants. Using an electrically controlled wire heater, pool boiling Critical Heat Flux (CHF) of Alumina ...

Truong, Bao H. (Bao Hoai)

2007-01-01T23:59:59.000Z

39

Thermal boundary layer development in dispersed flow film boiling  

E-Print Network [OSTI]

Dispersed flow film boiling consists of a dispersion of droplets which are carried over a very hot surface by their vapor. This process occurs in cryogenic equipment and wet steam turbines. It is also of interest in the ...

Hull, Lawrence M.

1982-01-01T23:59:59.000Z

40

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

Note: This page contains sample records for the topic "naph tha 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

The effects of surface conditions on boiling characteristics  

E-Print Network [OSTI]

A unified model relating surface variables to the nucleate pool boiling characteristics was developed. A simple vapor trapping mechanism was postulated and a geometrical model constructed for idealized conical cavities ...

Lorenz, J. J.

1972-01-01T23:59:59.000Z

42

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

43

Film Boiling on Downward Quenching Hemisphere of Varying Sizes  

SciTech Connect (OSTI)

Film boiling heat transfer coefficients for a downward-facing hemispherical surface are measured from the quenching tests in DELTA (Downward-boiling Experimental Laminar Transition Apparatus). Two test sections are made of copper to maintain low Biot numbers. The outer diameters of the hemispheres are 120 mm and 294 mm, respectively. The thickness of all the test sections is 30 mm. The effect of diameter on film boiling heat transfer is quantified utilizing results obtained from the test sections. The measured data are compared with the numerical predictions from laminar film boiling analysis. The measured heat transfer coefficients are found to be greater than those predicted by the conventional laminar flow theory on account of the interfacial wavy motion incurred by the Helmholtz instability. Incorporation of the wavy motion model considerably improves the agreement between the experimental and numerical results in terms of heat transfer coefficient. In addition, the interfacial wavy motion and the quenching process are visualized through a digital camera.

Chan S. Kim; Kune Y. Suh; Joy L. Rempe; Fan-Bill Cheung; Sang B. Kim

2004-04-01T23:59:59.000Z

44

Pressure drop with surface boiling in small-diameter tubes  

E-Print Network [OSTI]

Pressure drop for water flowing in small-diameter tubes under isothermal, nonboiling, and surface-boiling conditions was investigated. Experimental results for local pressure gradient and heattransfer coefficients are ...

Dr?mer, Thomas

1964-01-01T23:59:59.000Z

45

A study of boiling water flow regimes at low pressures  

E-Print Network [OSTI]

"A comprehensive experimental program to examine flow regimes at pressures below 100 psia for boiling of water in tubes was carried out. An electrical probe, which measures the resistance of the fluid between the centerline ...

Fiori, Mario P.

1966-01-01T23:59:59.000Z

46

Infrared thermometry study of nanofluid pool boiling phenomena  

E-Print Network [OSTI]

Abstract Infrared thermometry was used to obtain first-of-a-kind, time- and space-resolved data for pool boiling phenomena in water-based nanofluids with diamond and silica nanoparticles at low concentration (<0.1 vol.%). ...

Gerardi, Craig

47

Experimental design for study of nucleate boiling in porous structures  

E-Print Network [OSTI]

The superheat required to initiate nucleate boiling inside porous wicks is not well understood in practice. This thesis reports the design of an experimental setup for investigating the onset of vapor nucleation in sintered ...

Kelley, Mitchell Joseph

2011-01-01T23:59:59.000Z

48

Model of critical heat flux in subcooled flow boiling  

E-Print Network [OSTI]

The physical phenomenon occurring before and at the critical heat flux (CHF) for subcooled flow boiling has been investigated. The first phase of this study established the basic nature of the flow structure at CHF. A ...

Fiori, Mario P.

1968-01-01T23:59:59.000Z

49

Sodium boiling dryout correlation for LMFBR fuel assemblies  

SciTech Connect (OSTI)

Under certain postulated accident conditions for a Liquid Metal Fast Breeder Reactor (LMFBR), such as the failure of the shutdown heat removal system (SHRS), sodium boiling and clad dryout might occur in the fuel assemblies. It is important to predict the time from boiling inception to dryout, since sustained clad dryout will result in core damage. In this paper a dryout correlation is presented. This correlation is based on 21 boiling tests which resulted in dryout from the THORS BUNDLE 6A, a 19-pin full-length simulated LMFBR fuel assembly and from the THORS Bundle 9, a 61-pin full-length simulated LMFBR fuel assembly. All these tests were performed as follows: for each specified bundle power, an initial steady-state high sodium flow was established, for which sodium boiling did not occur in the bundle. The temperature at the outlet of the test section was approx. 700/sup 0/C. Then, using a programmable pump control system, the flow was reduced to a low value and boiling occurred.

Carbajo, J.J.; Rose, S.D.

1984-01-01T23:59:59.000Z

50

Enhanced boiling heat transfer in horizontal test bundles  

SciTech Connect (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

51

Pool boiling heat transfer enhancement over cylindrical tubes with water at atmospheric pressure, Part I: Experimental results  

E-Print Network [OSTI]

Pool boiling heat transfer enhancement over cylindrical tubes with water at atmospheric pressure online 4 May 2013 Keywords: Pool boiling Heat transfer enhancement Open microchannels Cylindrical tube boiling heat transfer over enhanced cylindrical microchannel test surfaces with water at atmospheric

Kandlikar, Satish

52

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

53

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.

54

E-Print Network 3.0 - advanced boiling water Sample Search Results  

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

water Search Powered by Explorit Topic List Advanced Search Sample search results for: advanced boiling water Page: << < 1 2 3 4 5 > >> 1 Boiling Radial Flow in Fractures of...

55

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

56

Measurement of Nucleate Pool Boiling with Synchronized Particle Imaging Velocimetry and Infrared Thermometry  

E-Print Network [OSTI]

Nucleate boiling is important in many energy systems including light water reactors. Currently significant efforts are underway to develop mechanisticmodels for nucleate boiling based on computational fluid dynamics (CFD). ...

Duan, X.

57

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

58

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

E-Print Network [OSTI]

Numerical study of high heat ÂŻux pool boiling heat transfer Ying He a,*, Masahiro Shoji b , Shigeo simulation model of boiling heat transfer is proposed based on a numerical macrolayer model [S. Maruyama, M. Shoji, S. Shimizu, A numerical simulation of transition boiling heat transfer, in: Proceedings

Maruyama, Shigeo

59

Flow Boiling Heat Transfer Coefficient In Minichannels Correlation and Trends Satish G. Kandlikar  

E-Print Network [OSTI]

Flow Boiling Heat Transfer Coefficient In Minichannels ­ Correlation and Trends Satish G. Kandlikar York 14623, USA The flow boiling heat transfer in small diameter passages is being applied in many boiling heat transfer coefficient with the correlations developed for conventional channels. It is found

Kandlikar, Satish

60

NUMERICAL SIMULATION OF POOL BOILING FOR STEADY STATE AND TRANSIENT HEATING  

E-Print Network [OSTI]

1 NUMERICAL SIMULATION OF POOL BOILING FOR STEADY STATE AND TRANSIENT HEATING Ying He, Masahiro role in nucleate and transition boiling heat transfer at high heat flux. Many experiments have been in the numerical simulation of boiling heat transfer. In this study, based on the macrolayer evaporation model

Maruyama, Shigeo

Note: This page contains sample records for the topic "naph tha 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

Enhancement of Pool Boiling Heat Transfer in Confined Space  

E-Print Network [OSTI]

on pool boiling. In the study, confinement was achieved by placing a flat plate over heated surface. The flat plate has a hole in the middle, and there is a gap between the flat plate and the heater. The diameters of hole are 2 mm, 3 mm, and 4 mm; the gap...

Hsu, Chia-Hsiang

2014-05-05T23:59:59.000Z

62

Modeling acid-gas generation from boiling chloride brines  

SciTech Connect (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

63

Great Boiling Springs Geothermal Area | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia: Energy Resources Jump to: navigation,Ohio: EnergyGrasslands Renewable Energy LLCGray,Boiling Springs Geothermal

64

CASL-U-2015-0040-000 Initial Boiling Water  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation Proposed New Substation Sites Proposed Route Segments (notCAMDL20-000 Initial Boiling Water

65

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

66

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

67

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

68

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

69

Hypothetical Thermodynamic Properties: The Boiling and Critical Temperatures of Polyethylene and Polytetrafluoroethylene  

E-Print Network [OSTI]

Hypothetical Thermodynamic Properties: The Boiling and Critical Temperatures of Polyethylene value asymptotically approaches TB() ) (1217 ( 246) K for series related to polyethylene by the melting temperature of polyethylene.4,5 In this article, the question of whether the normal boiling tem

Chickos, James S.

70

Vapor pressure and boiling point elevation of slash pine black liquors: Predictive models with statistical approach  

SciTech Connect (OSTI)

Vapor-liquid equilibria and boiling point elevation of slash pine kraft black liquors over a wide range of solid concentrations (up to 85% solids) has been studied. The liquors are from a statistically designed pulping experiment for pulping slash pine in a pilot scale digester with four cooking variables of effective alkali, sulfidity, cooking time, and cooking temperature. It was found that boiling point elevation of black liquors is pressure dependent, and this dependency is more significant at higher solids concentrations. The boiling point elevation data at different solids contents (at a fixed pressure) were correlated to the dissolved solids (S/(1 {minus} S)) in black liquor. Due to the solubility limit of some of the salts in black liquor, a change in the slope of the boiling point elevation as a function of the dissolved solids was observed at a concentration of around 65% solids. An empirical method was developed to describe the boiling point elevation of each liquor as a function of pressure and solids mass fraction. The boiling point elevation of slash pine black liquors was correlated quantitatively to the pulping variables, using different statistical procedures. These predictive models can be applied to determine the boiling point rise (and boiling point) of slash pine black liquors at processing conditions from the knowledge of pulping variables. The results are presented, and their utility is discussed.

Zaman, A.A.; McNally, T.W.; Fricke, A.L. [Univ. of Florida, Gainesville, FL (United States)] [Univ. of Florida, Gainesville, FL (United States)

1998-01-01T23:59:59.000Z

71

Comparison of thorium-based fuels with different fissile components in existing boiling water reactors  

E-Print Network [OSTI]

Comparison of thorium-based fuels with different fissile components in existing boiling water, SE-412 96 Göteborg, Sweden Keywords: Thorium BWR Neutronics a b s t r a c t With the aim of investigating the technical feasibility of fuelling a conventional BWR (Boiling Water Reactor) with thorium

Demazière, Christophe

72

Boiling Crisis as a Non-Equilibrium Drying V. S. Nikolayev, D. A. Beysens, J. Hegseth  

E-Print Network [OSTI]

crisis is the formation of a vapor film between the heater and the liquid when the heat supply exceeds in the coordinates heat supply ­ heater temperature is sketched in Fig. 1 for the case of stationary boiling experiment, the so called "pool boiling". When the heat supply to the fluid pool is small, only a fluid

Nikolayev, Vadim S.

73

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

SciTech Connect (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

74

A Review Of Recent Progress On Nano/micro Scale Nucleate Boiling Fundamentals  

E-Print Network [OSTI]

Recent research progress in the area of nano/micro scale nucleate boiling is reviewed and an up-to-date summary is provided with a focus on the advances of fundamental boiling physics. This review examines nano/micro scale ...

Chung, J. N.

2011-01-01T23:59:59.000Z

75

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...

Glenn, Stephen T.

2011-08-08T23:59:59.000Z

76

Two-phase flow visualization in a transparent, atmospheric pressure, boiling water loop  

SciTech Connect (OSTI)

The Simulant Boiling Flow Visualization (SBFV) loop, a transparent, atmospheric pressure test apparatus employing boiling water as a simulant for boiling liquid sodium, has been designed and operated at Oak Ridge National Laboratory. The objective of testing in this loop has been to study two-phase flow behavior that is phenomenologically similar to that observed in sodium boiling experiments, as part of the US Department of Energy Breeder Reactor Safety Program. A detailed description of the design of the SBFV loop is presented, as well as experimental results that show the similarity between low-power boiling behavior in water and liquid sodium. Future tests are planned in a seven-pin flow visualization bundle that will be installed in the SBFV loop. The design of this bundle is also discussed.

Levin, A.E.; Carbajo, J.J.; Montgomery, B.H.; Wantland, J.L.

1985-01-01T23:59:59.000Z

77

Two-dimensional modeling of sodium boiling in a simulated LMFBR loss-of-flow test  

SciTech Connect (OSTI)

Loss-of-flow (LOF) accidents are of major importance in LMFBR safety. Tests have been performed to simulate the simultaneous failure of all primary pumps and reactor shutdown systems in a 37-pin electrically heated test bundle installed in the KNS sodium boiling loop at the Institute of Reactor Development, Karlsruhe. The tests simulated LOF conditions of the German prototype LMFBR, the SNR 300. The main objectives of these tests were to characterize the transient boiling development to cladding dryout and to provide data for validation of sodium boiling codes. One particular LOF test, designated L22, at full power was selected as a benchmark exercise for comparison of several codes at the Eleventh Meeting of the Liquid Metal Boiling Working Group (LMBWG) held in Grenoble, France, in October 1984. In this paper, the results of the calculations performed at ORNL with the two-dimensional (2-D) boiling code THORAX are presented.

Rose, S.D.

1984-01-01T23:59:59.000Z

78

Nonlinear dynamics and chaos in boiling water reactors  

SciTech Connect (OSTI)

There are currently 72 commercial boiling water reactors (BWRs) in operation or under construction in the western world, 37 of them in the United States. Consequently, a great effort has been devoted to the study of BWR systems under a wide range of plant operating conditions. This paper represents a contribution to this ongoing effort; its objective is to study the basic dynamic processes in BWR systems, with special emphasis on the physical interpretation of BWR dynamics. The main thrust in this work is the development of phenomenological BWR models suited for analytical studies performed in conjunction with numerical calculations. This approach leads to a deeper understanding of BWR dynamics and facilitates the interpretation of numerical results given by currently available sophisticated BWR codes. 6 refs., 14 figs., 2 tabs.

March-Leuba, J.

1988-01-01T23:59:59.000Z

79

Feasibility study on the thorium fueled boiling water breeder reactor  

SciTech Connect (OSTI)

The feasibility of (Th,U)O 2 fueled, boiling water breeder reactor based on conventional BWR technology has been studied. In order to determine the potential use of water cooled thorium reactor as a competitive breeder, this study evaluated criticality, breeding and void reactivity coefficient in response to changes made in MFR and fissile enrichments. The result of the study shows that while using light water as moderator, low moderator to fuel volume ratio (MFR=0.5), it was possible to breed fissile fuel in negative void reactivity condition. However the burnup value was lower than the value of the current LWR. On the other hand, heavy water cooled reactor shows relatively wider feasible breeding region, which lead into possibility of designing a core having better neutronic and economic performance than light water with negative void reactivity coefficient. (authors)

PetrusTakaki, N. [Dept. of Applied Science, Tokai Univ., Kitakaname, Hiratsuka, Kanagawa 259-1292 (Japan)

2012-07-01T23:59:59.000Z

80

Nucleate boiling pressure drop in an annulus: Book 2  

SciTech Connect (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 annulus has a full-scale geometry, and in fat uses SRL dummy hardware for the inner annulus wall in the ribbed geometry. The materials aluminum. The annulus is uniformly heated in the axial direction, but the circumferential heat flux can be varied to provide ``power tilt`` or asymmetric heating of the inner and outer annulus walls. The test facility uses H{sub 2}O rather than D{sub 2}O, but it includes the effects of dissolved helium gas present in the reactor. 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.

Block, J.A.; Crowley, C.; Dolan, F.X.; Sam, R.G.; Stoedefalke, B.H.

1992-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "naph tha boiling" from the National Library of EnergyBeta (NLEBeta).
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81

CORQUENCH: A model for gas sparging-enhanced melt-water, film boiling heat transfer  

SciTech Connect (OSTI)

A phenomenological model (CORQUENCH) has been developed to describe the gas-sparging enhanced film boiling heat transfer between a molten pool of corium and an overlying water layer. The model accounts for thermal radiation across the vapor film, bulk liquid subcooling, interfacial area enhancement due to sparging gas, and melt entrainment into the overlying water layer. In this paper, the modeling approach is described, and a comparison with the lead-Freon 11 and lead-water film boiling experiment data of Greene is made. Predictions are then made for the case of film boiling over corium in the presence of sparging concrete decomposition gases. 15 refs., 3 figs.

Farmer, M.T.; Sienicki, J.J.; Spencer, B.W.

1990-01-01T23:59:59.000Z

82

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

83

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

84

Nano-engineering the boiling surface for optimal heat transfer rate and critical heat flux  

E-Print Network [OSTI]

The effects on pool boiling characteristics such as critical heat flux and the heat transfer coefficient of different surface characteristics such as surface wettability, roughness, morphology, and porosity are not well ...

Phillips, Bren Andrew

2011-01-01T23:59:59.000Z

85

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

86

A visualization comparison of convective flow boiling heat transfer augmentation devices  

E-Print Network [OSTI]

The qualitative effects of inset-table heat transfer phics. augmentation devices on vertical in-tube convective flow boiling flow regimes, transition mechanisms, and heat transfer are presented in this study. Three twisted tapes with twist ratios...

Lundy, Brian Franklin

1998-01-01T23:59:59.000Z

87

Experimental Observation and Measurements of Pool Boiling Heat Transfer using PIV, Shadowgraphy, RICM Techniques  

E-Print Network [OSTI]

This present study seeks to contribute detailed visualization data on a pool boiling experiments using HFE-7000. Particle Image Velocimetry (PIV) was used to measure the time resolved whole field liquid velocity. Bubble dynamic parameters...

Di, Yuan 1988-

2012-12-05T23:59:59.000Z

88

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 out of borosilicate glass, and flown on NASA's KC-135 reduced gravity airplane...

Westheimer, David Thomas

2000-01-01T23:59:59.000Z

89

Experimental and Numerical Investigation of Pool Boiling Heat Transfer on Engineered Nano-Finned Surfaces  

E-Print Network [OSTI]

Pool boiling experiments for nanocoatings (or nanostructured surfaces) show that despite the lower thermal conductivity values than carbon, silicon yielded higher values of CHF (critical heat flux). Subsequently numerical studies showed...

Yang, Hongjoo

2014-08-10T23:59:59.000Z

90

A study of system-induced instabilities in forced-convection flows with subcooled boiling  

E-Print Network [OSTI]

A combined analytical and experimental program was carried out to investigate the problem of hydrodynamic stability of forcedconvection flows with boiling. The study was restricted to the flow of water in small channels ...

Maulbetsch, John S.

1965-01-01T23:59:59.000Z

91

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

92

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

93

Thermal non-equilibrium in dispersed flow film boiling in a vertical tube  

E-Print Network [OSTI]

The departure from thermal equilibrium between a dispersed liquid phase and its vapor at high quality during film boiling is investigated, The departure from equilibruim is manifested by the high resistance to heat transfer ...

Forslund, Robert Paul

1966-01-01T23:59:59.000Z

94

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

E-Print Network [OSTI]

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

Estrada Perez, Carlos E.

2010-01-16T23:59:59.000Z

95

Enhanced convective and film boiling heat transfer by surface gas injection  

SciTech Connect (OSTI)

Heat transfer measurements were made for stable film boiling of water over a horizontal, flat stainless steel plate from the minimum film boiling point temperature, T{sub SURFACE} {approximately}500K, to T{sub SURFACE} {approximately}950K. The pressure at the plate was approximately 1 atmosphere and the temperature of the water pool was maintained at saturation. The data were compared to the Berenson film-boiling model, which was developed for minimum film-boiling-point conditions. The model accurately represented the data near the minimum film-boiling point and at the highest temperatures measured, as long it was corrected for the heat transferred by radiation. On the average, the experimental data lay within {plus_minus}7% of the model. Measurements of heat transfer were made without film boiling for nitrogen jetting into an overlying pool of water from nine 1-mm- diameter holes, drilled in the heat transfer plate. The heat flux was maintained constant at approximately 26.4 kW/m{sup 2}. For water-pool heights of less than 6cm the heat transfer coefficient deceased linearly with a decrease in heights. Above 6cm the heat transfer coefficient was unaffected. For the entire range of gas velocities measured [0 to 8.5 cm/s], the magnitude of the magnitude of the heat transfer coefficient only changed by approximately 20%. The heat transfer data bound the Konsetov model for turbulent pool heat transfer which was developed for vertical heat transfer surfaces. This agreement suggests that surface orientation may not be important when the gas jets do not locally affect the surface heat transfer. Finally, a database was developed for heat transfer from the plate with both film boiling and gas jetting occurring simultaneously, in a pool of water maintained at its saturation temperature. The effect of passing nitrogen through established film boiling is to increase the heat transfer from that surface. 60 refs.

Duignan, M.R.; Greene, G.A. [Brookhaven National Lab., Upton, NY (United States); Irvine, T.F., Jr. [State Univ. of New York, Stony Brook, NY (United States). Dept. of Mechanical Engineering

1992-04-01T23:59:59.000Z

96

Enhanced convective and film boiling heat transfer by surface gas injection  

SciTech Connect (OSTI)

Heat transfer measurements were made for stable film boiling of water over a horizontal, flat stainless steel plate from the minimum film boiling point temperature, T{sub SURFACE} {approximately}500K, to T{sub SURFACE} {approximately}950K. The pressure at the plate was approximately 1 atmosphere and the temperature of the water pool was maintained at saturation. The data were compared to the Berenson film-boiling model, which was developed for minimum film-boiling-point conditions. The model accurately represented the data near the minimum film-boiling point and at the highest temperatures measured, as long it was corrected for the heat transferred by radiation. On the average, the experimental data lay within {plus minus}7% of the model. Measurements of heat transfer were made without film boiling for nitrogen jetting into an overlying pool of water from nine 1-mm- diameter holes, drilled in the heat transfer plate. The heat flux was maintained constant at approximately 26.4 kW/m{sup 2}. For water-pool heights of less than 6cm the heat transfer coefficient deceased linearly with a decrease in heights. Above 6cm the heat transfer coefficient was unaffected. For the entire range of gas velocities measured (0 to 8.5 cm/s), the magnitude of the magnitude of the heat transfer coefficient only changed by approximately 20%. The heat transfer data bound the Konsetov model for turbulent pool heat transfer which was developed for vertical heat transfer surfaces. This agreement suggests that surface orientation may not be important when the gas jets do not locally affect the surface heat transfer. Finally, a database was developed for heat transfer from the plate with both film boiling and gas jetting occurring simultaneously, in a pool of water maintained at its saturation temperature. The effect of passing nitrogen through established film boiling is to increase the heat transfer from that surface. 60 refs.

Duignan, M.R.; Greene, G.A. (Brookhaven National Lab., Upton, NY (United States)); Irvine, T.F., Jr. (State Univ. of New York, Stony Brook, NY (United States). Dept. of Mechanical Engineering)

1992-04-01T23:59:59.000Z

97

Boiling-Water Reactor internals aging degradation study. Phase 1  

SciTech Connect (OSTI)

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

98

Corrosion optimized Zircaloy for boiling water reactor (BWR) fuel elements  

SciTech Connect (OSTI)

A corrosion optimized Zircaloy has to be based primarily on in-boiling water reactor (in-BWR) results. Therefore, the material parameters affecting corrosion were deduced from results of experimental fuel rod irradiation with systematic variations and from a large variety of material coupons exposed in water rods up to four cycles. The major material effects is the size and distribution of precipitates. For optimizing both early and late corrosion, the size has to stay in a small range. In the case of material quenched in the final stage, the quenching rate appears to be an important parameter. As far as materials chemistry is concerned, the in-BWR results indicate that corrosion in BWRs is influenced by the alloying elements tin, chromium, and the impurity silicon. In addition to corrosion optimization, hydriding is also considered. A large variation from lot to lot under identically coolant condition has been found. The available data indicate that the chromium content is the most important material parameter for hydrogen pickup.

Garzarolli, F.; Schumann, R.; Steinberg, E. [Siemens AG, Erlangen (Germany). Power Generation Group

1994-12-31T23:59:59.000Z

99

Camera Inspection Arm for Boiling Water Reactors - 13330  

SciTech Connect (OSTI)

Boiling Water Reactor (BWR) outage maintenance tasks can be time-consuming and hazardous. Reactor facilities are continuously looking for quicker, safer, and more effective methods of performing routine inspection during these outages. In 2011, S.A. Technology (SAT) was approached by Energy Northwest to provide a remote system capable of increasing efficiencies related to Reactor Pressure Vessel (RPV) internal inspection activities. The specific intent of the system discussed was to inspect recirculation jet pumps in a manner that did not require manual tooling, and could be performed independently of other ongoing inspection activities. In 2012, SAT developed a compact, remote, camera inspection arm to create a safer, more efficient outage environment. This arm incorporates a compact and lightweight design along with the innovative use of bi-stable composite tubes to provide a six-degree of freedom inspection tool capable of reducing dose uptake, reducing crew size, and reducing the overall critical path for jet pump inspections. The prototype camera inspection arm unit is scheduled for final testing in early 2013 in preparation for the Columbia Generating Station refueling outage in the spring of 2013. (authors)

Martin, Scott; Rood, Marc [S.A. Technology, 3985 S. Lincoln Ave, Loveland, CO 80537 (United States)] [S.A. Technology, 3985 S. Lincoln Ave, Loveland, CO 80537 (United States)

2013-07-01T23:59:59.000Z

100

Aging study of boiling water reactor high pressure injection systems  

SciTech Connect (OSTI)

The purpose of high pressure injection systems is to maintain an adequate coolant level in reactor pressure vessels, so that the fuel cladding temperature does not exceed 1,200{degrees}C (2,200{degrees}F), and to permit plant shutdown during a variety of design basis loss-of-coolant accidents. This report presents the results of a study on aging performed for high pressure injection systems of boiling water reactor plants in the United States. The purpose of the study was to identify and evaluate the effects of aging and the effectiveness of testing and maintenance in detecting and mitigating aging degradation. Guidelines from the United States Nuclear Regulatory Commission`s Nuclear Plant Aging Research Program were used in performing the aging study. Review and analysis of the failures reported in databases such as Nuclear Power Experience, Licensee Event Reports, and the Nuclear Plant Reliability Data System, along with plant-specific maintenance records databases, are included in this report to provide the information required to identify aging stressors, failure modes, and failure causes. Several probabilistic risk assessments were reviewed to identify risk-significant components in high pressure injection systems. Testing, maintenance, specific safety issues, and codes and standards are also discussed.

Conley, D.A.; Edson, J.L.; Fineman, C.F. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)

1995-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "naph tha 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

Multi-cycle boiling water reactor fuel cycle optimization  

SciTech Connect (OSTI)

In this work a new computer code, BWROPT (Boiling Water Reactor Optimization), is presented. BWROPT uses the Parallel Simulated Annealing (PSA) algorithm to solve the out-of-core optimization problem coupled with an in-core optimization that determines the optimum fuel loading pattern. However it uses a Haling power profile for the depletion instead of optimizing the operating strategy. The result of this optimization is the optimum new fuel inventory and the core loading pattern for the first cycle considered in the optimization. Several changes were made to the optimization algorithm with respect to other nuclear fuel cycle optimization codes that use PSA. Instead of using constant sampling probabilities for the solution perturbation types throughout the optimization as is usually done in PSA optimizations the sampling probabilities are varied to get a better solution and/or decrease runtime. The new fuel types available for use can be sorted into an array based on any number of parameters so that each parameter can be incremented or decremented, which allows for more precise fuel type selection compared to random sampling. Also, the results are sorted by the new fuel inventory of the first cycle for ease of comparing alternative solutions. (authors)

Ottinger, K.; Maldonado, G.I. [University of Tennessee, 311 Pasqua Engineering Building, Knoxville, TN 37996-2300 (United States)

2013-07-01T23:59:59.000Z

102

Boiling behavior of sodium-potassium alloy in a bench-scale solar receiver  

SciTech Connect (OSTI)

During 1989-90, a 75-kW{sub t} sodium reflux pool-boiler solar receiver was successfully demonstrated at Sandia National Laboratories. Significant features of this receiver include (1) boiling sodium as the heat transfer medium and (2) electric-discharge-machined (EDM) cavities as artificial nucleation sites to stabilize boiling. Since this first demonstration, design of a second-generation pool-boiler receiver that will bring the concept closer to commercialization has begun. For long life, the new receiver uses Haynes Alloy 230. For increased safety factors against film boiling and flooding, it has a refined shape and somewhat larger dimensions. To eliminate the need for trace heating, the receiver will boil the sodium-potassium alloy NaK-78 instead of sodium. To reduce manufacturing costs, it will use one of a number of alternatives to EDM cavities for stabilization of boiling. To control incipient-boiling superheats, especially during hot restarts, it will contain a small amount of inert gas. Before the new receiver design could be finalized, bench-scale tests of some of the proposed changes were necessary. A series of bench-scale pool boilers were built from Haynes Alloy 230 and filled with NaK-78. Various boiling-stabilizer candidates were incorporated into them, including laser-drilled cavities and a number of different sintered-powder-metal coatings. These bench-scale pool boilers have been operated at temperatures up to 750{degree}C, heated by quartz lamps with incident radiant fluxes up to 95 W/cm{sup 2}. The effects of various orientations and added gases have been studied. results of these studies are presented. 15 refs.

Moreno, J.B.; Andraka, C.E.; Moss, T.A.

1992-01-01T23:59:59.000Z

103

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

SciTech Connect (OSTI)

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

104

Two-dimensional computational modeling of sodium boiling in simulated LMFBR fuel-pin bundles  

SciTech Connect (OSTI)

Extensive sodium boiling tests have been carried out in two simulated LMFBR fuel pin bundles in the Thermal-Hydraulic Out-of-Reactor Safety (THORS) Facility at Oak Ridge National Laboratory. Experimental results from a 19-pin bundle (THORS Bundle 6A) have been previously reported, and experimental results from a 61-pin bundle (THORS Bundle 9) will be reported soon. The results discussed here are from the 19-pin bundle. Preliminary analysis has shown that the computational methods used and conclusions reached are equally valid for the 61-pin bundle, as well as the 19-pin in-reactor Sodium Loop Safety Facility (SLSF) W-1 experiment. The main result of THORS sodium boiling experimentation is that boiling behavior is determined by two-dimensional effects, i.e., the rates of mass, momentum and energy transfer in the direction perpendicular to the axes of the fuel pins.

Dearing, J.F.

1981-01-01T23:59:59.000Z

105

BOILING CRISIS:THEORY,SIMULATION,AND EXPERIMENTSBOILING CRISIS: THEORY, SIMULATION, AND EXPERIMENTS Boiling is a very efficient way to transfer heat from a heater to the liquid heat carrier. We discuss the  

E-Print Network [OSTI]

that separates the liquid from the heater. Film boiling can be also observed in the kitchen by sprinkling water onto a hot frying pan. In spite of the large temperature of the heater (the pan) the water drops Boiling is a very efficient way to transfer heat from a heater to the liquid heat carrier. We discuss

Nikolayev, Vadim S.

106

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

SciTech Connect (OSTI)

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

107

The use of the probability distribution function to analyze surface temperature fluctuations in pool boiling  

E-Print Network [OSTI]

' '. t 1 . 1 1 q 'd. C t' ~bl', 1. 11 d tl b '1 q, - b '1' q ' b 1 in which fluid flows or boiling outside the channel over The citations used follow the style and format of Transaction of the ASMEi - Journal of Heat Transfer. which fluid flows.... In convective boiling, the heating sur- face is the channel wall and the direction of heat transfer through the heating surface may be either from inside the channel to the outside or vice versa. For instance, feed- water flowing inside economizer tubes...

Tu, Chau Qui

1976-01-01T23:59:59.000Z

108

Investigation of boiling heat transfer at a surface with a system of cylindrical cavities under conditions of free motion  

SciTech Connect (OSTI)

The authors propose a mathematical model for the intensification of boiling heat transfer and the subsequent increase in thermal efficiency of the cylindrical heat transfer surfaces in an evaporative cooling system. The boiling curves for water, ethanol, and freon 113 are calculated for a surface with artificial nucleation sites. The model incorporates such coolant properties as surface tension, specific heat, and vaporization heat.

Danilova, G.N.; Reznikov, V.I.

1988-01-01T23:59:59.000Z

109

Nanoscale modification of key surface parameters to augment pool boiling heat transfer and critical heat flux in water and dielectric fluids  

E-Print Network [OSTI]

Surface effects on pool boiling heat transfer and the critical heat flux are well documented but poorly understood. This study investigates the pool boiling characteristics of various fluids, and demonstrates that surface ...

Forrest, Eric Christopher

2009-01-01T23:59:59.000Z

110

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 of fossil-fuel energy systems. These scenarios are analysed for various environmental and health impacts from fossil fuels and other energy sources reported by IEA []. In all of these countries except Kenya

Kammen, Daniel M.

111

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

E-Print Network [OSTI]

Boiling heat transfer in a hydrofoil-based micro pin fin heat sink Ali KosĂ?ar, Yoav Peles-based micro pin fin heat sink was investigated. Average two-phase heat transfer coefficients were obtained intermittent and spray-annular flows. Heat transfer coefficient trends and flow morphologies were used to infer

Peles, Yoav

112

INVESTIGATING THE EFFECT OF HEATING METHOD ON POOL BOILING HEAT TRANSFER  

E-Print Network [OSTI]

INVESTIGATING THE EFFECT OF HEATING METHOD ON POOL BOILING HEAT TRANSFER Satish G. Kandlikar surfaces in laboratories to obtain the heat transfer coefficient data. In many process applications however, a fluid stream is employed as the heating medium. The heat transfer data generated with the electrically

Kandlikar, Satish

113

"Hot Water" in Lassen Volcanic National Park--Fumaroles, Steaming Ground, and Boiling Mudpots  

E-Print Network [OSTI]

"Hot Water" in Lassen Volcanic National Park-- Fumaroles, Steaming Ground, and Boiling Mudpots U, ydrothermal (hot water) and steaming ground. These features are re- lated to active volcanism, the largest fumarole (steam and volcanic-gas vent) in the park. The temperature of the high-velocity steam

Torgersen, Christian

114

Hydrodynamic cavitation and boiling in refrigerant (R-123) flow inside microchannels  

E-Print Network [OSTI]

Hydrodynamic cavitation and boiling in refrigerant (R-123) flow inside microchannels Brandon cavitation has on heat transfer. The fluid medium is refrigerant R-123 flowing through 227 lm hydraulic diameter microchannels. The cavitation is instigated by the inlet orifice. Adiabatic tests were con- ducted

Peles, Yoav

115

Numerical simulation of boiling during the quenching process N. Kosseifi1  

E-Print Network [OSTI]

by computing the heat flux that arises from the different modes of boiling. They coupled the phase change to heat dissipation of the metal thanks to an interface coupling code. The heat transfer coefficient using a level set method. Surface tension is evaluated using the continuum surface force. The proposed

Paris-Sud XI, Université de

116

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

E-Print Network [OSTI]

. 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...

Reza, S.M. Mohsin

2002-01-01T23:59:59.000Z

117

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 (OSTI)

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

118

Development of a general purpose subgrid wall boiling model from improved physical understanding for use in computational fluid dynamics  

E-Print Network [OSTI]

Advanced modeling capabilities were developed for application to subcooled flow boiling through this work. The target was to introduce, and demonstrate, all necessary mechanisms required to accurately predict the temperature ...

Gilman, Lindsey Anne

2014-01-01T23:59:59.000Z

119

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

120

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

Note: This page contains sample records for the topic "naph tha 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

Effect of combined nanoparticle and polymeric dispersions on critical heat flux, nucleate boiling heat transfer coefficient, and coating adhesion  

E-Print Network [OSTI]

An experimental study was performed to determine thermal performance and adhesion effects of a combined nanoparticle and polymeric dispersion coating. The critical heat flux (CHF) values and nucleate boiling heat transfer ...

Edwards, Bronwyn K

2009-01-01T23:59:59.000Z

122

Experimental pool boiling investigation of FC-72 on silicon with artificial cavities, integrated temperature micro-sensors and heater   

E-Print Network [OSTI]

Today nucleate boiling is widely used in numerous industrial applications such as cooling processes because of the high achieved heat transfer rates for low temperature differences. It remains a possible cooling solution ...

Hutter, Christian

2010-01-01T23:59:59.000Z

123

Film boiling on the inside of vertical tubes with upward flow of the fluid at low qualities  

E-Print Network [OSTI]

Flow regimes, local heat transfer coefficients, and temperature distributions along the wall have been studied for film boiling inside a vertical tube with upward flow of a saturated liquid. The area of interest has been ...

Dougall, R. S.

1963-01-01T23:59:59.000Z

124

Experimental investigation of subcooled flow boiling using synchronized high speed video, infrared thermography, and particle image velocimetry  

E-Print Network [OSTI]

Subcooled flow boiling of water was experimentally investigated using high-speed video (HSV), infrared (IR) thermography, and particle image velocimetry (PIV) to generate a unique database of synchronized data. HSV allowed ...

Phillips, Bren Andrew

2014-01-01T23:59:59.000Z

125

Study of bubble growth in water pool boiling through synchronized, infrared thermometry and high-speed video  

E-Print Network [OSTI]

High-speed video and infrared thermometry were used to obtain time- and space-resolved information on bubble nucleation and heat transfer in pool boiling of water. The bubble departure diameter and frequency, growth and ...

Gerardi, Craig

126

Development of models for the two-dimensional, two-fluid code for sodium boiling NATOF-2D  

E-Print Network [OSTI]

Several features were incorporated into NATOF-2D, a twodimensional, two fluid code developed at M.I.T. for the purpose of analysis of sodium boiling transients under LMFBR conditions. They include improved interfacial mass, ...

Zielinski, R. G.

1981-01-01T23:59:59.000Z

127

Two-dimensional modeling of sodium boiling transients in simulated LMFBR fuel bundles  

SciTech Connect (OSTI)

A two-dimensional code for analysis of sodium boiling in LMFBR fuel assemblies has been developed at ORNL. This code, THORAX, has been used to analyze tests in 19- and 61-pin electrically-heated, simulated LMFBR fuel assemblies in the THORS facility. THORAX has simulated well the transient growth of the two-dimensional boiling region and the resulting static flow instability leading to dryout. Extrapolation of results to a full size fuel pin bundle shows that two-dimensional effects are reduced but still significant. The code will be extended to include a loop model in support of forthcoming tests in the THORS-SHRS Assembly 1 loop, which will include two parallel 19-pin simulated driver bundles.

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

1982-01-01T23:59:59.000Z

128

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

SciTech Connect (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

129

Design, construction and testing of a boiling and convective condensation experiment for use in a microgravity environment  

E-Print Network [OSTI]

travel in the direction of flow. Slug flow occurs when the waves get large enough to reach across the tube. A frothy slug which is propagated along the channel at a high velocity can also form. Annular flow is characterized by a liquid film around... 6mm ID, 8mm OD glass tubes. Observation included direct visual observation and high speed photography of both boiling and condensing flow. Measurements taken included the pressure, and temperature drops associated with both boiling and condensing...

Kachnik, Leo Joseph

1987-01-01T23:59:59.000Z

130

Convective currents in nucleate pool boiling and their effects on the heat flux from varying diameter flat plate heating elements  

E-Print Network [OSTI]

investigation was conducred to amine the effects of convection currents in nucleate oool boil ing and to determine the changes in critical heat flux caused by varying the diameter of horizontal flat olate heating surfaces. Freon 113 (Trichlorotrifluoroethane... by high energy costs and thc need to economize in industrial heat transfer applications . I'nucleate boiling is a very efficient neans of heat transfer because of the large sur ace areas involved in vaporization of the bulk fluid. as bubbles form...

Morford, Peter Stephen

1980-01-01T23:59:59.000Z

131

Multi-scale Control and Enhancement of Reactor Boiling Heat Flux by Reagents and Nanoparticles  

SciTech Connect (OSTI)

The phenomenological characterization of the use of non-invasive and passive techniques to enhance the boiling heat transfer in water has been carried out in this extended study. It provides fundamental enhanced heat transfer data for nucleate boiling and discusses the associated physics with the aim of addressing future and next-generation reactor thermal-hydraulic management. It essentially addresses the hypothesis that in phase-change processes during boiling, the primary mechanisms can be related to the liquid-vapor interfacial tension and surface wetting at the solidliquid interface. These interfacial characteristics can be significantly altered and decoupled by introducing small quantities of additives in water, such as surface-active polymers, surfactants, and nanoparticles. The changes are fundamentally caused at a molecular-scale by the relative bulk molecular dynamics and adsorption-desorption of the additive at the liquid-vapor interface, and its physisorption and electrokinetics at the liquid-solid interface. At the micro-scale, the transient transport mechanisms at the solid-liquid-vapor interface during nucleation and bubblegrowth can be attributed to thin-film spreading, surface-micro-cavity activation, and micro-layer evaporation. Furthermore at the macro-scale, the heat transport is in turn governed by the bubble growth and distribution, macro-layer heat transfer, bubble dynamics (bubble coalescence, collapse, break-up, and translation), and liquid rheology. Some of these behaviors and processes are measured and characterized in this study, the outcomes of which advance the concomitant fundamental physics, as well as provide insights for developing control strategies for the molecular-scale manipulation of interfacial tension and surface wetting in boiling by means of polymeric reagents, surfactants, and other soluble surface-active additives.

R.M. Manglik; A. Athavale; D.S. Kalaikadal; A. Deodhar; U. Verma

2011-09-02T23:59:59.000Z

132

Analysis of the magnetic corrosion product deposits on a boiling water reactor cladding  

SciTech Connect (OSTI)

The buildup of corrosion product deposits (CRUD) on the fuel cladding of the boiling water reactor (BWR) before and after zinc injection has been investigated by applying local experimental analytical techniques. Under the BWR water chemistry conditions, Zn addition together with the presence of Ni and Mn induce the formation of (Zn,Ni,Mn)[Fe{sub 2}O{sub 4}] spinel solid solutions. X-ray absorption spectroscopy (XAS) revealed inversion ratios of cation distribution in spinels deposited from the solid solution. Based on this information, a two-site ferrite spinel solid solution model is proposed. Electron probe microanalysis (EPMA) and extended X-ray absorption fine structure (EXAFS) findings suggest the zinc-rich ferrite spinels formation on BWR fuel cladding mainly at lower pin. - Graphical Abstract: Analysis of spinels in corrosion product deposits on boiling water reactor fuel rod. Combining EPMA and XAFS results: schematic representation of the ferrite spinels in terms of the end members and their extent of inversion. Note that the ferrites are represented as a surface between the normal (upper plane, M[Fe{sub 2}]O{sub 4}) and the inverse (lower plane, Fe[MFe]O{sub 4}). Actual compositions red Black-Small-Square for the specimen at low elevation (810 mm), blue Black-Small-Square for the specimen at mid elevation (1800 mm). The results have an impact on the properties of the CRUD material. Highlights: Black-Right-Pointing-Pointer Buildup of corrosion product deposits on fuel claddings of a boiling water reactor (BWR) are investigated. Black-Right-Pointing-Pointer Under BWR water conditions, Zn addition with Ni and Mn induced formation of (Zn,Ni,Mn)[Fe{sub 2}O{sub 4}]. Black-Right-Pointing-Pointer X-Ray Adsorption Spectroscopy (XAS) revealed inversion of cations in spinel solid solutions. Black-Right-Pointing-Pointer Zinc-rich ferrite spinels are formed on BWR fuel cladding mainly at lower pin elevations.

Orlov, Andrey [Paul Scherrer Institut, Villigen (Switzerland); Degueldre, Claude, E-mail: claude.degueldre@psi.ch [Paul Scherrer Institut, Villigen (Switzerland); Kaufmann, Wilfried [Kernkraftwerk Leibstadt, Leibstadt (Switzerland)

2013-01-15T23:59:59.000Z

133

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

SciTech Connect (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

134

Evaluation of nonequilibrium effects in bundle dispersed-flow film boiling. [PWR; BWR  

SciTech Connect (OSTI)

The effects of thermodynamic nonequilibrium in dispersed flow film boiling heat transfer are examined. Steady-state and transient rod-bundle data are used to evaluate several empirical heat-transfer models commonly employed to predict post-CHF behavior. The models that account for thermodynamic nonequilibrium perform adequately, while those that ignore nonequilibrium effects incur errors in wall superheat as high as 190/sup 0/K. Nonequilibrium effects can also be treated by explicitly modeling the phenomena. The thermal-hydraulic code COBRA-TF employs this approach. Using bundle data, the models in the code are evaluated. Analysis suggests that the interfacial heat transfer is overpredicted.

Morris, D.G.; Mullins, C.B.; Yoder, G.L.

1983-01-01T23:59:59.000Z

135

Modeling Single-Phase and Boiling Liquid Jet Impingement Cooling in Power Electronics  

SciTech Connect (OSTI)

Jet impingement has been an attractive cooling option in a number of industries over the past few decades. Over the past 15 years, jet impingement has been explored as a cooling option in microelectronics. Recently, interest has been expressed by the automotive industry in exploring jet impingement for cooling power electronics components. This technical report explores, from a modeling perspective, both single-phase and boiling jet impingement cooling in power electronics, primarily from a heat transfer viewpoint. The discussion is from the viewpoint of the cooling of IGBTs (insulated-gate bipolar transistors), which are found in hybrid automobile inverters.

Narumanchi, S. V. J.; Hassani, V.; Bharathan, D.

2005-12-01T23:59:59.000Z

136

Enhancement of pool boiling heat transfer with electrohydrodynamics and its fundamental study  

E-Print Network [OSTI]

, enhancements of up to an order of magnitude was achieved. Cooper (1990) made visual observations and noted that when an electrode potential of about 5-8 kV was applied to R-114 at a few degrees of superheat, immediate activation of nucleation sites all over..., and 10kV. To conduct this study, an existing low pressure pool boiling apparatus was modified and another high pressure apparatus was designed and built. The fluids were tested on the smooth tube at operating temperatures of 4'C and 20'C, and 19 fins...

Raghupathi, Sri Laxmi Priya

1998-01-01T23:59:59.000Z

137

CORQUENCH: A model for gas sparging-enhanced, melt-water, film-boiling heat transfer  

SciTech Connect (OSTI)

In evaluation of severe-accident sequences for water-cooled nuclear reactors, molten core materials may be postulated to be released into the containment and accumulate on concrete. The heatup and decomposition of concrete is accompanied by the release of water vapor and carbon dioxide gases. Gases flowing through the melt upper surface can influence the rates of heat transfer to water overlying the melt. In particular, the gas flow through the interface can be envisioned to enhance the heat removal from the melt. A mechanistic model (CORQUENCH) has been developed to describe film-boiling heat transfer between a molten pool and an overlying coolant layer in the presence of sparging gas. The model favorably predicts the lead-Feron 11 data of Greene and Greene et al. for which the calculations indicate that area enhancement in the conduction heat transfer across the film is the predominant mechanism leading to augmentation in the heat flux as the gas velocity increases. Predictions for oxidic corium indicate a rapid increase in film-boiling heat flux as the gas velocity rises. The predominant mode of heat transfer for this case is radiation, and the increase in heat flux with gas velocity is primarily a result of interfacial area enhancement of the radiation component of the overall heat transfer coefficient. The CORQUENCH model has been incorporated into the MELTSPREAD-1 computer code{sup 6} for the analysis of transient spreading in containments.

Farmer, M.T.; Sienicki, J.J.; Spencer, B.W.

1990-01-01T23:59:59.000Z

138

Magnetic thaw-down and boil-off due to magneto acceptors in 2DEG  

SciTech Connect (OSTI)

The Quantum Hall Effect (QHE) and Shubnikov-de Haas effect are investigated experimentally using n type modulation-doped GaAs/GaAlAs quantum wells (QWs) additionally doped in the well with beryllium acceptor atoms. It is presently shown that the localized magneto-acceptor (MA) states which possess discrete energies above the corresponding Landau levels (LLs) lead to two observable effects in magneto-transport: magnetic thaw-down and magnetic boil-off of 2D electrons. Both effects are related to the fact that electrons occupying the localized MA states cannot conduct. Thus in the thaw-down effect the electrons fall down from the MA states to the free Landau states. This leads to a shift of the Hall plateau towards higher magnetic fields as a consequence of an increase of the 2D electron density N{sub S}. In the boil-off effect the electrons are pushed from the free Landau states to the empty MA states under high enough Hall electric field. This process has an avalanche character leading to a dramatic increase of magneto-resistance, consequence of a decrease of N{sub S}.

Chaubet, C.; Raymond, A. [L2C UMR 5221, CNRS-Université Montpellier 2, Place E. Bataillon, 34090 Montpellier cedex 05 (France); Bisotto, I. [LNCMI, UPR 3228, CNRS-INSA-UJF-UPS, BP166, 38042 Grenoble, Cedex 9 (France); Harmand, J. C. [LPN, CNRS, route de Nozay, 91460 Marcoussis (France); Kubisa, M. [Institute of Physics, Wroclaw University of Technology, 50-370 Wroclaw (Poland); Zawadzki, W. [Institute of Physics, Polish Academy of Sciences, 02668 Warsaw (Poland)

2013-12-04T23:59:59.000Z

139

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

SciTech Connect (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

140

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

SciTech Connect (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

Note: This page contains sample records for the topic "naph tha 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

A correlation for local coefficients of heat transfer in boiling of R12 and R22 refrigerants on multirow bundles of smooth tubes  

SciTech Connect (OSTI)

Experimental results on the boiling of R12 and R22 on bundles of 30 to 50 vertically stacked rows of smooth tubes are presented and correlated. Engineering equations for determining the coefficients of heat transfer in the pool boiling of freons on such multirow bundles are derived.

Rebrov, P.N.; Bukin, V.G.; Danilova, G.N.

1989-07-01T23:59:59.000Z

142

IEEE TRANSACTIONS ON AUTOMATIC CONTROL, VOL. AC-20, NO. 6, DECEMBER 1975 127 Acoustics, Stability, and Compensation in Boiling  

E-Print Network [OSTI]

of turbine bypass valves duringstart-up as well asduringand following rapid closure of the turbine admissionIEEE TRANSACTIONS ON AUTOMATIC CONTROL, VOL. AC-20, NO. 6, DECEMBER 1975 127 Acoustics, Stability of steam pipe acoustics on the control of steam pressore in boiling waterreactors. A madel is developed

Kwatny, Harry G.

143

Microjet array single-phase and flow boiling heat transfer with R134a Eric A. Browne a  

E-Print Network [OSTI]

of a submerged microjet array was conducted with R134a. The staggered array of seventeen 112-lm diameter orifices blades and quench metals. Many of these practical uses of jets employ an array of jets rather than circular microjets of diameter 112 lm on a 1 Ă? 1 mm heater to investigate single-phase and boiling heat

Peles, Yoav

144

Boiling Water at Hot Creek--The Dangerous and Dynamic Thermal Springs in California's Long Valley Caldera  

E-Print Network [OSTI]

). Conditions in Hot Creek can change very quickly. These fish--caught in a burst of high-temperature water" or intermittently spurting very hot, sediment-laden water as high as 6 feet (2 m) above the stream surface. At timesBoiling Water at Hot Creek--The Dangerous and Dynamic Thermal Springs in California's Long Valley

Torgersen, Christian

145

Experimental determination of residual stress by neutron diffraction in a boiling water reactor core shroud  

SciTech Connect (OSTI)

Residual strains in a 51 mm (2-inch) thick 304L stainless steel plate have been measured by neutron diffraction and interpreted in terms of residual stress. The plate, measuring (300 mm) in area, was removed from a 6m (20-ft.) diameter unirradiated boiling water reactor core shroud, and included a multiple-pass horizontal weld which joined two of the cylindrical shells which comprise the core shroud. Residual stress mapping was undertaken in the heat affected zone, concentrating on the outside half of the plate thickness. Variations in residual stresses with location appeared consistent with trends expected from finite element calculations, considering that a large fraction of the residual hoop stress was released upon removal of the plate from the core shroud cylinder.

Payzant, A.; Spooner, S.; Zhu, Xiaojing; Hubbard, C.R. [and others

1996-06-01T23:59:59.000Z

146

Complete Numerical Simulation of Subcooled Flow Boiling in the Presence of Thermal and Chemical Interactions  

SciTech Connect (OSTI)

At present, guidelines for fuel cycle designs to prevent axial offset anomalies (AOA) in pressurized water reactor (PWR) cores are based on empirical data from several operating reactors. Although the guidelines provide an ad-hoc solution to the problem, a unified approach based on simultaneous modeling of thermal-hydraulics, chemical, and nuclear interactions with vapor generation at the fuel cladding surface does not exist. As a result, the fuel designs are overly constrained with a resulting economic penalty. The objective of present project is to develop a numerical simulation model supported by laboratory experiments that can be used for fuel cycle design with respect to thermal duty of the fuel to avoid economic penalty, as well as, AOA. At first, two-dimensional numerical simulation of the growth and departure of a bubble in pool boiling with chemical interaction is considered. A finite difference scheme is used to solve the equations governing conservation of mass, momentum, energy, and species concentration. The Level Set method is used to capture the evolving liquid-vapor interface. A dilute aqueous boron solution is considered in the simulation. From numerical simulations, the dynamic change in concentration distribution of boron during the bubble growth shows that the precipitation of boron can occur near the advancing and receding liquid-vapor interface when the ambient boron concentration level is 3,000 ppm by weight. Secondly, a complete three-dimensional numerical simulation of inception, growth and departure of a single bubble subjected to forced flow parallel to the heater surface was developed. Experiments on a flat plate heater with water and with boron dissolved in the water were carried out. The heater was made out of well-polished silicon wafer. Numbers of nucleation sites and their locations were well controlled. Bubble dynamics in great details on an isolated nucleation site were obtained while varying the wall superheat, liquid subcooling and flow velocity parametrically. Concentration variation of boron near the liquid-vapor interface was detected successfully with a newly developed miniature concentration sensor. The measured concentration variations at different radial locations from the center of cavity have the same trend as given by the numerical simulations. The deposition of boron was found near the nucleation site on the heater surface, which validates the numerical simulation. Subcooled flow boiling experiments at three pressures were performed on a nine-rod bundle with water and with boron dissolved in the water. The test runs were conducted with a wide range of mass fluxes (186 to 2800 kg/m2s) and heat fluxes (1.0 to 30.0 W/ cm2). Not only the variables required to develop mechanistic models for subcooled flow boiling were measured, but also the crud formation during boiling and its effect on the heat transfer process were investigated. (B204)

V.K. Dhir

2003-04-28T23:59:59.000Z

147

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

SciTech Connect (OSTI)

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

148

Operational experience with and post-irradiation examinations on boiling water reactor control rods  

SciTech Connect (OSTI)

The control rods of the KRB-I 250-MW (electric) boiling water reactor contain Vipac B/sub 4/C powder in Type 304 stainless steel tubes as a neutron-absorbing material. Because of an increase in the reactor coolant /sup 3/H activity, defective control rods were suspected. The hot cell examination of a highly exposed control rod revealed B/sub 4/C losses. The mechanism of failure was shown to be B/sub 4/C swelling and stress corrosion cracking of the absorber tubes, followed by B/sub 4/C washout. The B/sub 4/C volume swelling is given. The tube cracking starts at 30 to 35% and the B/sub 4/C washout at 50 to 55% local /sup 10/B burnup in the tubes.

Eickelpash, N.; Mullauer, J.; Seepolt, R.W.; Spalthoff, W.

1983-03-01T23:59:59.000Z

149

Boiling water reactor control rod programming using heuristic and mathematical methods  

SciTech Connect (OSTI)

OPROD, a computer code for automatic generation of control rod programming that has successfully been applied to an older boiling water reactor (BWR), has experienced some difficulties when applied to a BWR of larger power density and stronger heterogeneity. To improve the performance, a heuristic algorithm that is derived from accumulated experience has been introduced to search for a feasible rod pattern that satisfies all constraints. Application of this algorithm to an initial cycle of an 800-MW(e) BWR of high heterogeneity has been very successful. It has been demonstrated that the proposed algorithm is capable of finding a feasible rod pattern, even starting from an all-rods-out pattern. Some improvement was also made in the method of approximation programming (MAP) algorithm. The temporal constraint relaxation method is shown to be effective in finding an optimal control rod pattern in MAP starting from a guess pattern that is not feasible.

Hayase, T.; Motoda, H.

1980-04-01T23:59:59.000Z

150

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

151

Lattice Boltzmann Methods to Address Fundamental Boiling and Two-Phase Problems  

SciTech Connect (OSTI)

This report presents the progress made during the fourth (no cost extension) year of this three-year grant aimed at the development of a consistent Lattice Boltzmann formulation for boiling and two-phase flows. During the first year, a consistent LBM formulation for the simulation of a two-phase water-steam system was developed. Results of initial model validation in a range of thermo-dynamic conditions typical for Boiling Water Reactors (BWRs) were shown. Progress was made on several fronts during the second year. Most important of these included the simulation of the coalescence of two bubbles including the surface tension effects. Work during the third year focused on the development of a new lattice Boltzmann model, called the artificial interface lattice Boltzmann model (AILB model) for the 3 simulation of two-phase dynamics. The model is based on the principle of free energy minimization and invokes the Gibbs-Duhem equation in the formulation of non-ideal forcing function. This was reported in detail in the last progress report. Part of the efforts during the last (no-cost extension) year were focused on developing a parallel capability for the 2D as well as for the 3D codes developed in this project. This will be reported in the final report. Here we report the work carried out on testing the AILB model for conditions including the thermal effects. A simplified thermal LB model, based on the thermal energy distribution approach, was developed. The simplifications are made after neglecting the viscous heat dissipation and the work done by pressure in the original thermal energy distribution model. Details of the model are presented here, followed by a discussion of the boundary conditions, and then results for some two-phase thermal problems.

Rizwan Uddin

2012-01-01T23:59:59.000Z

152

Knowledge and abilities catalog for nuclear power plant operators: boiling water reactors  

SciTech Connect (OSTI)

The Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Boiling-Water Reactors (BWR) (NUREG-1123) 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 and Examiners' Handbook for Developing Operator Licensing Examinations (NUREG-1121) will cover those topics listed under Title 10, Code of Federal Regulations, Part 55. The BWR Catalog contains approximately 7000 knowledge and ability (K/A) statements for ROs and SROs at boiling water reactors. Each K/A statement has been rated for its importance to the safe operation of the plant in a manner ensuring personnel and public health and safety. The BWR K/A Catalog is organized into five major sections: Plant-wide Generic Knowledge and Ability Statements, Plant Systems grouped by Safety Function, Emergency and Abnormal Plant Evolutions, Components, and Theory. The BWR Catalog represents a modification of the form and content of the K/A Catalog for Nuclear Power Plant Operators: Pressurized Water Reactors (NUREG-1122). First, categories of knowledge and ability statements have been redefined. Second, the scope of the definition of emergency and abnormal plant evolutions has been revised in line with a symptom-based approach. Third, K/As related to the operational applications of theory have been incorporated into the delineations for both plant systems and emergency and abnormal plant evolutions, while K/As pertaining to theory fundamental to plant operation have been delineated in a separate theory section. Finally, the components section has been revised.

Not Available

1986-09-01T23:59:59.000Z

153

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

SciTech Connect (OSTI)

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

154

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

SciTech Connect (OSTI)

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

155

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

156

The effects of orientation angle, subcooling, heat flux, mass flux, and pressure on bubble growth and detachment in subcooled flow boiling  

E-Print Network [OSTI]

The effects of orientation angle, subcooling, heat flux, mass flux, and pressure on bubble growth and detachment in subcooled flow boiling were studied using a high-speed video camera in conjunction with a two-phase flow ...

Sugrue, Rosemary M

2012-01-01T23:59:59.000Z

157

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

158

THORAX pretest prediction of a sodium-boiling transient in a 19-pin simulated LMFBR driver bundle  

SciTech Connect (OSTI)

Experiments will be conducted in the Thermal-Hydraulic Out-of-Reactor Safety-Shutdown Heat Removal System (THORS-SHRS) Assembly 1 loop at Oak Ridge National Laboratory (ORNL) to model the behavior of a reactor during degraded decay heat removal conditions. The test section is to consist of two parallel 19-pin electrically-heated driver bundles, typical of U.S. Large Developmental Plant (LDP) Liquid Metal Fast Breeder Reactor (LMFBR) design. Analysis of these experiments will include using THORAX, a two-dimensional boiling model which assumes an equilibrium mixture two-phase flow (with slip). A THORAX prediction is presented for a single-bundle forced convection boiling-to-dryout transient at 15.8 kW/pin.

Rose, S.D.

1982-01-01T23:59:59.000Z

159

Technology, safety and costs of decommissioning a Reference Boiling Water Reactor Power Station. Main report. Volume 1  

SciTech Connect (OSTI)

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.

Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

1980-06-01T23:59:59.000Z

160

Study of plutonium disposition using existing GE advanced Boiling Water Reactors  

SciTech Connect (OSTI)

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

Note: This page contains sample records for the topic "naph tha 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

The Neutronics Design and Analysis of a 200-MW(electric) Simplified Boiling Water Reactor Core  

SciTech Connect (OSTI)

A 200-MW(electric) simplified boiling water reactor (SBWR) was designed and analyzed under sponsorship of the U.S. Department of Energy Nuclear Energy Research Initiative program. The compact size of a 200-MW(electric) reactor makes it attractive for countries with a less well developed engineering infrastructure, as well as for developed countries seeking to tailor generation capacity more closely to the growth of their electricity demand. The 200-MW(electric) core design reported here is based on the 600-MW(electric) General Electric SBWR core, which was first analyzed in the work performed here in order to qualify the computer codes used in the analysis. Cross sections for the 8 x 8 fuel assembly design were generated with the HELIOS lattice physics code, and core simulation was performed with the U.S. Nuclear Regulatory Commission codes RELAP5/PARCS. In order to predict the critical heat flux, the Hench-Gillis correlation was implemented in the RELAP5 code. An equilibrium cycle was designed for the 200-MW(electric) core, which provided a cycle length of more than 2 yr and satisfied the minimum critical power ratio throughout the core life.

Tinkler, Daniel R.; Downar, Thomas J. [Purdue University (United States)

2003-06-15T23:59:59.000Z

162

FORMOSA-B: A Boiling Water Reactor In-Core Fuel Management Optimization Package II  

SciTech Connect (OSTI)

As part of the continuing development of the boiling water reactor in-core fuel management optimization code FORMOSA-B, the fidelity of the core simulator has been improved and a control rod pattern (CRP) sampling capability has been added. The robustness of the core simulator is first demonstrated by benchmarking against core load-follow depletion predictions of both SIMULATE-3 and MICROBURN-B2 codes. The CRP sampling capability, based on heuristic rules, is next successfully tested on a fixed fuel loading pattern (LP) to yield a feasible CRP that removes the thermal margin and critical flow constraint violations. Its performance in facilitating a spectral shift flow operation is also demonstrated, and then its significant influence on the cost of thermal margin is presented. Finally, the heuristic CRP sampling capability is coupled with the stochastic LP optimization capability in FORMOSA-B - based on simulated annealing (SA) - to solve the combined CRP-LP optimization problem. Effectiveness of the sampling in improving the efficiency of the SA adaptive algorithm is shown by comparing the results to those obtained with the sampling turned off (i.e., only LP optimization is carried out for the fixed reference CRP). The results presented clearly indicate the successful implementation of the CRP sampling algorithm and demonstrate FORMOSA-B's enhanced optimization features, which facilitate the code's usage for broader optimization studies.

Karve, Atul A.; Turinsky, Paul J. [North Carolina State University (United States)

2000-07-15T23:59:59.000Z

163

Protective coatings for radiation control in boiling water nuclear power reactors  

SciTech Connect (OSTI)

Stainless-steel surfaces (316 nuclear grade) develop /sup 60/Co-embedded oxide scales when exposed to a boiling water reactor (BWR) environment. Thin films such as Pd, Ni, Au, and Cr were found to drastically reduce the radioactive buildup. The films were prepared by vacuum evaporation and electroless deposition. The electroless coating consisted of a thin cathodically treated layer, followed by a nickel strike (--1 ..mu..m) and an electroless layer (--600 A). The present paper describes the results obtained from a transmission electron microscope replica study of the radioactive growths that formed on uncoated and thin-film-coated stainless-steel rods. The coated rods, when exposed to a simulated BWR environment, exhibited corrosion film growths ranging from large faceted grains (uncoated) and isolated islands of similar crystallites (Au coated) to extremely small nucleated growths (Pd, Ni coated). Also, it was found that chromium oxide films, which generally form a protective oxide on stainless steel, do not completely stop either the corrosion film growth or the associated radioactive buildup. The morphologies of the corrosion film growth were correlated with the relative /sup 60/Co activity, and the substrate topography. The best coating to date was found to be a Pd thin film, 1000 A thick, which reduced the radioactive buildup by a factor of --13.

Rao, T.V.; Vook, R.W.; Meyer, W.; Wittwer, C.

1987-07-01T23:59:59.000Z

164

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

SciTech Connect (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

165

Operational experience with and postirradiation examinations on boiling water reactor control rods  

SciTech Connect (OSTI)

The control rods of the KRBI-I 250-MW(electric) boiling water reactor contain Vipac B/sub 4/C powder in Type 304 stainless steel tubes as a neutron-absorbing material. Because of an increase in the reactor coolant /sup 3/H activity, defective control rods were suspected. The hot cell examination of a highly exposed control rod revealed B/sub 4/C losses. The mechanism of failure was shown to be B/sub 4/C swelling and stress corrosion cracking of the absorber tubes, followed by B/sub 4/C washout. The B/sub 4/C volume swelling is ..delta..V(%) = 0.851x + 0.0449x/sup 2/ (x = /sup 10/B decays in 10/sup 21/(n,..cap alpha..)/cm/sup 3/). The tube cracking starts at 30 to 35% and the B/sub 4/C washout at 50 to 55% local /sup 10/B burnup in the tubes.

Eickelpasch, N.; Seepolt, R.W.; Muellauer, J.; Spalthoff, W.

1983-03-01T23:59:59.000Z

166

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

SciTech Connect (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

167

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

SciTech Connect (OSTI)

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

168

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

SciTech Connect (OSTI)

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

169

Metallurgical failure analysis of a propane tank boiling liquid expanding vapor explosion (BLEVE).  

SciTech Connect (OSTI)

A severe fire and explosion occurred at a propane storage yard in Truth or Consequences, N.M., when a truck ran into the pumping and plumbing system beneath a large propane tank. The storage tank emptied when the liquid-phase excess flow valve tore out of the tank. The ensuing fire engulfed several propane delivery trucks, causing one of them to explode. A series of elevated-temperature stress-rupture tears developed along the top of a 9800 L (2600 gal) truck-mounted tank as it was heated by the fire. Unstable fracture then occurred suddenly along the length of the tank and around both end caps, along the girth welds connecting the end caps to the center portion of the tank. The remaining contents of the tank were suddenly released, aerosolized, and combusted, creating a powerful boiling liquid expanding vapor explosion (BLEVE). Based on metallography of the tank pieces, the approximate tank temperature at the onset of the BLEVE was determined. Metallurgical analysis of the ruptured tank also permitted several hypotheses regarding BLEVE mechanisms to be evaluated. Suggestions are made for additional work that could provide improved predictive capabilities regarding BLEVEs and for methods to decrease the susceptibility of propane tanks to BLEVEs.

Kilgo, Alice C.; Eckelmeyer, Kenneth Hall; Susan, Donald Francis

2005-01-01T23:59:59.000Z

170

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

SciTech Connect (OSTI)

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

171

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

SciTech Connect (OSTI)

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

172

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 (OSTI)

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

173

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

SciTech Connect (OSTI)

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

174

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

SciTech Connect (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

175

Steady-state film-boiling data in rod-bundle geometry and non-equilibrium correlation assessment  

SciTech Connect (OSTI)

A series of 22 steady-state, rod bundle, dispersed flow film boiling experiments has been performed in the Thermal-Hydraulic Test Facility (THTF), a pressurized-water loop containing 64 full-length electrically heated rods. Test parameters in the upflow experiments cover a wide range of conditions typical of those which might be encountered during a nuclear reactor loss-of-coolant accident. Local equilibrium fluid conditions were calculated using mass and energy conservation considerations. Experimentally determined heat transfer coefficients were compared to several available film boiling heat transfer correlations: Dougall-Rohsenow, Groeneveld 5.7, Groeneveld-Delorme, Chen, Jones-Zuber, and Yoder-Rohsenow. The Groeneveld 5.7 correlation tended to predict the data better than any other correlation tested. The Dougall-Rohsenow correlation tends to overpredict the data while the Yoder-Rohsenow correlation predicted the data better than the other nonequilibrium correlations examined. However, all of the nonequilibrium correlations generally underpredict the heat transfer.

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

1982-01-01T23:59:59.000Z

176

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

SciTech Connect (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

177

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

SciTech Connect (OSTI)

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

178

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 (OSTI)

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

179

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

SciTech Connect (OSTI)

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

180

Results and phenomena observed from the DF-4 BWR (boiling water reactor) control blade-channel box test  

SciTech Connect (OSTI)

The DF-4 in-pile fuel damage experiment, one of a series of tests performed as part of the USNRC's internationally sponsored severe fuel damage (SFD) program, and carried out at Sandia National Laboratories, addressed the behavior of boiling water reactor (BWR) fuel canisters and control blades in the high temperature environment of an unrecovered loss of coolant accident. The DF-4 test is described in some detail herein and results from the experiment are presented. Significant results from prior experiments in the series are also summarized. 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. This early melt and relocation phenomena could significantly influence the progression of meltdown in BWRs and should be considered in SFD accident analyses. 14 refs., 9 figs.

Gauntt, R.O.; Gasser, R.D.; Fryer, C.P.; Walker, J.V.

1988-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "naph tha 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

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

SciTech Connect (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

182

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

SciTech Connect (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

183

Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 1. Main report. Technical report, September 1977-October 1979  

SciTech Connect (OSTI)

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.

Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

1980-06-01T23:59:59.000Z

184

Standard test method for evaluating stress-corrosion cracking of stainless alloys with different nickel content in boiling acidified sodium chloride solution  

E-Print Network [OSTI]

1.1 This test method describes a procedure for conducting stress-corrosion cracking tests in an acidified boiling sodium chloride solution. This test method is performed in 25% (by mass ) sodium chloride acidified to pH 1.5 with phosphoric acid. This test method is concerned primarily with the test solution and glassware, although a specific style of U-bend test specimen is suggested. 1.2 This test method is designed to provide better correlation with chemical process industry experience for stainless steels than the more severe boiling magnesium chloride test of Practice G36. Some stainless steels which have provided satisfactory service in many environments readily crack in Practice G36, but have not cracked during interlaboratory testing using this sodium chloride test method. 1.3 This boiling sodium chloride test method was used in an interlaboratory test program to evaluate wrought stainless steels, including duplex (ferrite-austenite) stainless and an alloy with up to about 33% nickel. It may also b...

American Society for Testing and Materials. Philadelphia

2000-01-01T23:59:59.000Z

185

Preliminary design study of small long life boiling water reactor (BWR) with tight lattice thorium nitride fuel  

SciTech Connect (OSTI)

Neutronic performance of small long-life boiling water reactors (BWR) with thorium nitride based fuel has been performed. A recent study conducted on BWR in tight lattice environments (with a lower moderator percentage) produces small power reactor which has some specifications, i.e. 10 years operation time, power density of 19.1 watt/cc and maximum excess reactivity of about 4%. This excess reactivity value is smaller than standard reactivity of conventional BWR. The use of hexagonal geometry on the fuel cell of BWR provides a substantial effect on the criticality of the reactor to obtain a longer operating time. Supported by a tight concept lattice where the volume fraction of the fuel is greater than the moderator and fuel, Thorium Nitride give good results for fuel cell design on small long life BWR. The excess reactivity of the reactor can be reduced with the addition of gadolinium as burnable poisons. Therefore the hexagonal tight lattice fuel cell design of small long life BWR that has a criticality more than 20 years of operating time has been obtained.

Trianti, Nuri, E-mail: nuri.trianti@gmail.com, E-mail: szaki@fi.itba.c.id; Su'ud, Zaki, E-mail: nuri.trianti@gmail.com, E-mail: szaki@fi.itba.c.id; Arif, Idam, E-mail: nuri.trianti@gmail.com, E-mail: szaki@fi.itba.c.id [Nuclear Physics and Biophysics Research Group, Faculty of Mathematics and Natural Science, Bandung Institute of Technology (Ganesha 10 Bandung, Indonesia) (Indonesia); Riyana, EkaSapta [Nuclear Energy Regulatory Agency (BAPETEN) (Indonesia)

2014-09-30T23:59:59.000Z

186

Load follow simulation of three-dimensional boiling water reactor core by PACS-32 parallel microprocessor system  

SciTech Connect (OSTI)

The three-dimensional boiling water reactor (BWR) core following the daily load was simulated by the use of the processor array for continuum simulation (PACS-32), a newly developed parallel microprocessor system. The PACS system consists of 32 processing units (PUs) (microprocessors) and has a multiinstruction, multidata type architecture, being optimum to the numerical simulation of the partial differential equations. The BWR core model includes the modified twogroup finite difference, coarse-mesh model for neutronics, steady-state model for thermohydraulics, criticality control by core coolant flow, and the time-dependent solution of iodine-xenon dynamics with constant flux level. The analysis of the parallel processing program revealed that the overhead is independent from the number of PUs and that the efficiency of PUs, i.e., the ratio of effective calculation over total, amounts to 75%, even up to 90% if it is limited to the core part. Simulation was made on the daily load follow for 144 h including the weekend, which took 1.3 central processing unit hours by the PACS system. The PACS system demonstrated a computation speed nearly one-tenth that of the large-scale high-speed general purpose computer, with a 25 times better cost performance ratio and showed that the system could be used as the pratical BWR core simulator with more complicated core models.

Hoshino, T.; Shirakawa, T.

1982-03-01T23:59:59.000Z

187

Summary and bibliography of safety-related events at boiling-water nuclear power plants as reported in 1979  

SciTech Connect (OSTI)

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 1979. The 1345 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. Keyword and permuted-title indexes to facilitate location of individual abstracts are provided in full size 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 the failures, deficiencies noted, and the time of occurrence (i.e., during refueling, operation, testing, or construction). Some of the more interesting events that occurred during the year are reviewed in detail. 32 refs.

Scott, R.L.; Gallaher, R.B.

1981-06-01T23:59:59.000Z

188

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

SciTech Connect (OSTI)

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

189

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

SciTech Connect (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

190

Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 2. Appendices. Technical report, September 1977-October 1979  

SciTech Connect (OSTI)

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

191

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  

SciTech Connect (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

192

WAX DEPOSITION IN CRUDE OILS: A NEW APPROACH Antonio Fasano -Mario Primicerio  

E-Print Network [OSTI]

. Introduction Crude oils are complex mixtures containing parans, aromatics, naph- tenics, resins, asphaltenes

Primicerio, Mario

193

Dispersed flow film boiling  

E-Print Network [OSTI]

Dispersed flow consists of small liquid droplets entrained in a flowing vapor. This flow regime can occur in cryogenic equipment, in steam generators, and during nuclear reactor loss of coolant accidents. A theoretical ...

Yoder, Graydon L.

1980-01-01T23:59:59.000Z

194

Advanced nuclear reactor safety analysis: the simulation of a small break loss of coolant accident in the simplified boiling water reactor using RELAP5/MOD3.1.1  

E-Print Network [OSTI]

The thermal hydraulic simulation code RELAP5/MOD3.1.1 was utilized to model General Electric's Simplified Boiling Water Reactor plant. The model of the plant was subjected to a small break loss of coolant accident occurring from a guillotine shear...

Faust, Christophor Randall

1995-01-01T23:59:59.000Z

195

Analytical and Experimental Study of The Effects of Non-Condensable in a Passive Condenser System for The Advanced Boiling Water Reactor  

SciTech Connect (OSTI)

The main goal of the project is to study analytically and experimentally condensation heat transfer for the passive condenser system relevant to the safety of next generation nuclear reactor such as Simplified Boiling Water Reactor (BWR). The objectives of this three-year research project are to: (1) obtain experimental data on the phenomenon of condensation of steam in a vertical tube in the presence of non-condensable for flow conditions of PCCS, (2) develop a analytic model for the condensation phenomena in the presence of non-condensable gas for the vertical tube, and (3) assess the RELAP5 computer code against the experimental data. The project involves experiment, theoretical modeling and a thermal-hydraulic code assessment. It involves graduate and undergraduate students' participation providing them with exposure and training in advanced reactor concepts and safety systems

Shripad T. Revankar; Seungmin Oh

2003-09-30T23:59:59.000Z

196

Importance of Delayed Neutrons on the Coupled Neutronic-Thermohydraulic Stability of a Natural Circulation Heavy Water-Moderated Boiling Light Water-Cooled Reactor  

SciTech Connect (OSTI)

The coupled neutronic-thermohydraulic stability characteristics of a natural circulation heavy water-moderated boiling light water-cooled reactor was investigated analytically considering the effects of prompt and delayed neutrons. For this purpose, the reactor considered is the Indian Advanced Heavy Water Reactor. The analytical model considers a point kinetics model for the neutron dynamics, a homogeneous two-phase flow model for the coolant thermal hydraulics, and a lumped heat transfer model for the fuel thermal dynamics. A higher mode of oscillation having a frequency much greater than the density-wave oscillation frequency was observed if prompt neutrons alone were considered. The occurrence of a higher mode of oscillation was found to be dependent on the concentration of delayed neutrons, the void reactivity coefficient, and the fuel time constant. The core inlet subcooling is found to have different effects on the decay ratio of the fundamental and higher modes of oscillations. The influences of void reactivity coefficient and fuel time constant on the fundamental and higher modes of oscillations were also found to be opposite in nature.

Nayak, A.K. [Bhaha Atomic Research Centre (India); Aritomi, M. [Tokyo Institute of Technology (Japan); Raj, V. Venkat [Bhaha Atomic Research Centre (India)

2001-07-15T23:59:59.000Z

197

Technology, safety and costs of decommissioning a reference boiling water reactor power station: Technical support for decommissioning matters related to preparation of the final decommissioning rule  

SciTech Connect (OSTI)

Preparation of the final Decommissioning Rule by the Nuclear Regulatory Commission (NRC) staff has been assisted by Pacific Northwest Laboratory (PNL) staff familiar with decommissioning matters. These efforts have included updating previous cost estimates developed during the series of studies of conceptually decommissioning reference licensed nuclear facilities for inclusion in the Final Generic Environmental Impact Statement (FGEIS) on decommissioning; documenting the cost updates; evaluating the cost and dose impacts of post-TMI-2 backfits on decommissioning; developing a revised scaling formula for estimating decommissioning costs for reactor plants different in size from the reference boiling water reactor (BWR) described in the earlier study; and defining a formula for adjusting current cost estimates to reflect future escalation in labor, materials, and waste disposal costs. This report presents the results of recent PNL studies to provide supporting information in three areas concerning decommissioning of the reference BWR: updating the previous cost estimates to January 1986 dollars; assessing the cost and dose impacts of post-TMI-2 backfits; and developing a scaling formula for plants different in size than the reference plant and an escalation formula for adjusting current cost estimates for future escalation.

Konzek, G.J.; Smith, R.I.

1988-07-01T23:59:59.000Z

198

Light Water Reactor Sustainability Program Support and Modeling for the Boiling Water Reactor Station Black Out Case Study Using RELAP and RAVEN  

SciTech Connect (OSTI)

The existing fleet of nuclear power plants is in the process of extending its lifetime and increasing the power generated. In order to evaluate the impact of these two factors on the safety of the plant, the Risk Informed Safety Margin Characterization (RISMC) project aims to provide insight to decision makers through a series of simulations of the plant dynamics for different initial conditions (e.g., probabilistic analysis and uncertainty quantification). This report focuses, in particular, on the impact of power uprate on the safety of a boiled water reactor system. The case study considered is a loss of off-site power followed by the loss of diesel generators, i.e., a station black out (SBO) event. Analysis is performed by using a thermo-hydraulic code, i.e. RELAP-5, and a stochastic analysis tool currently under development at INL, i.e. RAVEN. Starting from the event tree models contained in SAPHIRE, we built the input file for RELAP-5 that models in great detail system dynamics under SBO conditions. We also interfaced RAVEN with RELAP-5 so that it would be possible to run multiple RELAP-5 simulation runs by changing specific keywords of the input file. We both employed classical statistical tools, i.e. Monte-Carlo, and more advanced machine learning based algorithms to perform uncertainty quantification in order to quantify changes in system performance and limitations as a consequence of power uprate. We also employed advanced data analysis and visualization tools that helped us to correlate simulation outcome such as maximum core temperature with a set of input uncertain parameters. Results obtained gave a detailed overview of the issues associated to power uprate for a SBO accident scenario. We were able to quantify how timing of safety related events were impacted by a higher reactor core power. Such insights can provide useful material to the decision makers to perform risk-infomed safety margins management.

Diego Mandelli; Curtis Smith; Thomas Riley; John Schroeder; Cristian Rabiti; Aldrea Alfonsi; Joe Nielsen; Dan Maljovec; Bie Wang; Valerio Pascucci

2013-09-01T23:59:59.000Z

199

The DF-4 fuel damage experiment in ACRR (Annual Core Research Reactor) with a BWR (Boiling Water Reactor) control blade and channel box  

SciTech Connect (OSTI)

The DF-4 test was an experimental investigation into the melt progression behavior of boiling water reactor (BWR) core components under high temperature severe core damage conditions. In this study 14 zircaloy clad UO{sub 2} fuel rods, and representations of the zircaloy fuel canister and stainless steel/B{sub 4}C control blade were assembled into a 0.5 m long test bundle. The test bundle was fission heated in a flowing steam environment, using the Annular Core Research Reactor at Sandia Laboratories, simulating the environmental conditions of an uncovered BWR core experiencing high temperature damage as a result residual fission product decay heating. The experimental results provide information on the thermal response of the test bundle components, the rapid exothermic oxidation of the zircaloy fuel cladding and canister, the production of hydrogen from metal-steam oxidation, and the failure behavior of the progressively melting bundle components. This information is provided in the form of thermocouple data, steam and hydrogen flow rate data, test bundle fission power data and visual observation of the damage progression. In addition to BWR background information, this document contains a description of the experimental hardware with details on how the experiment was instrumented and diagnosed, a description of the test progression, and a presentation of the on-line measurements. Also in this report are the results of a thermal analysis of the fueled test section of the fueled test section of the experiment demonstrating an overall consistency in the measurable quantities from the test. A discussion of the results is provided. 38 refs., 72 figs., 7 tabs.

Gauntt, R.O.; Gasser, R.D.; Ott, L.J. (Sandia National Labs., Albuquerque, NM (USA))

1989-11-01T23:59:59.000Z

200

Numerical simulation of CO2 leakage from a geologic disposal reservoir including transitions from super- to sub-critical conditions, and boiling of liquid of CO2  

SciTech Connect (OSTI)

The critical point of CO{sub 2} is at temperature and pressure conditions of T{sub crit} = 31.04 C, P{sub crit} = 73.82 bar. At lower (subcritical) temperatures and/or pressures, CO{sub 2} can exist in two different phase states, a liquid and a gaseous state, as well as in two-phase mixtures of these states. Disposal of CO{sub 2} into brine formations would be made at supercritical pressures. However, CO{sub 2} escaping from the storage reservoir may migrate upwards towards regions with lower temperatures and pressures, where CO{sub 2} would be in subcritical conditions. An assessment of the fate of leaking CO{sub 2} requires a capability to model not only supercritical but also subcritical CO{sub 2}, as well as phase changes between liquid and gaseous CO{sub 2} in sub-critical conditions. We have developed a methodology for numerically simulating the behavior of water-CO{sub 2} mixtures in permeable media under conditions that may include liquid, gaseous, and supercritical CO{sub 2}. This has been applied to simulations of leakage from a deep storage reservoir in which a rising CO{sub 2} plume undergoes transitions from supercritical to subcritical conditions. We find strong cooling effects when liquid CO{sub 2} rises to elevations where it begins to boil and evolve a gaseous CO{sub 2} phase. A three-phase zone forms (aqueous - liquid - gas), which over time becomes several hundred meters thick as decreasing temperatures permit liquid CO{sub 2} to advance to shallower elevations. Fluid mobilities are reduced in the three-phase region from phase interference effects. This impedes CO{sub 2} upflow, causes the plume to spread out laterally, and gives rise to dispersed CO{sub 2} discharge at the land surface. Our simulation suggests that temperatures along a CO{sub 2} leakage path may decline to levels low enough so that solid water ice and CO{sub 2} hydrate phases may be formed.

Pruess, Karsten

2003-03-31T23:59:59.000Z

Note: This page contains sample records for the topic "naph tha 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

ORNL rod-bundle heat-transfer test data. Volume 3. Thermal-hydraulic test facility experimental data report for test 3. 06. 6B - transient film boiling in upflow. [PWR  

SciTech Connect (OSTI)

Reduced instrument responses are presented for Thermal-Hyraulic Test Facility (THTF) Test 3.06.6B. This test was conducted by members of the Oak Ridge National Laboratory Pressurized-Water-Reactor (PWR) Blowdown Heat Transfer (BDHT) Separate-Effects Program on August 29, 1980. The objective of the program was to investigate heat transfer phenomena believed to occur in PWR's during accidents, including small and large break loss-of-coolant accidents. Test 3.06.6B was conducted to obtain transient film boiling data in rod bundle geometry under reactor accident-type conditions. The primary purpose of this report is to make the reduced instrument responses for THTF Test 3.06.6B available. Included in the report are uncertainties in the instrument responses, calculated mass flows, and calculated rod powers.

Mullins, C.B.; Felde, D.K.; Sutton, A.G.; Gould, S.S.; Morris, D.G.; Robinson, J.J.

1982-05-01T23:59:59.000Z

202

ORNL rod-bundle heat-transfer test data. Volume 7. Thermal-Hydraulic Test Facility experimental data report for test series 3. 07. 9 - steady-state film boiling in upflow  

SciTech Connect (OSTI)

Thermal-Hydraulic Test Facility (THTF) test series 3.07.9 was conducted by members of the Oak Ridge National Laboratory Pressurized-Water Reactor (ORNL-PWR) Blowdown Heat Transfer (BDHT) Separate-Effects Program on September 11, September 18, and October 1, 1980. The objective of the program is to investigate heat transfer phenomena believed to occur in PWRs during accidents, including small- and large-break loss-of-coolant accidents. Test series 3.07.9 was designed to provide steady-state film boiling data in rod bundle geometry under reactor accident-type conditions. This report presents the reduced instrument responses for THTF test series 3.07.9. Also included are uncertainties in the instrument responses, calculated mass flows, and calculated rod powers.

Mullins, C.B.; Felde, D.K.; Sutton, A.G.; Gould, S.S.; Morris, D.G.; Robinson, J.J.

1982-05-01T23:59:59.000Z

203

English-Lahu Lexicon  

E-Print Network [OSTI]

the trunk and edible fruit; (“earhole-tree”) na -ph? -m? =tree sp. (jungle) na-ph? . . . . . . . . . . . . . .Healing; Tree of Eternal Immunity na -ph? -m? =c? . . . . .

Matisoff, James A.

2006-01-01T23:59:59.000Z

204

Subcooled Boiling Near a Heated Wall  

SciTech Connect (OSTI)

Experimental measurements of void fraction, bubble frequency, and velocity are obtained in subcooled R-134a flowing over a heated flat plate near an unheated wall and compared to analytical predictions. The measurements were obtained for a fixed system pressure and mass flow rate (P = 2.4 MPa and w = 106 kg/hr) at various inlet liquid temperatures. During the experiments, electrical power was applied at a constant rate to one side of the test section. The local void fraction data, acquired with a hot-film anemometer probe, showed the existence of a significant peak near the heated wall and a smaller secondary peak near the unheated wall for the larger inlet subcoolings. Local vapor velocity data, taken with the hot-film probe and a laser Doppler velocimeter, showed broad maxima near the centerline between the heated and unheated plates. Significant temperature gradients near the heated wall were observed for large inlet subcooling. Bubble size data, inferred from measurements of void fraction, bubble frequency and vapor velocity, when combined with the measured bubble chord length distributions illustrate the transition from pure three dimensional spherical to two-dimensional planar bubble flow, the latter being initiated when the bubbles fill the gap between the plates. These various two-phase flow measurements were used for development of a multidimensional, four-field calculational method; comparisons of the data to the calculations show reasonable agreement.

T.A. Trabold; C.C. Maneri; P.F. Vassallo; D.M. Considine

2000-10-27T23:59:59.000Z

205

Self-Sustaining Thorium Boiling Water Reactors  

E-Print Network [OSTI]

A thorium-fueled water-cooled reactor core design approach that features a radially uniform composition of fuel rods in stationary fuel assembly and is fuel-self-sustaining is described. This core design concept is similar ...

Ganda, Francesco

206

Validation Data Plan Implementation: Subcooled Flow Boiling  

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

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207

Boiling Springs Geothermal Area | Open Energy Information  

Open Energy Info (EERE)

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208

Experimental Investigation of Subcooled Flow Boiling  

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

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209

The prediction of low quality boiling voids  

E-Print Network [OSTI]

Slug flow theory is used to predict the density in heated channels of various shapes. In order to make this calculation possible, measurements are made of the bubble rise velocity in annuli, tube bundles, and channels. It ...

Griffith, P.

1963-01-01T23:59:59.000Z

210

The mechanism of heat transfer in nucleate pool boiling  

E-Print Network [OSTI]

A criterion is developed for bubble initiation from a gas filled cavity on a surface in contact with a superheated layer of liquid. It is found that the temperature of bubble initiation on a given surface is a function of ...

Han, Chi-Yeh

1962-01-01T23:59:59.000Z

211

Risk based ISI application to a boiling water reactor  

SciTech Connect (OSTI)

The ASME Section XI Working Group on Implementation of Risk-Based Examination produced a code case to define risk-based selection rules that could be used for In-Service Inspection (ISI) of Class 1, 2, and 3 piping. To provide guidelines for practical implementation of the code case, EPRI sponsored work to develop evaluation procedures and criteria. As part of an EPRI sponsored pilot study, these procedures have been applied to a BWR plant. Piping within the scope of the existing Section XI program has been analyzed. The results of this effort indicate that implementation of RBISI programs can significantly reduce the cost and radiation exposure associated with in-service inspections. The revised program was compared to the previous program and a net gain in safety benefit was demonstrated.

Smith, A. [New York Power Authority, White Plains, NY (United States); Dimitrijevic, V.B.; O`Regan, P.J. [Yankee Atomic Electric Co., Bolton, MA (United States)

1996-12-01T23:59:59.000Z

212

Simulation of sodium boiling experiments with THERMIT sodium version  

E-Print Network [OSTI]

Natural and forced convection experiments(SBTF and French) are simulated with the sodium version of the thermal-hydraulic computer code THERMIT. Simulation is done for the test secti- -on with the pressure-velocity boundary ...

Huh, Kang Yul

1982-01-01T23:59:59.000Z

213

Cooling Boiling in Head Region - PACCAR Integrated Underhood...  

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

D.C. vss004routbort2010o.pdf More Documents & Publications Integrated External Aerodynamic and Underhood Thermal Analysis for Heavy Vehicles CRADA with PACCAR Experimental...

214

Pressure suppression containment system for boiling water reactor  

DOE Patents [OSTI]

A system for suppressing the pressure inside the containment of a BWR following a postulated accident. A piping subsystem is provided which features a main process pipe that communicates the wetwell airspace to a connection point downstream of the guard charcoal bed in an offgas system and upstream of the main bank of delay charcoal beds which give extensive holdup to offgases. The main process pipe is fitted with both inboard and outboard containment isolation valves. Also incorporated in the main process pipe is a low-differential-pressure rupture disk which prevents any gas outflow in this piping whatsoever until or unless rupture occurs by virtue of pressure inside this main process pipe on the wetwell airspace side of the disk exceeding the design opening (rupture) pressure differential. The charcoal holds up the radioactive species in the noncondensable gas from the wetwell plenum by adsorption, allowing time for radioactive decay before the gas is vented to the environs.

Gluntz, Douglas M. (San Jose, CA); Nesbitt, Loyd B. (San Jose, CA)

1997-01-01T23:59:59.000Z

215

A mathematical method for boiling water reactor control rod programming  

SciTech Connect (OSTI)

A new mathematical programming method has been developed and utilized in OPROD, an existing computer code for automatic generation of control rod programs as an alternative inner-loop routine for the method of approximate programming. The new routine is constructed of a dual feasible direction algorithm, and consists essentially of two stages of iterative optimization procedures Optimization Procedures I and II. Both follow almost the same algorithm; Optimization Procedure I searches for feasible solutions and Optimization Procedure II optimizes the objective function. Optimization theory and computer simulations have demonstrated that the new routine could find optimum solutions, even if deteriorated initial control rod patterns were given.

Tokumasu, S.; Hiranuma, H.; Ozawa, M.; Yokomi, M.

1985-12-01T23:59:59.000Z

216

Pressure suppression containment system for boiling water reactor  

DOE Patents [OSTI]

A system is disclosed for suppressing the pressure inside the containment of a BWR following a postulated accident. A piping subsystem is provided which features a main process pipe that communicates the wetwell airspace to a connection point downstream of the guard charcoal bed in an offgas system and upstream of the main bank of delay charcoal beds which give extensive holdup to offgases. The main process pipe is fitted with both inboard and outboard containment isolation valves. Also incorporated in the main process pipe is a low-differential-pressure rupture disk which prevents any gas outflow in this piping whatsoever until or unless rupture occurs by virtue of pressure inside this main process pipe on the wetwell airspace side of the disk exceeding the design opening (rupture) pressure differential. The charcoal holds up the radioactive species in the noncondensable gas from the wetwell plenum by adsorption, allowing time for radioactive decay before the gas is vented to the environs. 3 figs.

Gluntz, D.M.; Nesbitt, L.B.

1997-01-21T23:59:59.000Z

217

A New Method of Preparing Owl Pellets: Boiling in Naoh  

E-Print Network [OSTI]

Frederick W. Schueler Journal:  Bird Banding Volume:  43 Issue:  2 (April) Section:  General Notes Year:  1972 Pages:  142

218

Apparatus for pumping liquids at or below the boiling point  

DOE Patents [OSTI]

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

Bingham, Dennis N. (Idaho Falls, ID)

2002-01-01T23:59:59.000Z

219

AECU-4439 PHYSICS AND MATHEMATICS HYDRODYNAMIC ASPECTS OF BOILING...  

Office of Scientific and Technical Information (OSTI)

Corporation University of California Los Angeles, California - 2 - .w- UNITED STATES ATOMIC ENERGY COMMISSION Technical Information Service L E G A L N O T I C E This report...

220

Natural convection flows in parallel connected vertical channels with boiling  

E-Print Network [OSTI]

The steady-state flow configuration in an array of parallel heated channels is examined with the objective of predicting the behavior of a reactor during a loss of flow accident. A method of combining the results of single ...

Eselgroth, Peter Ward

1967-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "naph tha 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

Modeling acid-gas generation from boiling chloride brines  

E-Print Network [OSTI]

Analysis Preliminary calculations assuming pure CaCl 2 solutions were carried out to investigate relationships between salt concentration, HCl gas fugacity (? partial pressure), and condensate

Zhang, Guoxiang

2010-01-01T23:59:59.000Z

222

Geothermal Technology Breakthrough in Alaska: Harvesting Heat below Boiling  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAX POLICIES7.pdfFuel Cell VehicleEnergy (5Temperatures | Department of Energy

223

Cooling Boiling in Head Region - PACCAR Integrated Underhood Thermal and  

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

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224

PACCAR CRADA: Experimental Investigation in Coolant Boiling in a  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustion | Department ofT ib l L d F SSales LLCDieselEnergy Joining|ActionOWENSDepartment of3

225

NISTIR 5780 Enhancement of R123 Pool Boiling by the  

E-Print Network [OSTI]

This paper presents the heat transfer data used to file international patent WO 94/18282. The data consisted of Commerce Technology Administration National Institute of Standards and Technology #12;NISTIR 5780 of Building Technology Technology Administration 1000 Independence Avenue Mary L. Good, Under SecretaryforTechnology

Oak Ridge National Laboratory

226

Nucleate Boiling Model Liping C, Y. Sung, and V. Kucukboyaci  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the ContributionsArms Control R&DNuclear fuel recycling in 4

227

Efficient Cooling in Engines with Nucleate Boiling | Department of Energy  

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

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228

Flow Boiling Carolyn Coyle, Jacopo Buongiorno, Thomas McKrell  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsing ZirconiaPolicyFeasibilityFieldMinds" | NationalFlipping theWellhead NA NA

229

Enhanced Pool-Boiling Heat Transfer Using Nanostructured Surfaces - Energy  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsing Zirconia NanoparticlesSmartAffects the Future Energy Mix Click to

230

Efficient Cooling in Engines with Nucleated Boiling | Department of Energy  

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

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231

CRADA with PACCAR Experimental Investigation in Coolant Boiling in a  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-Up fromDepartmentTie Ltd:June 2015 <Ones |Laboratory, JuneDid31-2,Rev. 0) |Half-Heated

232

AECU-4439 PHYSICS AND MATHEMATICS HYDRODYNAMIC ASPECTS OF BOILING HEAT  

Office of Scientific and Technical Information (OSTI)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartmentNationalRestart ofMeasuring Dopamine Release in the Human Brain withA. A.AECU-4439

233

A TEN MEGAWATT BOILING HETEROGENEOUS PACKAGE POWER REACTOR. Reactor...  

Office of Scientific and Technical Information (OSTI)

A reactor and associated power plant designed to produce 1.05 Mwh and 3.535 Mwh of steam for heating purposes are described. The total thermal output of the reactor is 10 Mwh....

234

Separate effects of surface roughness, wettability and porosity on boiling heat transfer and critical heat flux and optimization of boiling surfaces  

E-Print Network [OSTI]

The separate effects of surface wettability, porosity, and roughness on critical heat flux (CHF) and heat transfer coefficient (HTC) were examined using carefully-engineered surfaces. All test surfaces were prepared on ...

O'Hanley, Harrison Fagan

2012-01-01T23:59:59.000Z

235

The effect of surface conditions on nuceate pool boiling heat transfer to sodium  

E-Print Network [OSTI]

A simplified theoretical model for bubble nucleation stability has been proposed, and an approximate stability criterion has been developed. This criterion contains both fluid and surfqce properties, and it predicts that ...

Marto, P. J.

1965-01-01T23:59:59.000Z

236

Accident source terms for boiling water reactors with high burnup cores.  

SciTech Connect (OSTI)

The primary objective of this report is to provide the technical basis for development of recommendations for updates to the NUREG-1465 Source Term for BWRs that will extend its applicability to accidents involving high burnup (HBU) cores. However, a secondary objective is to re-examine the fundamental characteristics of the prescription for fission product release to containment described by NUREG-1465. This secondary objective is motivated by an interest to understand the extent to which research into the release and behaviors of radionuclides under accident conditions has altered best-estimate calculations of the integral response of BWRs to severe core damage sequences and the resulting radiological source terms to containment. This report, therefore, documents specific results of fission product source term analyses that will form the basis for the HBU supplement to NUREG-1465. However, commentary is also provided on observed differences between the composite results of the source term calculations performed here and those reflected NUREG-1465 itself.

Gauntt, Randall O.; Powers, Dana Auburn; Leonard, Mark Thomas

2007-11-01T23:59:59.000Z

237

An experimental study of flow boiling characteristics of carbon dioxide in multiport mini channels  

E-Print Network [OSTI]

& Technology, Clear Water Bay, Kowloon, Hong Kong, China d Aluminum Technology Center, Showa Denko K.K. Oyama of CO2 flowing in a multi-port extruded aluminum test section, which had 10 circular channels, each. The promising applications of CO2 refrigeration systems include automotive air conditioning, heat pumps

Zhao, Tianshou

238

AN EXPERIMENTAL INVESTIGATION ON FLOW BOILING OF ETHYLENE-GLYCOL/WATER MIXTURE  

E-Print Network [OSTI]

are used in cooling the engines in automotive applications. To avoid the two-phase flow in the engine coefficient values over a small circular aluminum heater surface, 9.5-mm in diameter, placed at the bottom-glycol mixtures is in automotive engine cooling. Although this mixture has been used for over several decades

Kandlikar, Satish

239

Technology, safety and costs of decommissioning a reference boiling water reactor power station. Appendices. Volume 2  

SciTech Connect (OSTI)

Appendices are presented concerning the evaluations of decommissioning financing alternatives; reference site description; reference BWR facility description; radiation dose rate and concrete surface contamination data; radionuclide inventories; public radiation dose models and calculated maximum annual doses; decommissioning methods; generic decommissioning information; immediate dismantlement details; passive safe storage, continuing care, and deferred dismantlement details; entombment details; demolition and site restoration details; cost estimating bases; public radiological safety assessment details; and details of alternate study bases.

Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

1980-06-01T23:59:59.000Z

240

Thermal stability of a spherical shell heated by convection and cooled by boiling  

E-Print Network [OSTI]

), assume an equilibrium tem- perature T (r). To this add a perturbation term e aT(r, t) = e f(r), then T(r, t) = Te(r) + e f(r) and instability occurs for positive values of a. Substituting equation (5) into equations (2) ~ (3) and (4...), and remembering the linear property of the boundary value problem, eventually ( 2 der ) a 2 f ( ) 0 dr dr -k ~df r gqi(T(r, t)) aT f(r) r=rl k~df r ' r2 pq2(T(r, t)) bT f( ) r=r2 If the heat transfer is non-linear, it is proper to define the coefficients...

Qaim-Maqami, Hassan

1973-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "naph tha 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

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

DOE Patents [OSTI]

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

Gluntz, Douglas M. (San Jose, CA)

1996-01-01T23:59:59.000Z

242

Optimization of boiling water reactor control rod patterns using linear search  

SciTech Connect (OSTI)

A computer program for searching the optimal control rod pattern has been developed. The program is able to find a control rod pattern where the resulting power distribution is optimal in the sense that it is the closest to the desired power distribution, and it satisfies all operational constraints. The search procedure consists of iterative uses of two steps: sensitivity analyses of local power and thermal margins using a three-dimensional reactor simulator for a simplified prediction model; linear search for the optimal control rod pattern with the simplified model. The optimal control rod pattern is found along the direction where the performance index gradient is the steepest. This program has been verified to find the optimal control rod pattern through simulations using operational data from the Oyster Creek Reactor.

Kiguchi, T.; Doi, K.; Fikuzaki, T.; Frogner, B.; Lin, C.; Long, A.B.

1984-10-01T23:59:59.000Z

243

Chimney for enhancing flow of coolant water in natural circulation boiling water reactor  

DOE Patents [OSTI]

A chimney which can be reconfigured or removed during refueling to allow vertical removal of the fuel assemblies is disclosed. The chimney is designed to be collapsed or dismantled. Collapse or dismantlement of the chimney reduces the volume required for chimney storage during the refueling operation. Alternatively, the chimney has movable parts which allow reconfiguration of its structure. In a first configuration suitable for normal reactor operation, the chimney is radially constricted such that the chimney obstructs vertical removal of the fuel assemblies. In a second configuration suitable for refueling or maintenance of the fuel core, the parts of the chimney which obstruct access to the fuel assemblies are moved radially outward to positions whereas access to the fuel assemblies is not obstructed. 11 figs.

Oosterkamp, W.J.; Marquino, W.

1999-01-05T23:59:59.000Z

244

Chimney for enhancing flow of coolant water in natural circulation boiling water reactor  

DOE Patents [OSTI]

A chimney which can be reconfigured or removed during refueling to allow vertical removal of the fuel assemblies. The chimney is designed to be collapsed or dismantled. Collapse or dismantlement of the chimney reduces the volume required for chimney storage during the refueling operation. Alternatively, the chimney has movable parts which allow reconfiguration of its structure. In a first configuration suitable for normal reactor operation, the chimney is radially constricted such that the chimney obstructs vertical removal of the fuel assemblies. In a second configuration suitable for refueling or maintenance of the fuel core, the parts of the chimney which obstruct access to the fuel assemblies are moved radially outward to positions whereat access to the fuel assemblies is not obstructed.

Oosterkamp, Willem Jan (Oosterbeek, NL); Marquino, Wayne (San Jose, CA)

1999-01-05T23:59:59.000Z

245

Bottom head to shell junction assembly for a boiling water nuclear reactor  

DOE Patents [OSTI]

A bottom head to shell junction assembly which, in one embodiment, includes an annular forging having an integrally formed pump deck and shroud support is described. In the one embodiment, the annular forging also includes a top, cylindrical shaped end configured to be welded to one end of the pressure vessel cylindrical shell and a bottom, conical shaped end configured to be welded to the disk shaped bottom head. Reactor internal pump nozzles also are integrally formed in the annular forging. The nozzles do not include any internal or external projections. Stubs are formed in each nozzle opening to facilitate welding a pump housing to the forging. Also, an upper portion of each nozzle opening is configured to receive a portion of a diffuser coupled to a pump shaft which extends through the nozzle opening. Diffuser openings are formed in the integral pump deck to provide additional support for the pump impellers. The diffuser opening is sized so that a pump impeller can extend at least partially therethrough. The pump impeller is connected to the pump shaft which extends through the nozzle opening.

Fife, Alex Blair (San Jose, CA); Ballas, Gary J. (San Jose, CA)

1998-01-01T23:59:59.000Z

246

Pyrosequencing Reveals High-Temperature Cellulolytic Microbial Consortia in Great Boiling Spring after In Situ  

E-Print Network [OSTI]

; and the Joint Genome Institute at the DOE (CSP-182). The authors are grateful for support from Greg Fullmer ``first-generation'' biofuel technology, rely on fermentable sugars from plants traditionally utilized

Ahmad, Sajjad

247

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

248

Separate effects of surface roughness, wettability, and porosity on the boiling critical heat flux  

E-Print Network [OSTI]

The separate effects of surface wettability, porosity, and roughness on the critical heat flux (CHF) of water were examined using engineered surfaces. Values explored were 0, 5, 10, and 15??m for Rz (roughness), <5°, ?75°, ...

O'Hanley, Harry

249

Splashing and boiling mechanisms of melt layer losses of PFCs during plasma instabilities  

E-Print Network [OSTI]

that includes the heat transfer and vaporization effects is developed using the open-source OpenFoam CFD, heat transfer, and mass ex- change across the interface [10,11]. The critical velocity as a function of wavelength is analyzed for various values of plasma viscosity and heat transfer coefficient. The CFD solver

Harilal, S. S.

250

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

E-Print Network [OSTI]

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...

Cuevas Vivas, Gabriel Francisco

1995-01-01T23:59:59.000Z

251

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

E-Print Network [OSTI]

Thickness/di erence Neighborhood size Contact Angle Seebeck Coe cient ( V/K) Density (kg/m3) Surface Tension (N/m) or standard deviation Optimal delay time ? The Heaviside step function Contact angle Fraction of false nearest neighbors Electric... and simultaneous development of the mathematical theory of fractals, it is now possible to characterize chaotic systems. Deterministic chaos is commonly encountered in Rayleigh-Benard convection, motion of a double pendulum, various electronic oscillators, chemical...

Sathyamurthi, Vijaykumar

2011-02-22T23:59:59.000Z

252

Bottom head to shell junction assembly for a boiling water nuclear reactor  

DOE Patents [OSTI]

A bottom head to shell junction assembly which, in one embodiment, includes an annular forging having an integrally formed pump deck and shroud support is described. In the one embodiment, the annular forging also includes a top, cylindrical shaped end configured to be welded to one end of the pressure vessel cylindrical shell and a bottom, conical shaped end configured to be welded to the disk shaped bottom head. Reactor internal pump nozzles also are integrally formed in the annular forging. The nozzles do not include any internal or external projections. Stubs are formed in each nozzle opening to facilitate welding a pump housing to the forging. Also, an upper portion of each nozzle opening is configured to receive a portion of a diffuser coupled to a pump shaft which extends through the nozzle opening. Diffuser openings are formed in the integral pump deck to provide additional support for the pump impellers. The diffuser opening is sized so that a pump impeller can extend at least partially therethrough. The pump impeller is connected to the pump shaft which extends through the nozzle opening. 5 figs.

Fife, A.B.; Ballas, G.J.

1998-02-24T23:59:59.000Z

253

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.

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

1982-12-21T23:59:59.000Z

254

2010 Inspection and Status Report for the Boiling Nuclear Superheater (BONUS) Reactor Facility, Rincon, Puerto Rico  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofofOxford SiteToledo SiteTonawanda North Site Unit

255

Experimental study of third (HFC) and fourth generation (HFO) refrigerants during flow boiling in singularities.  

E-Print Network [OSTI]

??La réduction de charge de fluides frigorigčnes dans les systčmes de production de froid est un enjeu important s'inscrivant dans les politiques environnementales sur la… (more)

Padilla Gomez, Miguel David

2011-01-01T23:59:59.000Z

256

Feasibility of breeding in hard spectrum boiling water reactors with oxide and nitride fuels  

E-Print Network [OSTI]

This study assesses the neutronic, thermal-hydraulic, and fuel performance aspects of using nitride fuel in place of oxides in Pu-based high conversion light water reactor designs. Using the higher density nitride fuel ...

Feng, Bo, Ph. D. Massachusetts Institute of Technology

2011-01-01T23:59:59.000Z

257

Methods to assess quality of boiled sorghum, gruel and chapaties from sorghums with different kernel characteristics  

E-Print Network [OSTI]

carborundum wheel for 50 sec, The sample was sieved with a U. S Standard No 8 Sieve for 5 sec with shaking by hand. Overs of the sieve were air classified in a South Dakota Seed Blower for 1 min at a setting of 3 0, Weight of sample on the lower screen...

Waniska, Ralph Dean

1976-01-01T23:59:59.000Z

258

CASL - Initial Modeling and Analysis of the Departure from Nucleate Boiling  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-Series to someone6Energy, science, andAnalysis ofLink to ResourcesChallenge

259

Design, fabrication, packaging and testing of thin film thermocouples for boiling studies  

E-Print Network [OSTI]

for deposition, before and after use (from left to right). The left most source shows the bare tungsten bars, the next source was a used Alumel source and the other two sources were used Chromel sources. 42 Fig. 2.22 Metal Evaporator Used....25 Sources Used for Deposition. (Left from Right: Bare Tungsten Bars before Use, Used Alumel Source and Two Used Chromel Sources.) Chromium was used as an adhesion layer and was used to increase the adhesiveness of the targets to the substrate...

Sinha, Nipun

2009-06-02T23:59:59.000Z

260

EHD enhancement of boiling/condensation, heat transfer of alternate refrigerants. Final Report for 1993-1999  

SciTech Connect (OSTI)

The goal was to address the feasibility of frost control by the EHD technique for operating conditions and geometries of significance to refrigeration. The objective of the experimental investigation was to demonstrate by experiment the feasibility of the EHD technique for control of frost on a cold surface under operating conditions of direct significance to refrigeration applications.

Ohadi, M. M.

1999-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "naph tha 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.


261

The effect of thermal aging and boiling water reactor environment on Type 316L stainless steel welds  

E-Print Network [OSTI]

The thermal aging and consequent embrittlement of materials are ongoing issues in cast stainless steels and duplex stainless steels. Spinodal decomposition is largely responsible for the well known "475°C" embrittlement ...

Lucas, Timothy R

2011-01-01T23:59:59.000Z

262

Perfluorooctanoic acid Melting point ~55 C, boiling point ~190 C, pKa ~ 2.5, sparingly  

E-Print Network [OSTI]

developmental and other adverse effects in laboratory animals. · Flammable and forms hazardous products like HF the Parkersburg, WV · Eight companies (Arkema, Asahi, Ciba, Clariant, Daikin, 3M/Dyneon, DuPont, Solvay Solexis

Cohen, Robert E.

263

Measurement of near-surface void fraction and macrolayer thickness in boiling water and silica-based nanofluid  

E-Print Network [OSTI]

Nanofluids are engineered fluids that contain a suspension of nanoparticles in a pure substance. Nanoparticles can be any variety of metals, metal oxides, or ceramics. They have been shown to increase heat transfer properties ...

Lerch Andrew (Andrew J.)

2008-01-01T23:59:59.000Z

264

Multifractal Analysis of Chaotic Flashing-Induced Instabilities in Boiling Channels in the Natural-Circulation CIRCUS Facility  

E-Print Network [OSTI]

Engineering, SE-412 96 Göteborg, Sweden and Christian Marcel, Martin Rohde, and Tim van der Hagen Delft-sustained den- sity wave oscillations ~DWOs! in the reactor core,1,2 was observed in the very early days are typically encountered during start- up, i.e., at reduced core flow and relatively high power level, as well

Demazière, Christophe

265

Experimental investigation of effects of surface roughness, wettability and boiling-time on steady state and transient CHF for nanofluids  

E-Print Network [OSTI]

Critical Heat Flux (CHF) is one of the primary design constraints in a nuclear reactor. Increasing the CHF of water can enhance the safety margins of the current fleet of Light Water Reactors (LWRs) and/or increase their ...

Sharma, Vivek Inder

2012-01-01T23:59:59.000Z

266

On using film boiling to thermally decompose liquid organic chemicals: Application to ethyl acetate as a model compound  

E-Print Network [OSTI]

to provide for autothermal operation without external heat input owing to the exothermicity of the oxidative

Walter, M.Todd

267

An assessment of BWR (boiling water reactor) Mark-II containment challenges, failure modes, and potential improvements in performance  

SciTech Connect (OSTI)

This report assesses challenges to BWR Mark II containment integrity that could potentially arise from severe accidents. Also assessed are some potential improvements that could prevent core damage or containment failure, or could mitigate the consequences of such failure by reducing the release of fission products to the environment. These challenges and improvements are analyzed via a limited quantitative risk/benefit analysis of a generic BWR/4 reactor with Mark II containment. Point estimate frequencies of the dominant core damage sequences are obtained and simple containment event trees are constructed to evaluate the response of the containment to these severe accident sequences. The resulting containment release modes are then binned into source term release categories, which provide inputs to the consequence analysis. The output of the consequences analysis is used to construct an overall base case risk profile. Potential improvements and sensitivities are evaluated by modifying the event tree spilt fractions, thus generating a revised risk profile. Several important sensitivity cases are examined to evaluate the impact of phenomenological uncertainties on the final results. 75 refs., 25 figs., 65 tabs.

Kelly, D.L.; Jones, K.R.; Dallman, R.J. (EG and G Idaho, Inc., Idaho Falls, ID (USA)); Wagner, K.C. (Science Applications International Corp., Albuquerque, NM (USA))

1990-07-01T23:59:59.000Z

268

Departure from nucleate boiling and pressure drop prediction for tubes containing multiple short-length twisted-tape swirl promoters  

E-Print Network [OSTI]

Previous studies conducted at MIT showed that the power performance of an inverted pressurized water reactor (IPWR) conceptual design, i.e. the coolant and moderator are inverted such that the fuel is the continuous medium ...

Arment, Tyrell W. (Tyrell Wayne), 1988-

2012-01-01T23:59:59.000Z

269

Comparison of water boiling models against recent experimental data, with special emphasis on the bubble ebullition cycle  

E-Print Network [OSTI]

Using recently collected data which was measured with state-of-the-art techniques, models for nucleation site density, bubble departure diameter, and nucleation frequency were compared against the acquired data. The ...

Virgen, Matthew Miguel

2011-01-01T23:59:59.000Z

270

A Study of the Role of Adjoint-Equipped CFD in VUQ Analysis of Channel Boiling Simulations -Slides  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered‰PNGExperience hands-onASTROPHYSICSHeResearch Stochastic Process-BasedStudy

271

AFG AF AFGANISTAN ABN AL ALBANIA  

E-Print Network [OSTI]

SUI CH SUIZA SNM SR SURINAME SWZ SZ SWAZILANDIA THA TH TAILANDIA FOR TW TAIWAN TAN TZ TANZANIA TJN TJ

Escolano, Francisco

273

Report of the US Nuclear Regulatory Commission Piping Review Committee. Volume 1. Investigation and evaluation of stress corrosion cracking in piping of boiling water reactor plants  

SciTech Connect (OSTI)

IGSCC in BWR piping is occurring owing to a combination of material, environment, and stress factors, each of which can affect both the initiation of a stress-corrosion crack and the rate of its subsequent propagation. In evaluating long-term solutions to the problem, one needs to consider the effects of each of the proposed remedial actions. Mitigating actions to control IGSCC in BWR piping must be designed to alleviate one or more of the three synergistic factors: sensitized material, the convention BWR environment, and high tensile stresses. Because mitigating actions addressing each of these factors may not be fully effective under all anticipated operating conditions, mitigating actions should address two and preferably all three of the causative factors; e.g., material plus some control of water chemistry, or stress reversal plus controlled water chemistry.

Not Available

1984-08-01T23:59:59.000Z

274

BWRSAR (Boiling Water Reactor Severe Accident Response) calculations of reactor vessel debris pours for Peach Bottom short-term station blackout  

SciTech Connect (OSTI)

This paper describes recent analyses performed by the BWR Severe Accident Technology (BWRSAT) Program at Oak Ridge National Laboratory to estimate the release of debris from the reactor vessel for the unmitigated short-term station blackout accident sequence. Calculations were performed with the BWR Severe Accident Response (BWRSAR) code and are based upon consideration of the Peach Bottom Atomic Power Station. The modeling strategies employed within BWRSAR for debris relocation within the reactor vessel are briefly discussed and the calculated events of the accident sequence, including details of the calculated debris pours, are presented. 4 refs., 13 figs., 3 tabs.

Hodge, S.A.; Ott, L.J.

1988-01-01T23:59:59.000Z

275

Simulation of steady-state and transient sodium boiling experiments in a seven-pin bundle under flow rundown conditions by using BODYFIT-1FE code  

SciTech Connect (OSTI)

A seven-pin rod bundle under flow rundown conditions was simulated by using the computer code BODYFIT-1FE (BOunDarY-FITted Coordinate System - 1 phase, Fully-Elliptic). In this code, the complicated rod bundle configuration is first transformed into rectangular geometry with uniform meshes. The transformed governing equations for all the thermal-hydraulic variables are then solved. The results of the simulation are presented here. All the predicted values agree favorably with the measured data. 7 refs., 20 figs.

Chen, B.C.J.; Sha, W.T.

1981-01-01T23:59:59.000Z

276

Heat transfer enhancement in single-phase forced convection with blockages and in two-phase pool boiling with nano-structured surfaces  

E-Print Network [OSTI]

the average heat (mass) transfer by up to 8.5 and 7.0 times that for fully developed turbulent flow through a smooth channel at the same mass flow rate, respectively, in the smaller and larger hole-to-blockage area ratio (or smaller and larger hole diameter...

Ahn, Hee Seok

2007-09-17T23:59:59.000Z

277

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

SciTech Connect (OSTI)

This report summarizes the evaluations conducted during Phase 1C of the Pu Disposition Study have provided further results which reinforce the conclusions reached during Phase 1A & 1B: These conclusions clearly establish the benefits of the fission option and the use of the ABWR as a reliable, proven, well-defined and cost-effective means available to disposition the weapons Pu. This project could be implemented in the near-term at a cost and on a schedule being validated by reactor plants currently under construction in Japan and by cost and schedule history and validated plans for MOX plants in Europe. Evaluations conducted during this phase have established that (1) the MOX fuel is licensable based on existing criteria for new fuel with limited lead fuel rod testing, (2) that the applicable requirements for transport, handling and repository storage can be met, and (3) that all the applicable safeguards criteria can be met.

Not Available

1994-01-15T23:59:59.000Z

278

A Characterization and Evaluation of Coal Liquefaction Process Streams. Results of Inspection Tests on Nine Coal-Derived Distillation Cuts in the Jet Fuel Boiling Range  

SciTech Connect (OSTI)

This report describes the assessment of the physical and chemical properties of the jet fuel (180-300 C) distillation fraction of nine direct coal liquefaction products and compares those properties to the corresponding specifications for aviation turbine fuels. These crude coal liquids were compared with finished fuel specifications specifically to learn what the refining requirements for these crudes will be to make them into finished fuels. The properties of the jet fuel fractions were shown in this work to require extensive hydrotreating to meet Jet A-1 specifications. However, these materials have a number of desirable qualities as feedstocks for the production of high energy-density jet fuels.

S. D. Brandes; R. A. Winschel

1999-12-30T23:59:59.000Z

279

EK424 THERMODYNAMICS AND STATISTICAL MECHANICS (Fall 2013) Thermodynamics is the study of processes (e.g., expansion of a gas, boiling of water, or diffusion  

E-Print Network [OSTI]

EK424 THERMODYNAMICS AND STATISTICAL MECHANICS (Fall 2013) Thermodynamics is the study in order to take place? We will study the thermodynamics of two types of processes: mechanical, or the chemical conversion of glucose into useful work), and a good understanding of thermodynamics is essential

Vajda, Sandor

280

EK424 THERMODYNAMICS AND STATISTICAL MECHANICS (Spring 2013) Thermodynamics is the study of processes (e.g., expansion of a gas, boiling of water, or diffusion  

E-Print Network [OSTI]

EK424 THERMODYNAMICS AND STATISTICAL MECHANICS (Spring 2013) Thermodynamics is the study in order to take place? We will study the thermodynamics of two types of processes: mechanical, or the chemical conversion of glucose into useful work), and a good understanding of thermodynamics is essential

Vajda, Sandor

Note: This page contains sample records for the topic "naph tha 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

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

E-Print Network [OSTI]

parameters due to closed loop system feedback. In turn, these cause over-circuit instability in the reactor. Core power generation changes are carried out by means of influencing the nuclear fission process through changing the multiplication factor...

Rezvyi, Aleksey

2012-06-07T23:59:59.000Z

282

Study of turbulent single-phase heat transfer and onset of nucleate boiling in high aspect ratio mini-channels to support the MITR LEU conversion/  

E-Print Network [OSTI]

Heat transfer in high aspect ratio mini-channels has important applications for materials test reactors using plate-type fuel. These fuel plates typically possess coolant channels with hydraulic diameters on the order of ...

Forrest, Eric Christopher

2014-01-01T23:59:59.000Z

283

Development of computer code models for analysis of subassembly voiding in the LMFBR : interim report of the MIT Sodium Boiling Project, covering work through September 30, 1979  

E-Print Network [OSTI]

The research program discussed in this report was started in FY1979 under the combined sponsorship of the U.S. Department of Energy (DOE), General Electric (GE) and Hanford Engineering Development Laboratory (HEDL). The ...

Finkle, William Dean

1979-01-01T23:59:59.000Z

284

Flow boiling enhancement on a horizontal heater using carbon nanotube coatings N. Singh, V. Sathyamurthy, W. Peterson, J. Arendt, D. Banerjee *  

E-Print Network [OSTI]

mechanisms (thermal and hydro-dy- namic interactions). Apart from the fluid and heater thermo-phys- ical enhancement has been explored in the literature using micro-scale as well as macro-scale features in round have also been reported in the litera- ture such as plate fin surface, micro-fins, twisted-tape inserts

Banerjee, Debjyoti

285

ACTINIDE PRODUCTION IN 136Xe BOMBARDMENTS OF 249Cf  

E-Print Network [OSTI]

onto the column in HHO. or HCl in a volume of lessin about 50ul of a 0.1M HHO_ solution. The walls of tha

Gregorich, K.E.

2010-01-01T23:59:59.000Z

286

Revue de l'OFCE / Prvisions 123 (2012) PAYS MERGENTS : FIN DE LA SURCHAUFFE  

E-Print Network [OSTI]

,2 % en 2011 (tableau 1). Les pays de l'Asean-4 (Indonésie, Malaisie, Philippines et Thaïlande) ont très

Boyer, Edmond

287

Manual  

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

SC Office of Science SOTR Subcontracting Officer's Technical Representative THA Task Hazard Analysis TJNAF Thomas Jefferson National Accelerator Facility TJSO Thomas...

288

E-Print Network 3.0 - ammonia policy context Sample Search Results  

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

<< < 1 2 3 4 5 > >> 41 Water Quality Assessment and Analysis in Tha Chin River Basin, Thailand Summary: ; most physico-chemical parameters, such as ammonia, nitrate, nitrite,...

289

2007-2008 Review of the Year Annual Review  

E-Print Network [OSTI]

Coilltearachd na h-Alba airson 2007-08. Is e seo a' chiad bliadhna san robh Ro-innleachd Coilltearachd Alba gu ro-innleachdail1 fhoillseachadh aig deireadh na bliadhna. Tha mise a' meas an lčirmheis seo mar iris an aghaidh blŕthachadh na cruinne - tha iad seo uile air meudachadh thar na bliadhna a chaidh seachad. Is e

290

Evaluation of the heterotic potential of sorghum [Sorghum bicolor (L.) Moench] adapted to the southern Africa region  

E-Print Network [OSTI]

635 hybrids (73.16 compared to 72.37% respectively). Two hybrids, ATx.631/(87EON366*90EON328)-LD30 and ATx631/ ((TAM428*SV1)*CE151)-LD3 had the highest yields (5.04 t/ha and 4.93 t/ha, respectively). These hybrids also had small grains with good...

Mpofu, Leo Thokoza

2007-04-25T23:59:59.000Z

291

Development of a real-time quantitative hydrologic forecasting model  

E-Print Network [OSTI]

TIME ) Ftgure 2. porno(lal f loni daaaga reduction aada possible hy a gives ruspanav ties (acr rrata forecast Ivad (Iacl. The do(ted ll?es In tha figure gives wt essnple uhlclt ahoun that as tha fnrecast land tlaa Incrva. as frua 4 to l4 hours...

Bell, John Frank

1986-01-01T23:59:59.000Z

292

WEEK 2 Cycle Menu Menu for: May 26 30, 2014 Baby Gator/Lake Alice Revised 5/6/14  

E-Print Network [OSTI]

Chicken Drumsticks w/ Barbeque sauce Alt: Boiled Egg Turkey Sandwiches Alt: Yogurt Vegetable or Fruit

Wu, Dapeng Oliver

293

WEEK 2 Cycle Menu Menu for: March 17 21, 2014 Baby Gator/Lake Alice Revised 10/2/13  

E-Print Network [OSTI]

Chicken Drumsticks w/ Barbeque sauce Alt: Boiled Egg Turkey Sandwiches Alt: Yogurt Vegetable or Fruit

Sheremet, Alexandru

294

The Role of Emerging Technologies in Improving Energy Efficiency: Examples from the Food Processing Industry  

E-Print Network [OSTI]

food. They include cooking, boiling, baking, drying, refrigerating/freezing, dehydration, pasteurizing, fermentation, and irradiation.

Lung, Robert Bruce; Masanet, Eric; McKane, Aimee

2006-01-01T23:59:59.000Z

295

EVOLVE Lithium Tray Thermal-Hydraulic Analysis Mark Anderson  

E-Print Network [OSTI]

(continued) · "Void Distribution in Boiling Pools with Internal Heat Generation", Kazimi & Chen, (LMFBR core

California at Los Angeles, University of

296

Alkyne Activation DOI: 10.1002/anie.201101090  

E-Print Network [OSTI]

2 T [8C] t [h] Yield [%][a] 1 CO2tBu Ph TES iPr RT 12 83 2 CO2Et H TES iPr 0 4 87 3 CO2Et H TES Bn 0 4 67 4 COSBu Ph TES iPr Ă?20 1 69 5 COStBu Ph TMS iPr Ă?20 1 67 6 COStBu Ph TIPS iPr Ă?20 1 75 7 COStBu Ph TES tBu Ă?20 1 78 8 COStBu vinyl TES iPr Ă?20 1 71 9 COStBu 2-naph TES iPr Ă?20 1 76 10 COStBu o

Lepore, Salvatore D.

297

Revised analyses of decommissioning for the reference boiling water reactor power station. Effects of current regulatory and other considerations on the financial assurance requirements of the decommissioning rule and on estimates of occupational radiation exposure - appendices. Final report  

SciTech Connect (OSTI)

The NRC staff is in need of decommissioning bases documentation that will assist them in assessing the adequacy of the licensee submittals, from the viewpoint of both the planned actions, including occupational radiation exposure, and the probable costs. The purpose of this reevaluation study is to update the needed bases documentation. This report presents the results of a review and reevaluation of the PNL 1980 decommissioning study of the Washington Public Power Supply System`s Washington Nuclear Plant Two (WNP-2) located at Richland, Washington, including all identifiable factors and cost assumptions which contribute significantly to the total cost of decommissioning the plant for the DECON, SAFSTOR, and ENTOMB decommissioning alternatives. These alternatives now include an initial 5-7 year period during which time the spent fuel is stored in the spent fuel pool prior to beginning major disassembly or extended safe storage of the plant. Included for information (but not presently part of the license termination cost) is an estimate of the cost to demolish the decontaminated and clear structures on the site and to restore the site to a {open_quotes}green field{close_quotes} condition. This report also includes consideration of the NRC requirement that decontamination and decommissioning activities leading to termination of the nuclear license be completed within 60 years of final reactor shutdown, consideration of packaging and disposal requirements for materials whose radionuclide concentrations exceed the limits for Class C low-level waste (i.e., Greater-Than-Class C), and reflects 1993 costs for labor, materials, transport, and disposal activities. Sensitivity of the total license termination cost to the disposal costs at different low-level radioactive waste disposal sites, to different depths of contaminated concrete surface removal within the facilities, and to different transport distances is also examined.

Smith, R.I.; Bierschbach, M.C.; Konzek, G.J.; McDuffie, P.N.

1996-07-01T23:59:59.000Z

298

In-vessel Retention Strategy for High Power Reactors - K-INERI Final Report (includes SBLB Test Results for Task 3 on External Reactor Vessel Cooling (ERVC) Boiling Data and CHF Enhancement Correlations)  

SciTech Connect (OSTI)

In-vessel retention (IVR) of core melt is a key severe accident management strategy adopted by some operating nuclear power plants and proposed for some advanced light water reactors (ALWRs). If there were inadequate cooling during a reactor accident, a significant amount of core material could become molten and relocate to the lower head of the reactor vessel, as happened in the Three Mile Island Unit 2 (TMI-2) accident. If it is possible to ensure that the vessel head remains intact so that relocated core materials are retained within the vessel, the enhanced safety associated with these plants can reduce concerns about containment failure and associated risk. For example, the enhanced safety of the Westinghouse Advanced 600 MWe PWR (AP600), which relied upon External Reactor Vessel Cooling (ERVC) for IVR, resulted in the U.S. Nuclear Regulatory Commission (US NRC) approving the design without requiring certain conventional features common to existing LWRs. However, it is not clear that currently proposed external reactor vessel cooling (ERVC) without additional enhancements could provide sufficient heat removal for higher-power reactors (up to 1500 MWe). Hence, a collaborative, three-year, U.S. - Korean International Nuclear Energy Research Initiative (INERI) project was completed in which the Idaho National Engineering and Environmental Laboratory (INEEL), Seoul National University (SNU), Pennsylvania State University (PSU), and the Korea Atomic Energy Research Institute (KAERI) investigated the performance of ERVC and an in-vessel core catcher (IVCC) to determine if IVR is feasible for reactors up to 1500 MWe.

F. B. Cheung; J. Yang; M. B. Dizon; J. Rempe

2005-01-01T23:59:59.000Z

299

4-50 A vertical piston-cylinder device is filled with water and covered with a 20-kg piston that serves as the lid. The boiling temperature of water is to be determined.  

E-Print Network [OSTI]

4-24 4-50 A vertical piston-cylinder device is filled with water and covered with a 20-kg piston in the cylinder is determined from a force balance on the piston, PA = PatmA + W W = mg Patm P or, kPa119.61 skg

Bahrami, Majid

300

Process for reforming naphthene and paraffin-containing hydrocarbons in the naphtha boiling range and isomerizing C sub 5 -C sub 6 normal paraffin feedstock to produce a high octane gasoline  

SciTech Connect (OSTI)

This patent describes a process for reforming a naphthenic and paraffin-containing hydrocarbon feedstock to produce a reformate product having an increased octane rating by contacting the feedstock with a reforming catalyst in the presence of hydrogen at reforming conditions in a reforming zone, the reforming zone including a naphtha dehydrogenation zone and a paraffin dehydrocyclization zone wherein heated, pressurized hydrogen is added to the effluent stream from the naphtha dehydrogenation zone prior to charging the effluent stream to the paraffin dehydrocyclization zone to produce a first product stream comprising a gasoline range reformate product having an RON octane rating of at least about 90 and hydrogen wherein the reformate product is separated from the hydrogen in a reformate separation zone. It comprises: charging at least a portion of the heated, pressurized hydrogen with a C{sub 5}-C{sub 6} n-paraffin feedstock to an isomerization zone containing an isomerization catalyst at isomerization conditions to produce a second product stream containing an isomerized C{sub 5}-C{sub 6} product and passing the second product stream to the reformate separation zone and recovering at least a major portion of the isomerized C{sub 5}-C{sub 6} product with the reformate product.

Dalson, M.H.

1990-05-08T23:59:59.000Z

Note: This page contains sample records for the topic "naph tha 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

13 novembre 2013 INVITATION PRESSE  

E-Print Network [OSTI]

doctorales au Sud (Sénégal, Maroc, Burkina-Faso, Thaïlande...). Le développement économique - le Pôle de

302

Over-Current Protection Scheme for SiC Power MOSFET DC Circuit Breaker  

E-Print Network [OSTI]

V. Radun, “SiC based solid state power controller,” in 23tha solid-state circuit breaker based on SiC power MOSFET withSolid-state DC circuit breakers made of the modern wide bandgap power

Zhang, Yuan; Liang, Yung C.

2015-01-01T23:59:59.000Z

303

Matrix monotonicity and self-concordance: how to handle quantum ...  

E-Print Network [OSTI]

Let V be a finite-dimensional power associative algebra over F with an ..... Tha function ?2 appears in compressed sensing (and is known as nuclear norm for p

2014-08-28T23:59:59.000Z

304

Variation in joint fluid composition and its effect on the tribology of replacement joint articulation  

E-Print Network [OSTI]

Polyethylene wear is a significant clinical problem limiting the long-term survival of joint replacement prostheses, particularly in total hip arthroplasty (THA) and total knee arthroplasty (TKA). Although the tribology ...

Mazzucco, Daniel Clarke, 1976-

2003-01-01T23:59:59.000Z

305

PREPARED FORTHE U.S. DEPARTMENT OF ENERGY, UNDER CONTRACT DEAC0276CH03073  

E-Print Network [OSTI]

ctome try J Krame r, R Nazikian, E Vale o Princeton Pla sma Physics La bora tory Princeton 08543­0451 E meters indica tha t ma gnetic field strength ca relia be mea in pla sma provided density fluctua

306

Experimental ornithosis in ewes (Ovis aries  

E-Print Network [OSTI]

, generalised vasculitis and reticulo- endothelial hyperplasia in the spleen and liver were present in most of tha turkeys, Pocal interstitial pneumonitis and pexivascular inflammatory reaction in the myocardium were sean less frequently. 24 Five turkeys...

Pierce, Kenneth Ray

1962-01-01T23:59:59.000Z

307

Actes de l'atelier du PCSI, 2-3 dcembre 2003, Montpellier, France 1 Le Goulven P., Bouarfa S., Kuper M., 2004. Gestion intgre  

E-Print Network [OSTI]

acteurs locaux Le cas du bassin versant de Pang Da, Nord Thaïlande Nicolas BECU*, Pascal PEREZ** *CEMAGREF'un bassin versant2 Gestion des bassins versants dans le Nord-Thaïlande Comme dans de nombreuses autres amont d'un point définissant son exutoire, est une unité de gestion également privilégiée dans le Nord

Paris-Sud XI, Université de

308

A study of selected criteria for real time control of intersections  

E-Print Network [OSTI]

criteria, used in the real time computer control of traffic, form the ob)ectives of this thesis. Traffic operations data were obtained from research work carried out on the Dallas Corridor Pro)act and the Houston Surveillance Project where computer... traffic control systems were in operation. Operational criteria, which includee tha prediction and use of vehicle arrivals, progression from intersection to intersection and tha effects of various move- ments wi'thin the intersection, were analyzed...

Romano, Elio Joseph

1973-01-01T23:59:59.000Z

309

arctic ecosystem final: Topics by E-print Network  

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

FROST-BOIL ECOSYSTEMS A PROJECT SUMMARY The central goal of this project to changing climate. We focus on frost-boils because: (1) The processes that are involved in the self...

310

Minimizing corrosion in coal liquid distillation  

DOE Patents [OSTI]

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

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

1985-01-01T23:59:59.000Z

311

Bui & Dinh VVDA.P6.01  

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

CASL-U-2013-0328-000 Figure 2.1. The pyramid of the subcooled boiling flow phenomenology 3. The subcooled flow boiling model describes the physics schematically...

312

Micro/Nano-Scale Phase Change Systems for Thermal Management and Solar Energy Conversion Applications  

E-Print Network [OSTI]

Enhancement in Pool Boiling of Nano-fluids,” InternationalLiquid Spreading Due to Nano/Microstructures on the CriticalWicking Action of Micro/Nano Structures on Pool Boiling

Coso, Dusan

2013-01-01T23:59:59.000Z

313

Study of chemistry and irradiation effects on nanofluids to be used in light water reactor accident cooling  

E-Print Network [OSTI]

Nanofluids, colloidal dispersions of nanoparticles in a base fluid, have shown enhancements in both pool boiling and flow boiling critical heat flux (CHF) in laboratory tests. The applicability of this aspect to nuclear ...

Lucas, Timothy R

2008-01-01T23:59:59.000Z

314

Direct production of fractionated and upgraded hydrocarbon fuels from biomass  

SciTech Connect (OSTI)

Multistage processing of biomass to produce at least two separate fungible fuel streams, one dominated by gasoline boiling-point range liquids and the other by diesel boiling-point range liquids. The processing involves hydrotreating the biomass to produce a hydrotreatment product including a deoxygenated hydrocarbon product of gasoline and diesel boiling materials, followed by separating each of the gasoline and diesel boiling materials from the hydrotreatment product and each other.

Felix, Larry G.; Linck, Martin B.; Marker, Terry L.; Roberts, Michael J.

2014-08-26T23:59:59.000Z

315

University Residence Halls Summer Residential  

E-Print Network [OSTI]

-style fish boil served on the sho and organic offerings and home baked desserts bring raves from our guests

Scharer, John E.

316

Hydrogen Storage Options: Technologies and Comparisons for Light-Duty Vehicle Applications  

E-Print Network [OSTI]

hydrogen compressor in parallel with their system to compress boil-off gas. In general the system costs

Burke, Andy; Gardiner, Monterey

2005-01-01T23:59:59.000Z

317

R*6 Report No. 129 Danish Atomic Energy Commission  

E-Print Network [OSTI]

of Boiling-Heavy-Water Nuclear Reactors Part II by Nick Kjær-Pedersen August, 1966 Salts distributor): Jul Commiwiofi, Riio, Rotkildc, Dnmtrk #12;August 1966 Kisd Report No. 129 Dynamic Aspects of Boiling-Heavy-Water of a boiling-heavy-water reactor. #12;- 2 - Preface The present report, together with Rise Report No. 128

318

Ankit Kalani e-mail: axk2161@rit.edu  

E-Print Network [OSTI]

-based cooling systems can occur. [DOI: 10.1115/1.4024595] Keywords: pool boiling, heat transfer enhancement, refrigerants, alcohols, binary mixture, and more recently nanofluids in pool boiling systems. Lowering Boiling With Ethanol at Subatmospheric Pressures for Electronics Cooling The growing trend

Kandlikar, Satish

319

LETTER doi:10.1038/nature11418 Stabilization of Leidenfrost vapour layer by textured  

E-Print Network [OSTI]

-called Leidenfrost regime, the low thermal conductivity of the vapour layer inhibits heat transfer between the hot from the nucleate-boiling to the film-boiling regime11­16 . As the low thermal conductivity-boiling phase. This result demonstrates that topological texture on superhydrophobic materials is critical

Chan, Derek Y C

320

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

Note: This page contains sample records for the topic "naph tha 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

The influence of frequency of milking and nursing upon twenty four hour milk production of Hereford cows  

E-Print Network [OSTI]

average yields. ISl. h yields were above average when ths cows were milked 2, 3, 4 or 6 times at evenly spaced 12-, 8, 6, or 4 heat intervals, 0if fsrancas in milk ytslds at tha diffarant milhtng intervals wars signifi c'ant hf tha 0. 01 level. Tha.... 9 78. 8 84 3 78. 9. 81. 7 L3. 7 14. 1 14. 9 145. 9 14. '6 12. 5 16. 3 14 4 . : 12'g$ f 130. 8 ' , 138', 1 13. 1:, '-' 13'' -C 11. 5 14. 4 'll 9225. 3 126. 7 12. 9 15. 8 11. 9~14. 4 LL. 5~13. 8 727. 9 72. 8 76. 8 84. 8 1'2 0 14, 1...

Chow, Guillermo

1964-01-01T23:59:59.000Z

322

Progress in the Development of Compressible, Multiphase Flow Modeling Capability for Nuclear Reactor Flow Applications  

SciTech Connect (OSTI)

In nuclear reactor safety and optimization there are key issues that rely on in-depth understanding of basic two-phase flow phenomena with heat and mass transfer. Within the context of multiphase flows, two bubble-dynamic phenomena – boiling (heterogeneous) and flashing or cavitation (homogeneous boiling), with bubble collapse, are technologically very important to nuclear reactor systems. The main difference between boiling and flashing is that bubble growth (and collapse) in boiling is inhibited by limitations on the heat transfer at the interface, whereas bubble growth (and collapse) in flashing is limited primarily by inertial effects in the surrounding liquid. The flashing process tends to be far more explosive (and implosive), and is more violent and damaging (at least in the near term) than the bubble dynamics of boiling. However, other problematic phenomena, such as crud deposition, appear to be intimately connecting with the boiling process. In reality, these two processes share many details.

R. A. Berry; R. Saurel; F. Petitpas; E. Daniel; O. Le Metayer; S. Gavrilyuk; N. Dovetta

2008-10-01T23:59:59.000Z

323

Evaluation of development of wild turkey habitat in New Mexico  

E-Print Network [OSTI]

hebeet L, 8yiaer 9eheittad to the Qxadaate whoa], of tha Agrtealtersl aad Roahaeieal Collage af Teaa? ie $Nthial fluff llllwet af tha ~aiJAsoet& feF tho 60~ of J ?eaarg, l958 Rior Sab)eats Wildlife Raeegesaet RFALUATION OF DEFHLORKNT OF NLD... TUHKZI HABITAT IH IE? RZCLCO Robert L. Spioer Approved ae to etFle and oontent bye Chalrjman of Coea1. ttee Head of or Stadent, Achrlsor Panner' p l$$S 'This studP was a pro)est of tho Federal kid Division of tho New Xoaieo Qaue and Pish...

Spicer, Robert L

1958-01-01T23:59:59.000Z

324

Studies on the vitamin B b6 srequirement of the chick  

E-Print Network [OSTI]

' this experiment show qu1te clearly the comparative activ1ties of the three forms of the vitamin for the growing ch1ck. V1t 1 ~B ~d*f1 l. ~gt* . Tl ft t 1t i B~ def1c1ency symptom observed in all deficient ch1cks, of each experiment, was an extreme... of vitamin B6. Harris and co-workars (1939) proved that vitamin B6 was a pyridina derivative, and ln accordance with this fact, Gyorgy (1939), suggested that tha term pyridoxine appeared to ba an appropiate name for tha new vi. tamin. Snail at al. (1942...

Perrett, Roy W

1954-01-01T23:59:59.000Z

325

The effects of chronic gamma radiation on the peripheral blood of Spanish goats  

E-Print Network [OSTI]

for her tachaicsl help in henatolo@r. The Radiological Health Division of. tha U. S. Public Health Sexvice sponsored the grant under which this pro)act wss conducted. The author is grateful to those who made this financial assistance available...&atitu of 9unoen's Holtip1e gangs Test ~ y ~ e ~ i ~ ~ s o ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ 23 5 Coapsrison of rad blood osll and related obsarwa- tions between a oontrol sale, ?ha outracing 40 r malo?and tbs last nels to die in tha 40 r group from weeks 6-12 after...

Leidy, Ross Bennett

1966-01-01T23:59:59.000Z

326

Riso Report No. 128 u Danish Atomic Energy Commission  

E-Print Network [OSTI]

Dynamic Aspects of Boiling-Heavy-Water Nuclear Reactors Parti by Niels Kjær-Pedersen August, 1966 5a of Boiling-Heavy-Water Nuclear Reactors P a r t i by ·Niels Kjær-Pedersen The Danish Atomic Energy Commission. In the third chapter a linearized transfer-function model of a cooling channel of a boiling-heavy-water reactor

327

Effect of surfactant on evaporative heat transfer coefficients in vertical film forced convection  

E-Print Network [OSTI]

for different concentrations of surfactant (log-log scale) (Boiling liquid flow rate of 1. 025 gpm) Evaporative coefficient as function of tempera- ture drop over the liquid film for different concentrations of surfactant (log-log scale) (Boiling liquid... flow rate of 1. 275 gpm) Evaporative coefficient as function of tempera- ture drop over the liquid film for different concentrations of surfactant (log-log scale) (Boiling liquid flow rate of 1. 55 gpm) 47 84 85 86 87 10 Evaporative...

Shah, Basit Husain

1972-01-01T23:59:59.000Z

328

Phenology of fruit development in cotton  

E-Print Network [OSTI]

. (August 1981) Apirath Thangsuphanich, B. S. , Kasetsart University Chairman of Advisory Committee: Dr. G. A. Niles To evaluate the growth development of cotton squares and boils, three Upland cotton cultivars and two treatment variables (a size series... but displayed a generalized dual sigmoid curve in cotton boils. Size development in cotton squares dis- played a linear pattern but displayed a sigmoid curve in cotton boils. iv ACKNOWLEDGMENTS I wish to express my sincere appreciation for the guid- ance...

Thangsuphanich, Apirath

1981-01-01T23:59:59.000Z

329

Radiation Effects on Metastable States of Superheated Water.  

E-Print Network [OSTI]

??Radiation Effects on Metastable States of Superheated Water covers theory, application, and experimentation into the behavior of water at temperatures above the boiling point. The… (more)

Alvord, Charles William

2008-01-01T23:59:59.000Z

330

E-Print Network 3.0 - annular two-phase flow Sample Search Results  

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

Rensselaer Polytechnic Institute Collection: Engineering 54 Boiling heat transfer in a hydrofoil-based micro pin fin heat sink Summary: single-phase heat transfer coefficient at...

331

E-Print Network 3.0 - accurate heat transfer Sample Search Results  

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

Pennsylvania State University Collection: Engineering 11 Boiling heat transfer in a hydrofoil-based micro pin fin heat sink Summary: in large scatter and were not able to...

332

aicd advanced: Topics by E-print Network  

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. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

333

advanced quantra fticr: Topics by E-print Network  

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. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

334

advanced power plant: Topics by E-print Network  

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. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

335

advanced nuclear reactor: Topics by E-print Network  

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. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

336

advanced nuclear plant: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

337

advanced nuclear power: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

338

advanced gas-cooled reactor: Topics by E-print Network  

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. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

339

advanced computational model: Topics by E-print Network  

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. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

340

advanced metal-membrane technology-commercialization: Topics...  

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. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

Note: This page contains sample records for the topic "naph tha 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

advanced thermal reactor: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

342

advanced dynamic models: Topics by E-print Network  

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. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

343

advanced power group: Topics by E-print Network  

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. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

344

advanced coal-based power: Topics by E-print Network  

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. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

345

advanced test-analysis model: Topics by E-print Network  

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. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

346

advanced applications singapore: Topics by E-print Network  

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. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

347

advanced burner reactors: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

348

advanced self-shielding models: Topics by E-print Network  

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. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

349

advanced application examples: Topics by E-print Network  

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. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

350

applying advanced model: Topics by E-print Network  

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. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

351

advanced accelerator applications: Topics by E-print Network  

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. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

352

advanced t-stage nasopharyngeal: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

353

advanced nuclear plants: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

354

advanced cervix carcinoma: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

355

advanced power systems: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

356

advanced burner reactor: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

357

advanced modeling tool: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

358

advanced oropharyngeal carcinoma: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

359

advanced unresectable rectal: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

360

advanced steam plant: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

Note: This page contains sample records for the topic "naph tha 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

advanced vulvar carcinomas: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

362

advanced maxillary sinus: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

363

advanced epidermoid carcinoma: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

364

advanced nsclc patients: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

365

advanced hypopharyngeal carcinoma: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

366

advanced intrahepatic cholangiocarcinoma: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

367

advanced large power: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

368

advanced beam-dynamics simulation: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

369

advanced radioisotope power: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

370

advanced steam plants: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

371

advanced ceramics advanced: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

372

advanced melanoma results: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

373

advanced passive plant: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

374

advanced hippotherapy simulator: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

375

advanced power plants: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

376

advanced model approaches: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

377

advanced nuclear reactors: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

378

advanced applications kyoto: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

379

advanced astroculture plant: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

380

advanced orthotopic hepatocellular: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

Note: This page contains sample records for the topic "naph tha 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

advanced unresectable non-small: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

382

advanced nasopharyngeal carcinoma: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

383

advanced thermal reactor fugen: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

384

advanced coolside sorbent: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

385

advanced power system: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

386

advanced gas-cooled reactors: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

387

advanced computational modeling: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

388

advanced fimbrial ectopic: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

389

advanced mixing models: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

390

aries advanced power: Topics by E-print Network  

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

. . . . 18 3.4.1 Heat Exchanger - Code description . . . . . . . . . . . . . . . 18 3.4.2 Simulation ResultsADVANCED POWER PLANT MODELING WITH APPLICATIONS TO THE ADVANCED BOILING...

391

VERA Documentation for Challenge Problem Solutions with VERA  

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

Page vi 3312014 ACRONYMS AMA Advanced Modeling Applications BWR boiling water reactor CASL Consortium for Advanced Simulation of Light Water Reactors CILC...

392

E-Print Network 3.0 - annotated geothermal bibliography Sample...  

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

for fluids flowing in geothermal systems was used to determine the heat effects of adsorption at a boiling Source: Stanford University - Department of Energy Resources...

393

E-Print Network 3.0 - advanced bwr nuclear Sample Search Results  

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

BWR6... pressurized and boiling water reactors with emphasis on the nuclear steam supply system and its associated... safety and control systems. Textbook: El-Wakil, M. M.,...

394

EA-1394: Final Environmental Assessment  

Broader source: Energy.gov [DOE]

Authorizing the Puerto Rico Electric Power Authority (PREPA) to allow Public Access to the Boiling Nuclear Superheat (BONUS) Reactor Building, Ricon, Puerto Rico

395

The Influence of Molecular Structure of Distillate Fuels on HFRR...  

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

stream was fractionated by NCUT into a boiling point range that corresponded to a Carbon Number range to minimize the viscosity effect on lubricity. 10 Lubricity High...

396

Thermal Control of Power Electronics of Electric Vehicles with...  

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

RelevanceObjectives Objectives: * Explore the potential of nucleate boiling for vehicle power electronics cooling. * Conduct numerical heat transfer simulations. * Experimentally...

397

Vehicle Technologies Office Merit Review 2014: Thermal Control...  

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

Thermal Control of Power Electronics of Electric Vehicles with Small Channel Coolant Boiling Vehicle Technologies Office Merit Review 2014: Thermal Control of Power Electronics of...

398

Geothermal Technology Breakthrough in Alaska: Harvesting Heat...  

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

exploration at lower temperatures, thanks to a technology breakthrough that allows geothermal energy to be produced at temperatures below the boiling point (212 degrees...

399

A COMPILATION OF DATA ON FLUIDS FROM GEOTHERMAL RESOURCES IN THE UNITED STATES  

E-Print Network [OSTI]

CALIF. DIV. OIL. GASI. CALIFORNIA GEOLOGY, P. It2(l97b).OIL AND GAS, SACRAMENTO (USA' J. F..EFEF.ENCE- CALIFORNIA GEOLOGY,

Cosner, S.R.

2010-01-01T23:59:59.000Z

400

augmented musculature device: Topics by E-print Network  

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

by shar- ing Tanaka, Jiro 7 A visualization comparison of convective flow boiling heat transfer augmentation devices Texas A&M University - TxSpace Summary: The qualitative...

Note: This page contains sample records for the topic "naph tha 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.


401

E-Print Network 3.0 - anaerobic bacterium isolated Sample Search...  

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

colonies with visually distinct morphologies were restreaked several times on R2A agar... plates. Pure bacterial colonies, picked from each isolate, were boiled in 50 l...

402

Analysis of thermal self-maintained oscillation mechanism in the thermionic reactor-converter with multielement TFE's  

SciTech Connect (OSTI)

Thermal self-maintained oscillations are found in the TOPAZ reactor. These are caused by periodical boiling of the coolant in sections of separate channels. (AIP)

Zrodnikov, A.V.; Pupko, V.Y.; Semenisty, V.L. (Institute of Physics Power Engineering, 249020 Obninsk, USSR (SU))

1991-01-05T23:59:59.000Z

403

Fluorescent Pigments for High-Performance Cool Roofing and Facades...  

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

3 Berkeley Lab Heat Island Group physicist Paul Berdahl inserts precursor solution into a furnace. After boiling and then combustion, a fluorescent red pigment is formed. Image:...

404

The Northwest Geysers High-Temperature Reservoir- Evidence For...  

Open Energy Info (EERE)

and add new constraints to genetic models of the system and its evolution. The intensity of the magmatic signal is inconsistent with deep boiling of connate or metamorphic...

405

Microsoft PowerPoint - Interface_Levin  

Office of Environmental Management (EM)

Adam H. Levin AHL Consulting May 14, 2014 BWR - Boiling Water Reactor DOE - Department of Energy DSC - Dry Storage Canister ISF - Interim Storage Facility ISFSI - Independent Spent...

406

Geological Problems in Radioactive Waste Isolation: Second Worldwide Review  

E-Print Network [OSTI]

capacity of 890 MWe at Loviisa and two boiling wateron, the spent fuel from Loviisa nuclear power station willpower companies will The Loviisa power plant units are based

2010-01-01T23:59:59.000Z

407

The effects of wavelength, metals, and reactive oxygen species on the sunlight inactivation of microorganisms: observations and applications to the solar disinfection of drinking water  

E-Print Network [OSTI]

Solar Disinfection of Drinking Water and Oral Rehydrationof Boiling to Disinfect Drinking Water in Rural Vietnam.Solar disinfection of drinking water and diarrhoea in Maasai

Fisher, Michael Benjamin

2011-01-01T23:59:59.000Z

408

E-Print Network 3.0 - atom connectivity index-based Sample Search...  

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

explain many impor- tant phenomena related to the phase... of melting, boiling, and sublimation temperatures on the inter- atomic potentials, the ... Source: Kim, Sehun -...

409

E-Print Network 3.0 - atom bound states Sample Search Results  

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

surface atoms can... to the very weakly bound surface atoms. In fact, boiling 12 and sublimation 13 have been observed... distribution of atoms in ... Source: Kim, Sehun -...

410

Reprintedfrom American Journal of Ophthalmology  

E-Print Network [OSTI]

. ROACH, PHD optical coherence tomography images 0ÂŁ macular laser lesions clearly demonstrated differences, Boiling AFB, District of Columbia (Dr Roach). This researchwassponsored by USAF Armstrong Laboratory

Boppart, Stephen

411

Progress Report Rad Effects in Concrete Bio Shield Final  

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

Pressurized water reactors (PWRs) typically exhibit higher radiation levels outside the PV than the boiling water reactors. Among the PWRs, the highest radiation levels outside...

412

CNS 2008 Template  

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

Bubble Departure Diameter, Bubble Departure Frequency, and Local Temperature Distribution in Subcooled Flow Boiling of Water B. Phillips, J. Buongiorno and T. McKrell...

413

A Review of Hazardous Chemical Species Associated with CO2 Capture from Coal-Fired Power Plants and Their Potential Fate in CO2 Geologic Storage  

E-Print Network [OSTI]

with conventional steam turbine powered electric generation.used to boil water for steam turbine generation as a secondturbine) and Rankine (steam turbine) cycles, as illustrated

Apps, J.A.

2006-01-01T23:59:59.000Z

414

Oxygen And Carbon Isotope Ratios Of Hydrothermal Minerals From...  

Open Energy Info (EERE)

boiling or by isotopic exchange at low waterrock ratios in new fractures. The mineralogy and apparent 18O enrichments of hydrothermal fracture-filling minerals are...

415

Aithisg Bhliadhnail Coilltearachd na h-Alba  

E-Print Network [OSTI]

' toirt thugaibh Lčirmheas Bliadhnail Ůghdarras Coilltearachd na h-Alba 2007-08. B' e seo a' chiad bliadhna. Tha mise a' meas an Lčirmheas seo mar `iris dhealbhach' an cois na h-Aithisg Bhliadhnail agus Ůghdarras na Coilltearachd a bhith dčanamh cinnteach gu lean an fhŕs seo agus gum bi e na bhuannachd do

416

Evidence for a dynamic and transient pathway through the TAT protein transport machinery  

E-Print Network [OSTI]

, University of Florida, Gainesville FL, USA Tat systems transport completely folded proteins across ion Categories: membranes & transport; proteins Keywords: chloroplasts; protein transport; thylakoid; trans transport machinery in thylakoids (called cpTat) consists of three membrane proteins; Tha4, Hcf106, and cp

417

A. E. K. Ris Title and uthor(s)  

E-Print Network [OSTI]

A. E. K. Risø Title and »uthor(s) Nuclear Accident dosimetry Measurement;- --tt ' -.» IAEA ir, "criticaiity areas" at Ris«. These include tha '"KAiiA criticality dosimeter for the measurement.ter- eoaparison of Nuclear Acciier.t Ixssixetry .Iv^teiL -,t rir.e.., I.X., - - ." April 197>. The performance

418

The Spatial Structure of Transnational Human Activity  

E-Print Network [OSTI]

Recent studies have shown that the spatial structures of animal displacements and local-scale human motion follow L\\'{e}vy flights. Whether transnational human activity (THA) also exhibits such a pattern has however not been thoroughly examined as yet. To fill this gap, this article examines the planet-scale spatial structure of THA (a) across eight types of mobility and communication and (b) in its development over time. Combining data from various sources, it is shown that the spatial structure of THA can indeed be approximated by L\\'{e}vy flights with heavy tails that obey power laws. Scaling exponent and power-law fit differ by type of THA, being highest in refuge-seeking and tourism and lowest in student exchange. Variance in the availability of resources and opportunities for satisfying associated needs appears to explain these differences. Over time, the L\\'{e}vy-flight pattern remains intact and remarkably stable, contradicting the popular idea that socio-technological trends lead to a "death of dista...

Deutschmann, Emanuel

2015-01-01T23:59:59.000Z

419

Robotic-Lab.COM Nanotechnology boosts anticancer drug cocktail many times over http://www.robotic-lab.com/en/2011/04/22/nanotechnology-boosts-anticancer-drug-cocktail-many-times-over/[5/2/2011 12:11:22 PM  

E-Print Network [OSTI]

treatments for Lymph Node Cancer today. CancerCenter.com/CareTha... Lovelace Breast Care Our Breast Care, Addiction Rehab & Detox All Private Rooms, Insurance OK TransformationsTreatment.... Lung cancer National Laboratories, the University of New Mexico, and the UNM Cancer Research and Treatment Center have

Brinker, C. Jeffrey

420

Tagore au Tibet  

E-Print Network [OSTI]

lang tha’e) et lePčre Goriot (Rgad po Ka’o) d’H. de Balzac, Le Collier (Mgul rgyan) de G. deMaupassant,30 et L’Illiade (Dbyi le ya the) et L’Odyssée (A’o te sa’e) d’Homčre.Etonnamment pour un lecteur français, Tagore y figurait également pourson roman...

Robin, Francoise

2005-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "naph tha 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

BAT RESEARCH NEWS Volume 37: Number 4 Winter 1996  

E-Print Network [OSTI]

, BAT RESEARCH NEWS Volume 37: Number 4 Winter 1996 Bat Collisions with Wind Turbines colliding with a lighthouse at LODg POlDL. OnWlo. Bat collisions with wind turbines used to produce e \\IIRA IS a 25·megawau faciluy and conSISts cf 73 KVS-33 wind turbines thaI were grouped InlO 10 Stnngs

422

The effect of different characteristics of the diluent on the viable count of certain psychrophilic bacteria  

E-Print Network [OSTI]

~ ~ ~ ~ ~ ~ ~ ?I tfha effest of differ'ant typaa of 4%neat end time of holding ia tha 4ilnent sn tba viable aecec (52o C~ 2 4ays) of eall suspensions of serious oultures of RafcIdoeonas groan in nutrient broth at M ~ ~ ~ 50 Rl Rhe offset of different type...

Patel, Sudhir Desaibhai

1965-01-01T23:59:59.000Z

423

Science S e A b d Ifeature Released upon receipt  

E-Print Network [OSTI]

t o tha interposition of the gods in human affairs. Nons of tho Grodk and Roman philosophers took and Athens' c a p , o r some great oak; and nhy, pray? Oaks some pre-lunar age. shunned his rage, evary one

424

Advisory function of the Tales of the Prophets (Qi?a? al-anbiy??)   

E-Print Network [OSTI]

This thesis examines the advisory function of the tales of three prophets (Joseph, David and Solomon) in al-?abar?’s (d. 923/310 AH) History and al-Tha?lab?’s (d. 1025/416) Tales of the Prophets within their religio-political ...

Helewa, Sami

2012-06-26T23:59:59.000Z

425

Emissions of air pollutants and greenhouse gases over1 Asian regions during 20002008: Regional Emission2  

E-Print Network [OSTI]

-3-9 Toranomon, Minato-ku, Tokyo, 105-0001, Japan}12 [5]{Ocean Policy Research Foundation, 3-4-10 Toranomon Singapore SGP Thailand THA Vietnam VNM Bangladesh OSA BGD Bhutan BTN India/Andhra Pradesh IND ANPR India/Bihar, Jharkhand BIHA India/Assam, Manipur, Meghalaya, Mizoram, Nagaland, Sikkim, Tripura EHIM India/Gujarat GUJA

Meskhidze, Nicholas

426

Kraith Collected Issue 2  

E-Print Network [OSTI]

, and descended frDa tha tran.porter platform a. he .urveyed the .paciou. Tran.porter Lobby of Babel Tower. There were perhaps two hundred people using the facility but it waan't crowded. '~r. Spock, do you .uppole we should try to call yout parents again...

Lichtenberg, Jacqueline

1975-01-01T23:59:59.000Z

427

Released upun reucipt bu.t intended f o r use  

E-Print Network [OSTI]

and color o f i t s surface, tha inclination of the surface to the m f s rays and the strength of the air CU colors Were placed i n the sun but sheltered as f a r as possibl%rom the cooling influence of the wind

428

ANOTHER REASON WHY WE SHOULD LOOK AFTER OUR CHILDREN  

E-Print Network [OSTI]

of simulations that explore the hypothesis that neural network learning issues alone are sufficient to result, it is neural network learning that will be studied. I have previously run simulations of the evolution of the simulations by using a learning mechanism, or an approximation of learning, tha

Bullinaria, John

429

-A Science Service Feature 0 bHY THE VdZATHEH 1  

E-Print Network [OSTI]

w i t h the prevailing distribution of temperature. In tha last analysis, the pre- The trade winds differences i n prossure come ultimately from differences i n temperature, vB,iling winds blow i n accordance engine driven by the sun. Tho general features of this engine would bc simple enough i f the earth did

430

INDIAN AGRICULTURAL STATISTICS RESEARCH INSTITUTE LIBRARY AVENUE, PUSA, NEW DELHI 110 012  

E-Print Network [OSTI]

{kkRdkj dh frfFk ,oa frfFk vko';d okaNuh; ,u-,-vkbZ-ih- }kjk foRr iksf"kr ifj;kstuk % ck;ksizkLiSDfVx vkQ tha

Rodriguez, Carlos

431

NUCLEAR ENERGY RENAISSANCE:NUCLEAR ENERGY RENAISSANCE: ADDRESSING THE CHALLENGES OF CLIMATE CHANGE AND SUSTAINABILITYADDRESSING THE CHALLENGES OF CLIMATE CHANGE AND SUSTAINABILITY  

E-Print Network [OSTI]

(PWRs) NONNON--LWR REACTORSLWR REACTORS ·· Heavy Water Reactors (CANDU)Heavy Water Reactors (CANDU Two PrincipalTwo Principal Classes:Classes: LIGHT WATER REACTORSLIGHT WATER REACTORS ·· Boiling Water Reactors (BWRs)Boiling Water Reactors (BWRs) ·· Pressurized Water Reactors (PWRs)Pressurized Water Reactors

432

Energy and Society Week 11 Section Handout  

E-Print Network [OSTI]

reactors and boiling water reactors? Light water reactors and heavy water reactors? #12;d. Nuclear waste energy out? c. Different reactor types -- what are the basic differences between pressurized water energy, and this energy can be used to boil water that is used to turn a turbine and create electricity

Kammen, Daniel M.

433

Appendix A. Material Safety Data Sheets for Drilling Mud MATERIAL SAFETY DATA SHEET  

E-Print Network [OSTI]

Trade Name: EZ-MUD® GOLD Revision Date: 01-Aug-2011 1. CHEMICAL PRODUCT AND COMPANY IDENTIFICATION Not applicable 3. HAZARDS IDENTIFICATION Hazard Overview May cause eye and skin irritation. Airborne dust may./gallon): 6.66-8.33 Bulk Density @ 20 C (lbs/ft3): 52 Boiling Point/Range (F): Not Determined Boiling Point

Torgersen, Christian

434

4 Science mvics Faature ? WHY THE VEA'L'IIER 7  

E-Print Network [OSTI]

t h e temperature at which water b o i l s . To US6 an approximate figure t h e boiling point a kettle and t h i s ie insufficient. Blanc, over 15,000 feet high, water boile at 185 degrees hot soups, leet they burn their mouths, so accustonad have they become t o lower temperatures+ On Mt

435

Evaluation of microbials for Heliothis zea (Boddie) control in Texas cotton  

E-Print Network [OSTI]

in the study. Very few boils were shed from weevil attack (Table 7, p. 32) . More data are presented in Table 55 (p. 92), in Appendix I. Naturall Shed S uares and Boils Relatively fsw squares were lost due to natural shed for the season (Table 8, p. 33...

Castillo, Pedro R.

1985-01-01T23:59:59.000Z

436

Photocleavage Agarose Gel Procedure A.Purify pUC 18 plasmid DNA  

E-Print Network [OSTI]

is placed in front of the lamp sample holder. 2. Prepare a grid laying out the appropriate components on stir plate with stir and heat both set to 6. Allow to heat and stir until it comes to a vigorous boil. Let boil a minute and remove from the heat. Gel mixture at this point should have turned from cloudy

Turro, Claudia

437

1 Copyright 2007 by ASME Proceedings of ASME ICNMM2007  

E-Print Network [OSTI]

number G ­ mass flux htp ­ two-phase heat transfer coefficient hlo ­ liquid-only heat transfer coefficient, htp, is determined differently for nucleate boiling dominant (NBD) and convective boiling flow regime and for microchannels are given below. Determination of htp: The liquid-only heat transfer

Kandlikar, Satish

438

VOLUME 86, NUMBER 6 P H Y S I C A L R E V I E W L E T T E R S 5 FEBRUARY 2001 Effect of Potential Energy Distribution on the Melting of Clusters  

E-Print Network [OSTI]

Department of Chemistry and School of Molecular Science (BK21), Korea Advanced Institute of Science of melting, boiling, and sublimation temperatures on the inter- atomic potentials, the existence of a surface that clusters can dissipate thermal energy even by boiling [12] and sublimation [13]. In some clusters

Kim, Sehun

439

Effect of Narrow Cut Oil Shale Distillates on HCCI Engine Performance  

SciTech Connect (OSTI)

In this investigation, oil shale crude obtained from the Green River Formation in Colorado using Paraho Direct retorting was mildly hydrotreated and distilled to produce 7 narrow boiling point fuels of equal volumes. The resulting derived cetane numbers ranged between 38.3 and 43.9. Fuel chemistry and bulk properties strongly correlated with boiling point.

Eaton, Scott J [ORNL; Bunting, Bruce G [ORNL; Lewis Sr, Samuel Arthur [ORNL; Fairbridge, Craig [National Centre for Upgrading Technology, Canada

2009-01-01T23:59:59.000Z

440

Coal liquefaction process  

DOE Patents [OSTI]

A process for the liquefaction of coal wherein raw feed coal is dissolved in recycle solvent with a slurry containing recycle coal minerals in the presence of added hydrogen at elevated temperature and pressure. The highest boiling distillable dissolved liquid fraction is obtained from a vacuum distillation zone and is entirely recycled to extinction. Lower boiling distillable dissolved liquid is removed in vapor phase from the dissolver zone and passed without purification and essentially without reduction in pressure to a catalytic hydrogenation zone where it is converted to an essentially colorless liquid product boiling in the transportation fuel range.

Wright, Charles H. (Overland Park, KS)

1986-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "naph tha 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

Post-test analysis of dryout test 7B' of the W-1 Sodium Loop Safety Facility Experiment with the SABRE-2P code. [LMFBR  

SciTech Connect (OSTI)

An understanding of conditions that may cause sodium boiling and boiling propagation that may lead to dryout and fuel failure is crucial in liquid-metal fast-breeder reactor safety. In this study, the SABRE-2P subchannel analysis code has been used to analyze the ultimate transient of the in-core W-1 Sodium Loop Safety Facility experiment. This code has a 3-D simple nondynamic boiling model which is able to predict the flow instability which caused dryout. In other analyses dryout has been predicted for out-of-core test bundles and so this study provides additional confirmation of the model.

Rose, S.D.; Dearing, J.F.

1981-01-01T23:59:59.000Z

442

Coal liquefaction process  

DOE Patents [OSTI]

A process is described for the liquefaction of coal wherein raw feed coal is dissolved in recycle solvent with a slurry containing recycle coal minerals in the presence of added hydrogen at elevated temperature and pressure. The highest boiling distillable dissolved liquid fraction is obtained from a vacuum distillation zone and is entirely recycled to extinction. Lower boiling distillable dissolved liquid is removed in vapor phase from the dissolver zone and passed without purification and essentially without reduction in pressure to a catalytic hydrogenation zone where it is converted to an essentially colorless liquid product boiling in the transportation fuel range. 1 fig.

Wright, C.H.

1986-02-11T23:59:59.000Z

443

18-Membered cyclic esters derived from glycolide and lactide: preparations, structures and coordination to sodium ions  

SciTech Connect (OSTI)

From reactions between glycolide or lactide (4 equiv.) with 4-dimethylaminopyridine, DMAP (1 equiv.) and NaBPh4 (1 equiv.) in benzene at 70 C the cyclic ester adducts (CH{sub 2}C(O)O){sub 6}NaBPh{sub 4} and (CHMeC(O)O){sub 6}NaBPh{sub 4} are formed respectively. The structures of the salts Na[(S,R,S,R,S,R)-(CH{sub 3}CHC(O)O){sub 6}]{sub 2}BPh{sub 4} {center_dot} CH{sub 3}CN and (CH{sub 2}C(O)O){sub 6}NaBPh{sub 4} {center_dot} (CH{sub 3}CN){sub 2} are reported. The cyclic esters were separated by chromatography and the structures of (CH{sub 2}C(O)O){sub 6}, (S,R,R,R,R,R)-(CHMeC(O)O){sub 6} and (S,S,R,R,R,R)-(CHMeC(O)O){sub 6} were determined. The {sup 1}H and {sup 13}C NMR data are reported for one of each of the six enantiomers of (CHMeC(O)O){sub 6} and the two meso isomers. The mechanism for the formation of these 18-membered rings is discussed in terms of an initial reaction between DMAP and NaBPh{sub 4} in hot benzene that produces NaPh and DMAP:BPh{sub 3} in the presence of the monomer lactide. The cyclic esters (CHMeC(O)O){sub 6} can also be obtained from the reaction between polylactide, PLA, in the presence of DMAP and NaBPh{sub 4}. The cyclic esters 3-methyl-1,4-dioxane-2,5-dione and 3,6,6-trimethyl-1,4-dioxane-2,5-dione undergo similar ring enlarging reactions to give cyclic 18-membered ring esters as determined by ESI-MS.

Chisholm, Malcolm H.; Gallucci, Judith C.; Yin, Hongfeng (OSU)

2008-06-30T23:59:59.000Z

444

An EnhancedDQ UMA/MC-CDMA Protocol for Wireless Packet Networks  

E-Print Network [OSTI]

Introduction Code collisionsal pa ket corruptions due to multipleaeg: = interference (MAI)aA importa t problems ina receiver-oriented slotted CDMA system. Since the number ofa va11fi]2 codes in request aquestg is limitedae genera#= the number of receiver-codepa]E a much less tha tha ofag1E e mobiles, code collisions ma y occur ina slotted ALOHA request mode. The origina DQRUMA/MC-CDMA protocol wa s designed for wirelesspa ket networksak it ha good properties sucha spiggyba king mechag][ to reduce request aestgfi= as bagfi==[gx1fi[E'gag fagfi==[gx1fi round-robin (BoD-FSRR)traD-FS schedulingpolicy with mahg umca1

Jae-Yoon Par Duk-Kyung; Summary Theori; z Dqruma/mc-cdma Protocol

2002-01-01T23:59:59.000Z

445

Regmi Research Series ,Year 15, December 31, 1983  

E-Print Network [OSTI]

:i.;ld subsequ ently conven e Par1.16lDent comprising the Dh.~radari_ Sabha 311d tha Rast;c.:..-Satho. acco rding to the cansti tut10nal 1> roe edu j: .; . 'I'he "func tions to be discharged by the Parllaulent Will be prescrtted in thr; Constitution; he r.~ e... :i.;ld subsequ ently conven e Par1.16lDent comprising the Dh.~radari_ Sabha 311d tha Rast;c.:..-Satho. acco rding to the cansti tut10nal 1> roe edu j: .; . 'I'he "func tions to be discharged by the Parllaulent Will be prescrtted in thr; Constitution; he r.~ e...

Regmi, Mahesh C

1983-01-01T23:59:59.000Z

446

Friedel Craft's synthesis and characterization of some acene quinone compounds  

SciTech Connect (OSTI)

The synthesis and characterization of some linear acene quinones of up to nine fused rings prepared by the Friedel-Craft's reaction of hydroquinone (HQ) and 1,4,9,10 tetrahydroxy anthracene (THA) with pyromellitic dianhydride (PMDA), and fused AlCl/sub 3/, was carried out. The intermediate product of the reaction of THA and PMDA, 1,4 dihydroxy anthraquinone, 6,7 dicarboxylic acid (DADCA) was also isolated and its synthesis optimized. This material was reduced to 1,4,9,10-tetrahydroxy anthracene 6,7-dicarboxylic acid (TADCA) and further dehydrated to its anhydride (TADCAmh). These compounds contain the necessary chemical functionalities which may lead to the facile synthesis of higher molecular weight quinones. These acene quinones show electronic spectral absorptions extending far into the NIR region, an indication of their long conjunction length.

Galleguillos, R.; Litt, M.; Rickert, S.E.

1987-01-01T23:59:59.000Z

447

An analysis of the accuracy of relative permeability  

E-Print Network [OSTI]

proportionality constant defined by Darcy's law, must be introduced. Darcy's law was originally derived for single phase flow through porous media (3, 4). In petroleum reservoirs, however, the rocks are usually saturated with two or more immiscible fluids... observations of water flowing through sand beds (4), is the fundamental relation used to describe the phenomenon of flow through porous media. This important law can be stated as: Tha rate of flow of a homogeneous fluid through a porous media...

Tao, Teh-Ming

1982-01-01T23:59:59.000Z

448

Use of artificial intelligence for process modeling and control  

E-Print Network [OSTI]

, recurrent neural networks constitute a simple and effective general method for static and dynmnic input-output mocleling of nonlinear systems. Design of a fuzzy logic control system for a biochemical system is also conducted, Fuzzification membership... method for input-output modeling of static and dynamic nonlinear systems vis, recurrent neural nctvvorks (RNNs) and design of a fuzzy logic control svstem for a biochcnzical process system. Simulation results show tha. t RNNs can learn nonlinear ste...

You, Yong

1991-01-01T23:59:59.000Z

449

Formulation of substrate removal kinetics in multi-component aqueous systems  

E-Print Network [OSTI]

are refractory to the biological culture, A refractory compound ls a chemical compound possessing a structure incapable of being broken by ensymes secreted by microorganisms. Additionally? knowledge of the kinetics of tha individual components could be used...-butanol, a refractory compound, was 0. 0322 as shown in Table 3. The exponential constant for the removal of 1-pentanol was 0, 0330 during the first ten hours, essentially the same as that for 2-methyl-2-butanol. however, the constant increased to 0...

Chaney, Ernest William

1967-01-01T23:59:59.000Z

450

David HOYRUP 30 aot 2005 EPIID/LEPII  

E-Print Network [OSTI]

, les Philippines et la Thaïlande (souvent regroupés sous l'appellation ASEAN-4 ou NPI 2) constituent un'une seconde vague de NPI, situés en Asie du Sud-Est, puis de la Chine, et enfin, des autres pays de l'ASEAN parler à la fois des institutions régionales (l'ASEAN en est à ce stade la seule réelle) et des

Paris-Sud XI, Université de

451

Sri Ganapathi Ragam: Sowrastram  

E-Print Network [OSTI]

; dNd | P ; ; P M-DPM gmPmg R R ; R ; || sri - ga na pa- - - -- thi- ni - - - -- - se ­ vim-pa ra--- - - - thi ni - - - - - se- vim-pa ra- - - - - - -- - - -- - - R ; -S R S ; R ; GMPM P, n d N d | P ; ; P M- D P M gmpd nsrs sndp mgrs || R ; re Sri tha ma- -- na ­vu- la- - ra - - - - - se- - vim-pa ra

Kalyanaraman, Shivkumar

452

pectively). Since our results also show gene-tic variability within the southern and central  

E-Print Network [OSTI]

considérable entre les échantillons provenant du nord de la Thaï- lande et ceux du centre et du sud, alors qu'il n'y avait guère de différenciation au sein des populations du nord et du sud. Ces résultats, basée sur des données morphologiques et des études du ADNmt, classent les abeilles du nord du pays et

Paris-Sud XI, Université de

453

Ragam: HANUMATH THODI (8TH Melakartha ragam)  

E-Print Network [OSTI]

Maruni kanna Sree Venkatesa Sukumara nannelu kora sarasuda N D D N D D N G M N D P M G R S | Ma - - - ru ku || D N S R G R G M G R N G R S N D | #12;ma - - - ra - nan - - - ne - - lu - - | N S R D N D G R | Da - - ni ma - - - ta - - lu - vi - ni | G , , M , , P D | N S , S N D P M || in - - tha - - sa

Kalyanaraman, Shivkumar

454

Wittgenstein on Practice and the Myth of the Giving  

E-Print Network [OSTI]

'' and "Pla n lo t L.i ' ing." In till' ro iiOidn~Junt• \\ It . Rohnh ( ir r u latecl a lt- ttc l Oil lw h a ll of tiH' Committee, pro p o:-.ing in ~OIIH ' Wlml hroadc 1 l t' l lll~ tha t l'l tt · in con1c from tlti .. f11nd ' lt ould ht· spent in a qunt...

Hurley, Susan

1995-01-01T23:59:59.000Z

455

Effects of variations in rate of temperature rise, curing temperature and size of specimen on selected physical properties of concrete made with type I cement and steam cured at atmospheric pressure  

E-Print Network [OSTI]

By Blear Olivieri-Cintrou Subsitted to tha Graduate Sobool of tba Agricultural aad Mechauieal College of Tares iu Partial fulfillaaat of the requiraaeats for tbe degree of MASTER OP SCIENCE May ISSS Ma)or gabfest: Civil Bagiaeeriug EPPECTS OP... to understand nore dully the influence of the various factors affecting stean curing& the Tense Transportation Institute in cooperation with the Departaant of Civil Engineering has started a progrm of research on this subject. This investigation is e part...

Olivieri-Cintron, Elmer

1958-01-01T23:59:59.000Z

456

Effect of viscosity of asphalt on stress strain and volume change characteristics of asphaltic mixtures  

E-Print Network [OSTI]

~ter Setup 6 Cceprossion Test Results 7 Mold for Trianial Tost Specinens 19 21 23 28 Scuble Plunger Conpaction Using Uuiversal Testing Machine 29 9 Shotch of Trianial Coll 10 Trianial Call Used in tha Study ll Shetch of Voluae Change Measuring... received continuous study. The main aim should be to sicmlate the ccmpacticn usually obtained under field conditions. Saac investigators used double plunger static compaction under a particular load for a selected time (8, 14, 31, 32)i Kneading...

Gandhi, Poduru Mohandas Karamchand

1966-01-01T23:59:59.000Z

457

An insoluble residue study of the Comanche Peak and Edwards limestones of Kimble County, Texas  

E-Print Network [OSTI]

. . . . . . . . . . . . . . . . . . . . . . . Previous investigations Comanche Peak and Edwards limestones. . Insoluble res idues 1 1 3 5 6 S tratigraphy Wa)nut clay. Conanche Peak limestone Edwards limestone. Georgetown limestone. 8 9 9 12 Paleontology Macropaleontology... on the basis of tha silt?clay insoluble residua y. Tectonic map of Early Cretaceous. Plate I. Vertical variation in insoluble residua content. . . . pocket vertical variation in sand-siss insoluble residue content Vertical vari. stion in sand...

Jurik, Paul Peter

1961-01-01T23:59:59.000Z

458

Changes in niacin content produced by nickel-chloride in a rust susceptible wheat and oat variety  

E-Print Network [OSTI]

ONANNES IN NIACIN CONTENT PRODUOE9 BT NICKEL-CNLORIBE IN k RSST SOSOEPTIBLE NNEST SNB OST VSRXETT k Thesis Suhnitted to the Graduate School of the SSricultural and Nechanical Collage- of Tunas in partial fulfillment of the requireneat.... d typical standard curve for tha growth of 17-5 f Idee b ill d l . . . . . . . . . . , . . . . . 12 I, The affeot of nickel-chloride sprays on niacin content of 131 wheat conpared to controls at thre~ ages4 ~ 4 ~ ~ 4...

Lacy, Logan Wayne

1961-01-01T23:59:59.000Z

459

The use of CEN38 in assessing evolutionary relationships in the genus Sorghum  

E-Print Network [OSTI]

University ? AusTRC number, Australian Tropical Crops and Forages Collection, Queensland Department of Primary Industries ? CANB = Australian National Herbarium, Canberra, ACT Australia ? BRI = Queensland Herbarium, Mt Coot-tha, QLD... are indigenous to Australia (Dillon et al., 2001). The other species of Sorghum are found in Africa, Central America and India (Garber, 1950). Species in the Sorghum genus have chromosome numbers of 2n = 10, 20, 30, and 40 (Garber, 1950; Lazarides et al...

Anderson, Jason Correnth

2005-11-01T23:59:59.000Z

460

The development of a passive dosimeter for airborne benzene vapors  

E-Print Network [OSTI]

entirely different from that usually employed in gas or vapor collection devices, as there is no need for pumps and airflow control s to provi de fi xed airflows or volumes. This principle, Ficks First Law of Diffusion, states tha t the rate of transfer...+ Ilay 1978 ABSTRACT The Development of a Passive Dosimeter for Airborne Benzene Vapor. ", . (Nay 1978) David Hilliam Hager, B. S. , University of Rochester; Chairman of Advisory Committee: Dr. David F. Ciapo Passive diffusion dosimeters offer...

Hager, David William

2012-06-07T23:59:59.000Z

Note: This page contains sample records for the topic "naph tha 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

J o u r n a lJ o u r n a l Volume 11 | 2008  

E-Print Network [OSTI]

H. Buckler, Professor, UVA School of Law, 1931 Inscribed on the face of Clay Hall Virginia JournalJ o u r n a lJ o u r n a l Volume 11 | 2008 uniVersity of Virginia School of law #12;VirginiaJ o u r n a l Volume 11 | 2008 University of Virginia School of law #12;ThaT Those alone may be servan

Acton, Scott

462

A frequency referenced digitally self-tuned approach to monolithic filter design  

E-Print Network [OSTI]

be taken in processing so tha& the component characteristics can be more accurately predicted and controlled. ln the future. technology may be developed which provides the requir& 8 ac&'uracy and repeatabfiity. However, these improvements will likely... be obtained at the expense of higher production costs and reductions in yield. Another approach which may be taken is external trimming '1'. Here, capacitors and/or resistors are fabricated such that they can be externally adjusted. This may take the form...

Fincher, Jeffrey Louis

1984-01-01T23:59:59.000Z

463

A BRIEF HISTORY OF THE DEPARTMENT OF ENERGY | Department of Energy  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: Alternative Fuels Data CenterEnergyAuthorizationSunShot Initiative1 Strategic Plan 2011420155thA

464

BWR Assembly Optimization for Minor Actinide Recycling  

SciTech Connect (OSTI)

The Primary objective of the proposed project is to apply and extend the latest advancements in LWR fuel management optimization to the design of advanced boiling water reactor (BWR) fuel assemblies specifically for the recycling of minor actinides (MAs).

G. Ivan Maldonado; John M. Christenson; J.P. Renier; T.F. Marcille; J. Casal

2010-03-22T23:59:59.000Z

465

Mississippi Nuclear Profile - Grand Gulf  

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

expiration date" 1,"1,251","9,643",88.0,"BWR","applicationvnd.ms-excel","applicationvnd.ms-excel" ,"1,251","9,643",88.0 "Data for 2010" "BWR Boiling Water Reactor."...

466

Minnesota Nuclear Profile - Monticello  

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

date","License expiration date" 1,554,"4,695",96.7,"BWR","applicationvnd.ms-excel","applicationvnd.ms-excel" ,554,"4,695",96.7 "Data for 2010" "BWR Boiling Water Reactor."...

467

Operating Experience and Test Results From An Ammonia-Based Dry/Wet Cooling System For Electric Power Stations  

E-Print Network [OSTI]

tower by heat rejection to the atmosphere. The condenser/ reboiler features Union carbide's doubly enhanced heat transfer tubing to boil ammonia on the inside and to condense the steam externally. System description and performance characteristics...

Allemann, R. T.; Werry, E. V.; Fricke, H. D.; Price, R. E.; Bartz, J. A.

1982-01-01T23:59:59.000Z

468

INSTITUTE OF PHYSICS PUBLISHING PHYSICS IN MEDICINE AND BIOLOGY Phys. Med. Biol. 49 (2004) 52955308 PII: S0031-9155(04)84030-2  

E-Print Network [OSTI]

or ms) y vertical coordinate (m) z nozzle-to-substrate distance (mm) Greek symbols thermal diffusivity and skin phantom remains in the nucleate boiling region even if T0 is 80 C. (Some figures in this article

Aguilar, Guillermo

469

Stress corrosion cracking and crack tip characterization of Alloy X-750 in light water reactor environments  

E-Print Network [OSTI]

Stress corrosion cracking (SCC) susceptibility of Inconel Alloy X-750 in the HTH condition has been evaluated in high purity water at 93 and 288°C under Boiling Water Reactor Normal Water Chemistry (NWC) and Hydrogen Water ...

Gibbs, Jonathan Paul

2011-01-01T23:59:59.000Z

470

Stress Corrosion Cracking and Crack Tip Characterization of Alloy X-750 in Light Water Reactor Environments  

E-Print Network [OSTI]

Stress corrosion cracking (SCC) susceptibility of Inconel Alloy X-750 in the HTH condition has been evaluated in high purity water at 93 and 288°C under Boiling Water Reactor Normal Water Chemistry (NWC) and Hydrogen Water ...

Gibbs, Jonathan Paul

471

Optimal Distributed Beamforming for MISO Interference Channels  

E-Print Network [OSTI]

In this thesis, the problem of quantifying the Pareto optimal boundary of the achievable rate region is considered over multiple-input single-output(MISO)interference channels, where the problem boils down to solving a sequence of convex feasibility...

Qiu, Jiaming

2012-07-16T23:59:59.000Z

472

Conceptual Design of Molten Salt Loop Experiment for MIT Research Reactor  

E-Print Network [OSTI]

Molten salt is a promising coolant candidate for Advanced High Temperature Reactor (AHTR) Gen-IV designs. The low neutron absorption, high thermal capacity, chemical inertness, and high boiling point at low pressure of ...

Bean, Malcolm K.

2011-08-01T23:59:59.000Z

473

Satish G. Kandlikar ASME Fellow  

E-Print Network [OSTI]

the engines in automotive applications. Heat is transferred essentially under subcooled flow boiling circular aluminum heater surface, 9.5-mm in diameter, placed at the bottom 40-mm wide wall of a rectangular

Kandlikar, Satish

474

Use of once-through treat gas to remove the heat of reaction in solvent hydrogenation processes  

DOE Patents [OSTI]

In a coal liquefaction process wherein feed coal is contacted with molecular hydrogen and a hydrogen-donor solvent in a liquefaction zone to form coal liquids and vapors and coal liquids in the solvent boiling range are thereafter hydrogenated to produce recycle solvent and liquid products, the improvement which comprises separating the effluent from the liquefaction zone into a hot vapor stream and a liquid stream; cooling the entire hot vapor stream sufficiently to condense vaporized liquid hydrocarbons; separating condensed liquid hydrocarbons from the cooled vapor; fractionating the liquid stream to produce coal liquids in the solvent boiling range; dividing the cooled vapor into at least two streams; passing the cooling vapors from one of the streams, the coal liquids in the solvent boiling range, and makeup hydrogen to a solvent hydrogenation zone, catalytically hydrogenating the coal liquids in the solvent boiling range and quenching the hydrogenation zone with cooled vapors from the other cooled vapor stream.

Nizamoff, Alan J. (Convent Station, NJ)

1980-01-01T23:59:59.000Z

475

Argonne National Laboratory 9700 S. Cass Avenue  

E-Print Network [OSTI]

drives an electric generator. Accurate predictions of the detailed 3-D distribution of steam and liquid simulating a Boiling Water Reactor assembly. The experiment is electrically heated and detailed void

Kemner, Ken

476

1JIM / TMS Solidification Science and Processing Conference, Honolulu, HI, Dec. 13-15, 1995. pp. 197-208.  

E-Print Network [OSTI]

the meniscus. [7] They were attributed to boiling of the lubricating oil, bleeding through partial tears depressions. Oscillation marks have been proposed to originate from pressure buildup in the lubricating flux

Thomas, Brian G.

477

Physica D 61 (1992) 166-182 North-Holland  

E-Print Network [OSTI]

or lubricating agent, formation of aerosols by centrifugal effects [6], boiling of liquids with formation oil) and then placed in an unstable situation by flipping the plate upside- down. Complex dynamics

Wesfreid, José Eduardo

478

Sustainable From cassava  

E-Print Network [OSTI]

tuberous roots cheap source of energy Leaves rich in protein, minerals and vitamins Past emphasis on low; pounded; milled Leaves ­ ground; fermented; boiled; soup; sauce; wine; dried; blended Cassava is also

479

E-Print Network 3.0 - aqueous na2s2o3 solutions Sample Search...  

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

Harris, 7th Summary: the molar concentration of the solution. Preparation and standardization of 0.1 M Na2S2O3. Boil about 500 m... with the ... Source: McQuade, D. Tyler -...

480

W-1 SLSF post-test data analysis. Part 1. Thermal hydraulic analysis. [LMFBR  

SciTech Connect (OSTI)

Four types of tests were performed: (1) a decay heat transient test, (2) Loss-of-Piping-Integrity (LOPI) tests, (3) Boiling Window Tests (BWT), and (4) a fuel pin dryout and failure test. In addition, preliminary tests were run to check systems performance, instrumentation performance and test section heat balance. The objective of the decay heat test was to determine the decay heat transfer characteristics of fresh fuel pins with subcooled sodium. The objective of the LOPI experiments was to test the thermal behavior of fuel pins with four different fuel conditions subjected to the same transient. The transient was designed to simulate a rapid flow decrease as a result of pipe rupture followed by a reactor scram. The objective of the Boiling Window Tests was to study boiling initiation and progression of boiling within the fuel pin bundle.

Knight, D.D.

1980-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "naph tha 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.


481

Anatahan, Northern Mariana Islands- Reconnaissance Geological...  

Open Energy Info (EERE)

1992, 1994, and 2001, geothermal activity (fumaroles as well as pits with boiling, sediment-laden pools) was observed in the southern part of the pit crater. In March and April...

482

CX-004148: Categorical Exclusion Determination  

Broader source: Energy.gov [DOE]

Online Monitoring Implementation in Boiling Water ReactorsCX(s) Applied: B3.6, B5.1Date: 09/17/2010Location(s): Knoxville, TennesseeOffice(s): Energy Efficiency and Renewable Energy

483

CASL-U-2013-0140-000 A. Guion, G. Rabello dos Anjos,  

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

3-0140-000 A. Guion, G. Rabello dos Anjos, C. Narayanan, J. Buogiorno, MIT, ASCOMP June 2013 CASL-U-2013-0140-000 1 Closure Relation for Microlayer Evaporation in Nucleate Boiling,...

484

4 Chemistry4 Chemistry Spring 2000 Chemists Shed Light on  

E-Print Network [OSTI]

that boiling water makes but also for the noise produced by submarine propellers and for the erosion of turbines. "By understanding the conditions inside the bubbles, we can learn to control cavitation and its

Suslick, Kenneth S.

485

Nanofluid heat transfer enhancement for nuclear reactor applications  

E-Print Network [OSTI]

Colloidal dispersions of nanoparticles are known as `nanofluids'. Such engineered fluids offer the potential for enhancing heat transfer, particularly boiling heat transfer, while avoiding the drawbacks (i.e., erosion, ...

Buongiorno, Jacopo

486

RUTGERS COOPERATIVE RESEARCH AND EXTENSION NEW JERSEY AGRICULTURAL EXPERIMENT STATION  

E-Print Network [OSTI]

) 68 White spaghetti 38 Croissant 67 Whole wheat spaghetti 37 Angel food cake 67 Peanuts 15 Cola soft cereal 92 Brown rice 55 Boiled red-skinned potatoes 88 Pound cake 54 Whole wheat bread 77 Orange juice 53

Garfunkel, Eric

487

STANFORD GEOTHERMAL QUARTERLY REPORT  

E-Print Network [OSTI]

STANFORD GEOTHERMAL PROGRAM QUARTERLY REPORT OCTOBER 1 ­ DECEMBER 31, 1996 #12;1 1 AN EXPERIMENTAL that in the vertical case. 1.2 INTRODUCTION The process of boiling in porous media is of significance in geothermal

Stanford University

488

Application of the polynomial chaos expansion to multiphase CFD : a study of rising bubbles and slug flow  

E-Print Network [OSTI]

Part I of this thesis considers subcooled nucleate boiling on the microscale, focusing on the analysis of heat transfer near the Three-Phase (solid, liquid, and vapor) contact Line (TPL) region. A detailed derivation of ...

Langewisch, Dustin R

2014-01-01T23:59:59.000Z

489

Stability analysis of natural circulation in BWRs at high pressure conditions  

E-Print Network [OSTI]

At rated conditions, a natural circulation boiling water reactor (NCBWR) depends completely on buoyancy to remove heat from the reactor core. This raises the issue of potential unstable flow. oscillations. The objective ...

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

2007-01-01T23:59:59.000Z

490

Heat transfer to impacting drops and post critical heat flux dispersed flow  

E-Print Network [OSTI]

Heat transfer to drops impacting on a hot surface is examined in context of dispersions of flowing, boiling fluids. The liquid contribution to heat transfer from a hot tube to a two-phase dispersion is formulated in terms ...

Kendall, Gail E.

1978-01-01T23:59:59.000Z

491

Modeling of fuel-to-steel heat transfer in core disruptive accidents  

E-Print Network [OSTI]

A mathematical model for direct-contact boiling heat transfer between immiscible fluids was developed and tested experimentally. The model describes heat transfer from a hot fluid bath to an ensemble of droplets of a cooler ...

Smith, Russell Charles

1980-01-01T23:59:59.000Z

492

Chapter 8: Conservation Laws Did you read chapter 8  

E-Print Network [OSTI]

. ExamplesExamples · gasoline in car · forest fire · boiling water Conservation of total Electric Charge by th l ctr m n ticthe electromagnetic force via sharing electrons. Atoms Size ~ 10-10 meters. An atom

Hart, Gus

493

MSU Extension Publication Archive Archive copy of publication, do not use for current recommendations. Up-to-date  

E-Print Network [OSTI]

with salsa, chili, fat-free sour cream or yogurt and chives, mixed vegetables, low- fat ranch-style salad dressing or low-fat cheese. To boil Scrub potatoes and, if desired, peel. Put whole potatoes or potatoes

494

FOOD PRESERVATION SERIES types of potatoes  

E-Print Network [OSTI]

ranch-style salad dressing or low-fat cheese. Boil, cube and serve as salad with low-fat or fat free salad dressing Oven Wedge Fries 2 large russet potatoes 1 teaspoon olive oil or other vegetable oil

495

Duval County Extension 1010 N. McDuff Ave.  

E-Print Network [OSTI]

of vegetables to boiling water or steam for a brief period of time. The vegetables are then cooled quickly so, spaghetti, rice (cooked) Mayonnaise Meringue Milk sauces Please note that some of these foods may

Watson, Craig A.

496

Cross section generation strategy for high conversion light water reactors  

E-Print Network [OSTI]

High conversion water reactors (HCWR), such as the Resource-renewable Boiling Water Reactor (RBWR), are being designed with axial heterogeneity of alternating fissile and blanket zones to achieve a conversion ratio of ...

Herman, Bryan R. (Bryan Robert)

2011-01-01T23:59:59.000Z

497

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

E-Print Network [OSTI]

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

Hu, Lin-Wen

498

Design of annular fuel for high power density BWRs  

E-Print Network [OSTI]

Enabling high power density in the core of Boiling Water Reactors (BWRs) is economically profitable for existing or new reactors. In this work, we examine the potential for increasing the power density in BWR plants by ...

Morra, Paolo

2005-01-01T23:59:59.000Z

499

Integrated environmental degradation model for Fe-Ni-Cr alloys in irradiated aqueous solutions  

E-Print Network [OSTI]

An integrated model has been developed to evaluate the effect of reactor flux, fluence, and other operating conditions on crack growth rates in austenitic stainless steels in boiling water reactor (BWR) environments. The ...

Pleune, Thomas Todd, 1974-

1999-01-01T23:59:59.000Z

500

Computer Physics Communications 142 (2001) 201205 www.elsevier.com/locate/cpc  

E-Print Network [OSTI]

, Helsinki University of Technology, P.O. Box 1100, FIN-02015 HUT, Finland b Department of Chemistry temperature with size, the dependence of melting, boiling, and sublimation temperatures on the potentials

Kim, Sehun