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Note: This page contains sample records for the topic "boiling nuclear superheater" from the National Library of EnergyBeta (NLEBeta).
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1

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

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

394: Public Access to the BONUS Facility January 2003 394: Public Access to the BONUS Facility January 2003 i DOE/EA-1394 ENVIRONMENTAL ASSESSMENT FOR AUTHORIZING THE PUERTO RICO ELECTRIC POWER AUTHORITY (PREPA) TO ALLOW PUBLIC ACCESS TO THE BOILING NUCLEAR SUPERHEAT (BONUS) REACTOR BUILDING, RINCĂ“N, PUERTO RICO January 2003 U.S. Department of Energy Oak Ridge Operations Office Oak Ridge, Tennessee DOE/EA-1394: Public Access to the BONUS Facility January 2003 ii TABLE OF CONTENTS LIST OF FIGURES V LIST OF TABLES V ACRONYMS VI UNIT ABBREVIATIONS VII SUMMARY VIII 1. INTRODUCTION 10 1.1 Purpose and Need for Action 10 1.2 Operational and Decommissioning History 15 1.3 Summary of Radiological Conditions at the BONUS Facility 19 2. DESCRIPTION OF THE PROPOSED ACTION AND ALTERNATIVES 25

2

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

3

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

4

Alternate Materials for Recovery Boiler Superheater Tubes  

SciTech Connect

The ever escalating demands for increased efficiency of all types of boilers would most sensibly be realized by an increase in the steam parameters of temperature and pressure. However, materials and corrosion limitations in the steam generating components, particularly the superheater tubes, present major obstacles to boiler designers in achieving systems that can operate under the more severe conditions. This paper will address the issues associated with superheater tube selection for many types of boilers; particularly chemical recovery boilers, but also addressing the similarities in issues for biomass and coal fired boilers. It will also review our recent study of materials for recovery boiler superheaters. Additional, more extensive studies, both laboratory and field, are needed to gain a better understanding of the variables that affect superheater tube corrosion and to better determine the best means to control this corrosion to ultimately permit operation of recovery boilers at higher temperatures and pressures.

Keiser, James R [ORNL; Kish, Joseph [McMaster University; Singbeil, Douglas [FPInnovations

2009-01-01T23:59:59.000Z

5

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

SciTech Connect

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

NONE

1995-08-01T23:59:59.000Z

6

Can we remove iodine-131 from tap water in Japan by boiling? – Experimental testing in response to the Fukushima Daiichi Nuclear Power Plant accident  

Science Journals Connector (OSTI)

Iodine-131 concentrations in tap water higher than 100 Bq L?1 were reported by several local governments in Japan following the Fukushima Daiichi Nuclear Power Plant accident. Some individuals in the emergency-response community recommended the boiling of tap water to remove iodine-131. However, the tap water boiling tests in this study showed no iodine-131 loss from the tap water with either short-term boiling (1–10 min) or prolonged boiling (up to 30 min) resulting in up to 3-fold volume reductions. In this situation, boiling was shown to be not effective in removing iodine-131 from tap water; indeed even higher concentrations may result from the liquid-volume reduction accompanying this process.

K. Tagami; S. Uchida

2011-01-01T23:59:59.000Z

7

Recovery Boiler Superheater Ash Corrosion Field Study  

SciTech Connect

With the trend towards increasing the energy efficiency of black liquor recovery boilers operated in North America, there is a need to utilize superheater tubes with increased corrosion resistance that will permit operation at higher temperatures and pressures. In an effort to identify alloys with improved corrosion resistance under more harsh operating conditions, a field exposure was conducted that involved the insertion of an air-cooled probe, containing six candidate alloys, into the superheater section of an operating recovery boiler. A metallographic examination, complete with corrosion scale characterization using EMPA, was conducted after a 1,000 hour exposure period. Based on the results, a ranking of alloys based on corrosion performance was obtained.

Keiser, James R [ORNL] [ORNL; Kish, Joseph [McMaster University] [McMaster University; Singbeil, Douglas [FPInnovations] [FPInnovations

2010-01-01T23:59:59.000Z

8

Audit calculations with CORCON-MOD 3 of the duration of superheat in NUREG/CR-5423  

SciTech Connect

Analyses have shown that early rupture of the Mark-I boiling water reactor containment-by the direct action of core debris depends strongly on the time that core debris is superheated above its liquidus. The analyses of the duration of superheat in the core debris are compared to predictions obtained with the CORCON-MOD 3 computer code. The predicitons of this computer code as functions of the core debris mass, composition, and initial superheat are used to create a polynomial response surface. This response surface is used in a Monte Carlo analysis to produce probability distributions for the duration of superheat in core debris in the drywell of a Mark-I containment. It is concluded that to a high level of confidence (>90%) the duration of superheating predicted with the CORCON-MOD 3 code is less than what has been used in the analyses of the threats to the Mark-I containment liner. Based on these results, to the extent superheat duration dictates the threat to the liner, analyses in NUREG/CR-5423 would appear to overestimate the threat to the liner in comparison to threats estimated using the predictions of the duration of superheating obtained with CORCON-MOD 3.

Powers, D.A.; Heames, T.J.

1992-05-01T23:59:59.000Z

9

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

SciTech Connect

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

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

1982-03-01T23:59:59.000Z

10

Effect of Oxyfuel Combustion on Superheater Corrosion  

SciTech Connect

Combustion of coal in an oxygen environment (as opposed to air) will facilitate the sequestering of carbon dioxide by minimizing the amount of nitrogen in the exit gas stream. The presence of higher levels of certain gases associated with oxyfuel combustion (eg, CO2, SO2, and H2O) may impact the corrosion of waterwalls, superheaters, headers, reheaters, and other boiler components. Research is being conducted on bare and ash-embedded boiler tube materials in simulated oxyfuel- combustion and air-combustion environments at a superheater temperature of 675°C. Alloys were exposed at temperature to two different gaseous environments. Preliminary results show: (1) an increase in corrosion rate of bare K02707, K11547, K21590, K91560, K92460, S30409, S34700, and N06617 exposed to the oxyfuel combustion environment when compared to the air combustion environment; (2) an increase in corrosion rate of alloys K21590, K92460, S34700, and N06617, when embedded in ash in comparison to bare exposure; and (3) no effect of gaseous environment on alloy corrosion rate when embedded in ash.

Covino, B.S., Jr.; Matthes, S.A.; Bullard, S.J.

2008-03-16T23:59:59.000Z

11

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

12

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

SciTech Connect

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

Liu, C.; Theofanous, T. G.

2000-08-29T23:59:59.000Z

13

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

SciTech Connect

This document presents a bibliography that contains 100-word abstracts of event reports submitted to the US Nuclear Regulatory Commission concerning operational events that occurred at boiling-water-reactor nuclear power plants in 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

14

Study and Design of Platen Superheater of 300 MW CFB Boiler  

Science Journals Connector (OSTI)

In order to avoid overtemperature tube explosion of the platen superheater, the measurements of metal temperatures and the heat transfer coefficients of the platen superheater in a commercial 300 MW Circulating F...

Zhang Man; Lv Qinggang; Jiang Xiaoguo…

2013-01-01T23:59:59.000Z

15

Integrated boiler, superheater, and decomposer for sulfuric acid decomposition  

DOE Patents (OSTI)

A method and apparatus, constructed of ceramics and other corrosion resistant materials, for decomposing sulfuric acid into sulfur dioxide, oxygen and water using an integrated boiler, superheater, and decomposer unit comprising a bayonet-type, dual-tube, counter-flow heat exchanger with a catalytic insert and a central baffle to increase recuperation efficiency.

Moore, Robert (Edgewood, NM); Pickard, Paul S. (Albuquerque, NM); Parma, Jr., Edward J. (Albuquerque, NM); Vernon, Milton E. (Albuquerque, NM); Gelbard, Fred (Albuquerque, NM); Lenard, Roger X. (Edgewood, NM)

2010-01-12T23:59:59.000Z

16

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

17

MOLTEN SALT CORROSION OF SUPERHEATERS IN BLACK LIQUOR RECOVERY BOILERS John Bohling, University of Tennessee Georgia Tech SURF 2010 Fellow  

E-Print Network (OSTI)

MOLTEN SALT CORROSION OF SUPERHEATERS IN BLACK LIQUOR RECOVERY BOILERS John Bohling, University Goodman Introduction In the papermaking industry, black liquor recovery boilers burn black liquor into the superheater region of the boiler, where the salt-deposit, or smelt, forms a scale on the superheater tubes.1

Li, Mo

18

Fireside Corrosion of Superheater Materials in Coal/Biomass Co-fired Advanced Power Plants  

Science Journals Connector (OSTI)

A series of laboratory-based fireside corrosion exposures were conducted to assess the effect of such conditions on superheater/reheater materials at higher than conventional metal temperatures. Controlled atm...

Tanvir Hussain; Adnan U. Syed; Nigel J. Simms

2013-12-01T23:59:59.000Z

19

bonus  

Office of Legacy Management (LM)

decommissioned Boiling Nuclear Superheater decommissioned Boiling Nuclear Superheater (BONUS) reactor, located northwest of RincĂłn, Puerto Rico, was developed as a prototype nuclear power plant to investigate the technical and economic feasibility of the integral boiling-superheating concept. This small- scale nuclear reactor produced saturated steam in the central portion of the reactor core, superheated it in four surrounding "superheater" sections of the same

20

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

SciTech Connect

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

Note: This page contains sample records for the topic "boiling nuclear superheater" 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

Applications of Artificial Neural Network for the Prediction of Pool Boiling Curves  

SciTech Connect

Artificial neural network (ANN) has the advantage that the best-fit correlations of experimental data will no longer be necessary for predicting unknowns from the known parameters. The ANN was applied to predict the pool boiling curves in this paper. The database of experimental data presented by Berenson, Dhuga et al., and Bui and Dhir etc. were used in the analysis. The database is subdivided in two subsets. The first subset is used to train the network and the second one is used to test the network after the training process. The input parameters of the ANN are: wall superheat {delta}T{sub w}, surface roughness, steady/transient heating/transient cooling, subcooling, Surface inclination and pressure. The output parameter is heat flux q. The proposed methodology allows us to achieve the accuracy that satisfies the user's convergence criterion and it is suitable for pool boiling curve data processing. (authors)

Su, Guanghui; Fukuda, K.; Morita, K. [Kyushu University, 6-10-1, Hakozaki, Higashi-ku, Fukuoka 812-81 (Japan)

2002-07-01T23:59:59.000Z

22

Selection of Materials for Superheater Recovery Boiler Harold Nikoue: Georgia Tech, SURF 2009 Fellow  

E-Print Network (OSTI)

Selection of Materials for Superheater Recovery Boiler Harold Nikoue: Georgia Tech, SURF 2009 the situation, the high pressure gas flow is both oxidizing and sulfidizing at this temperature Materials that form a protective coating can withstand this harsh environment, and therefore permit higher efficiency

Li, Mo

23

Hard boiling eggs  

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

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

24

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

SciTech Connect

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

25

OXIDE SCALE EXFOLIATION AND REGROWTH IN TP347H SUPERHEATER TUBES  

SciTech Connect

This paper provides an introduction to a comprehensive model being developed to predict and control oxide scale exfoliation from the steam-side of superheater and reheater tubes in steam boilers. The model deals with the main phenomena involved in scale growth and failure in steam, and incorporates major variables related to boiler design and operation. The considerations used to calculate oxide growth under the specific constrains of small diameter tubes carrying high-pressure steam and operating with large temperature gradients under temperature and pressure cycling conditions, as well as the evolution of stresses and strains in the scales, are indicated but only a cursory description is given of the details of the analytical treatments. An example is presented of calculations made with the model to predict the extent of blockage expected in a single superheater loop as a function of time and outlet steam temperature under several realistic service conditions. The results suggest that problems due to scale exfoliation would be expected early in the operating life of superheater tubes made from austenitic steel TP347H.

Sabau, Adrian S [ORNL; Wright, Ian G [ORNL; Shingledecker, John P. [Electric Power Research Institute (EPRI)

2012-01-01T23:59:59.000Z

26

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

27

Fireside corrosion of superheaters: Effects of air and oxy-firing of coal and biomass  

Science Journals Connector (OSTI)

The growing world population requires increasing quantities of electricity from sources that have reduced environmental impact, especially CO2 emissions. For pulverised coal-fired power plants, reduced CO2 emissions can be achieved by increasing the operating temperatures/pressures of the steam systems (which increases the efficiency of power generation), the use of ‘carbon-neutral’ fuels such as biomass, and/or the implementation of CO2 capture technologies. The use of small quantities of biomass fuels (typically up to 5% of the energy content of the fuels) is already widely practised in the UK. As an alternative, oxy-firing pulverised fuel power plants provides a route to enable CO2 capture technologies to be introduced; but this route also requires the use of higher temperature/pressure steam systems to counter-act the efficiency penalty of CO2 capture and handling systems. All of these options to reduce CO2 emissions result in significant changes to the operating conditions (e.g. metal temperatures, gas temperatures, gaseous environments and deposits) that are anticipated for superheaters in these power systems. Such changes in operating conditions are expected to result in higher rates of fireside corrosion and so reduce the potential lives of these critical components. This paper reports the results of investigations that have been carried out to assess the effect on fireside corrosion of operating superheaters at higher metal temperatures in power systems using coal/biomass fuels fired with air or oxygen. A series of fireside corrosion experiments has been carried out using the ‘deposit recoat’ test method to simulate the damage anticipated in different specific environments. Using an alumina-lined controlled-atmosphere furnace, the gaseous and deposit environments were simulated for superheaters in (a) air-fired and (b) oxy-fired (hot gas recycle system variant) power plants using cereal co-product and a UK coal. The corrosion tests were carried out at temperatures of 600 and 650 °C, to represent the metal temperatures anticipated in power plants in the near future. The potential superheater materials used in these tests were T92, 347HFG and HR3C steels, as well as one nickel-based material, alloy 625. The progress of the exposures was monitored using traditional mass change methods. Destructive examinations of the samples were carried out after their exposures, using optical microscopy and SEM/EDX methods to characterise the damage observed. The performance of the materials was determined using dimensional metrology; pre-exposure micrometer measurements and post-exposure image analyser measurements on polished cross-sections. The resulting metal loss distribution data for each sample exposed are being used for the development of statistical models of the fireside corrosion of superheater materials in novel operating environments.

A.U. Syed; N.J. Simms; J.E. Oakey

2012-01-01T23:59:59.000Z

28

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

29

Formation of deposits on the surfaces of superheaters and economisers of MSW incinerator plants  

SciTech Connect

Highlights: Black-Right-Pointing-Pointer Composition of deposits depends on the temperature profile and boiler geometry. Black-Right-Pointing-Pointer The mineralogy of deposits defines critical and uncritical zones in the boiler. Black-Right-Pointing-Pointer Critical zones in boilers can be characterised by a classification systems. Black-Right-Pointing-Pointer Specific measures to enhance energy efficiency can be defined. - Abstract: Mineralogical and chemical investigations of deposits from superheaters and economisers from a MSWI plant in Mannheim, Germany, lead to a classification system which provides information about the most critical parameters leading to fouling and corrosion. With the help of this classification system parameters like the geometry of boilers and the waste input can be changed in order to prolong run times between revisions and enhance energy efficiency of MSWI plants.

Reichelt, J. [IBR, Obergrombacher Strasse 29, D-76646 Bruchsal (Germany); Pfrang-Stotz, G., E-mail: Gudrun.Pfrang-Stotz@kit.edu [Karlsruhe Institute of Technology (KIT), ITC, Hermann-von-Helmholtz-Platz 1, D-76344 Eggenstein-Leopoldshafen (Germany); Bergfeldt, B.; Seifert, H. [Karlsruhe Institute of Technology (KIT), ITC, Hermann-von-Helmholtz-Platz 1, D-76344 Eggenstein-Leopoldshafen (Germany); Knapp, P. [MVV O and M GmbH, Muellheizkraftwerk Mannheim, Otto-Hahn-Strasse 1, D-68169 Mannheim (Germany)

2013-01-15T23:59:59.000Z

30

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

31

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

32

Modeling acid-gas generation from boiling chloride brines  

SciTech Connect

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

33

Superheater/intermediate temperature airheater tube corrosion tests in the MHD Coal Fired Flow Facility (Eastern Coal Phase)  

SciTech Connect

Corrosion data have been obtained for tub is exposed for 1500--2000 hours in a proof-of-concept magnetohydrodynamics (MHD) power generation test facility to conditions representative of superheater and intermediate temperature air heater (ITAH) components. The tubes, coated with K{sub 2}SO{sub 4}-rich deposits, were corroded more than in most pulverized coal fired superheater service, but much less than the highly aggressive liquid phase attack encountered in conventional plants with certain coals and temperatures. Results indicated that, with parabolic corrosion kinetics, type 310 and 253MA stainless steels should be usable to 1400F at hot end of ITAH. At final superheater temperatures, 2.25 and 5 Cr steels were indicated to have parabolic corrosion rates generally below a 0.5 mm/yr criterion, based on corrosion scale thickness. However, unknown amounts of scale loss from spallation made this determination uncertain. Stainless steels 304H, 316H, and 321H had parabolic rates variably above the criterion, but may be servicable under less cyclic conditions. Corrosion rates derived from scale thickness and intergranular corrosion depth measurements are reported, along with scale morphologies and compositions. Implications of results on commercial MHD utilization of the alloys are discussed, as well as the indicated need for more corrosion resistant alloys or coatings under the most severe exposure conditions.

White, M.K.

1993-11-01T23:59:59.000Z

34

Fireside corrosion testing of candidate superheater tube alloys, coatings, and claddings  

SciTech Connect

Fireside corrosion, caused by liquid alkali-iron trisulfates, has been an obstacle to higher steam temperatures and to efficient utilization of high-sulfur coals. Tests simulating the environment in the superheater bank of a pulverized-coal-fired boiler were conducted on several promising new alloys and claddings. Alloys were exposed to a variety of synthetic ash and simulated flue gas compositions at 650 and 700{degrees}C for times ranging up to 800 hours. Included in the testing program were new high-chromium/high-nickel alloys, modified commercial alloys, lean stainless steels (modified Type 316) clad with high-chromium/high-nickel alloys, and intermetallic aluminides. Thickness loss measurements indicated that resistance to attach improved with increasing chromium level. Silicon and aluminum were also helpful in resisting attack, while molybdenum was detrimental to the resistance of the alloys to attack. Three different attack modes were observed on the alloys tested. Alloys with low resistance to attack exhibited uniform wastage, while pitting was observed in more resistant alloys. In addition to surface fluxing by molten alkali-iron trisulfates, subsurface sulfur penetration and intergranular attack also occurred.

Van Weele, S. (Foster Wheeler Development Corp., Livingston, NJ (United States))

1991-08-01T23:59:59.000Z

35

Fireside corrosion testing of candidate superheater tube alloys, coatings, and claddings. Final report  

SciTech Connect

Fireside corrosion, caused by liquid alkali-iron trisulfates, has been an obstacle to higher steam temperatures and to efficient utilization of high-sulfur coals. Tests simulating the environment in the superheater bank of a pulverized-coal-fired boiler were conducted on several promising new alloys and claddings. Alloys were exposed to a variety of synthetic ash and simulated flue gas compositions at 650 and 700{degrees}C for times ranging up to 800 hours. Included in the testing program were new high-chromium/high-nickel alloys, modified commercial alloys, lean stainless steels (modified Type 316) clad with high-chromium/high-nickel alloys, and intermetallic aluminides. Thickness loss measurements indicated that resistance to attach improved with increasing chromium level. Silicon and aluminum were also helpful in resisting attack, while molybdenum was detrimental to the resistance of the alloys to attack. Three different attack modes were observed on the alloys tested. Alloys with low resistance to attack exhibited uniform wastage, while pitting was observed in more resistant alloys. In addition to surface fluxing by molten alkali-iron trisulfates, subsurface sulfur penetration and intergranular attack also occurred.

Van Weele, S. [Foster Wheeler Development Corp., Livingston, NJ (United States)

1991-08-01T23:59:59.000Z

36

Fireside corrosion testing of candidate superheater tube alloys, coatings, and claddings -- Phase 2 field testing  

SciTech Connect

In Phase 1 of this project, laboratory experiments were performed on a variety of developmental and commercial tubing alloys and claddings by exposing them to fireside corrosion tests which simulated a superheater or reheater in a coal-fired boiler. Phase 2 (in situ testing) has exposed samples of 347, RA85H, HR3C, RA253MA, Fe{sub 3}Al + 5Cr, Ta-modified 310, NF 709, 690 clad, 671 clad, and 800HT for up to approximately 16,000 hours to the actual operating conditions of a 250-MW, coal-fired boiler. The samples were installed on air-cooled, retractable corrosion probes, installed in the reheater cavity, and controlled to the operating metal temperatures of an existing and advanced-cycle, coal-fired boiler. Samples of each alloy were exposed for 4,483, 11,348, and 15,883 hours of operation. The present results are for the metallurgical examination of the corrosion probe samples after the full 15,883 hours of exposure. A previous topical report has been issued for the 4,483 hours of exposure.

Blough, J.L.; Seitz, W.W.; Girshik, A. [Foster Wheeler Development Corp., Livingston, NJ (United States)

1998-06-01T23:59:59.000Z

37

Microsoft Word - TR07-27.doc  

Office of Legacy Management (LM)

Boiling Nuclear Superheat (BONUS), Site, RincĂłn, Puerto Rico Boiling Nuclear Superheat (BONUS), Site, RincĂłn, Puerto Rico July 2010 Page 1 2010 Inspection and Status Report for the Former Boiling Nuclear Superheater (BONUS) Reactor Facility, RincĂłn, Puerto Rico Summary The Former Boiling Nuclear Superheater (BONUS) Reactor Facility, located on the west coast of Puerto Rico in the town of RincĂłn, was inspected on June 24, 2010. During the inspection radiation technicians from the Idaho National Laboratory (INL) safely packaged and shipped two legacy radioactive sources to INL for disposition. The BONUS facility consists of the containment building, which houses the entombed reactor system, and outside support facilities. The Puerto Rico Electric Power Authority (PREPA) uses the decommissioned BONUS facility as a history museum. It is opened to the public for

38

Enhancement of Pool Boiling Heat Transfer in Confined Space  

E-Print Network (OSTI)

Pool boiling is an effective method used in many technical applications for a long time. Its highly efficient heat transfer performance results from not only the convection effect but also the phase change process in pool boiling. Pool boiling...

Hsu, Chia-Hsiang

2014-05-05T23:59:59.000Z

39

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

40

STEAM-SIDE OXIDE SCALE EXFOLIATION BEHAVIOR IN SUPERHEATERS AND REHEATERS  

SciTech Connect

Advances in materials for power plants include not only new materials with higher-temperature capabilities, but also the use of current materials at increasingly higher temperatures. This latter activity builds on extensive experience of the performance of the various alloys, and provides a basis for identifying changes in alloy behavior with increasing temperature as well as understanding the factors that ultimately determine the maximum use temperatures of the different alloy classes. This paper presents results from an effort to model the exfoliation processes of steam-side oxide scales in a manner that describes as accurately as possible the evolution of strains in oxides growing inside small-diameter tubes subjected to large thermal gradients and to thermal transients typical of normal steam boiler operation. One way of portraying the results of such calculations is by plotting the evolving strains in a given oxide scale on an Exfoliation Diagram (of the type pioneered by Manning et al. of the British Central Electricity Research Laboratory) to determine the earliest time at which the trajectory of these strains intersects a criterion for scale failure. Understanding of how such strain trajectories differ among different alloys and are affected by the major variables associated with boiler operation has the potential to suggest boiler operating strategies to manage scale exfoliation, as well as to highlight the mode of scale failure and the limitations of each alloy. Preliminary results are presented of the strain trajectories calculated for alloys T22, T91, and TP347 subjected to the conditions experienced by superheaters under assumed boiler operating scenarios. For all three alloys the earliest predicted scale failures were associated with the increased strains developed during a boiler shut-down event; indeed, in the cases considered it appeared unlikely that scale failure would occur in any practically meaningful time due to strains accumulated during operation in a load-following mode in the absence of a shut down. The accuracy of the algorithms used for the kinetics of oxide growth appeared to be a very important consideration, especially for alloy TP347 for which large effects on oxide growth rate are known to occur with changes in alloy grain size and surface cold work.

Sabau, Adrian S [ORNL; Shingledecker, John P. [Electric Power Research Institute (EPRI); Wright, Ian G [ORNL

2011-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "boiling nuclear superheater" 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

CRADA with PACCAR Experimental Investigation in Coolant Boiling...  

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

Half-Heated Circular Tube Efficient Cooling in Engines with Nucleate Boiling Cooling Boiling in Head Region - PACCAR Integrated Underhood Thermal and External Aerodynamics- Cummins...

42

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

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

of Power Electronics of Electric Vehicles with Small Channel Coolant Boiling Cooling Boiling in Head Region - PACCAR Integrated Underhood Thermal and External Aerodynamics- Cummins...

43

TVA chooses nuclear power  

Science Journals Connector (OSTI)

TVA chooses nuclear power ... In giving the nod to a nuclear (over a coal) power generating station 10 days ago, TVA probably gave nuclear power its biggest boost to date. ... The $247 million nuclear power plant—a dual boiling-water reactor unit with a total capacity of 2.2 million kw(e).—will ...

1966-06-27T23:59:59.000Z

44

PHYSICAL REVIEW E 89, 013011 (2014) Unorthodox bubbles when boiling in cold water  

E-Print Network (OSTI)

that stirs the water, followed by several conventional bubbles. This large dataset is analyzed and discussed and reliable performance of nuclear reactors and microchip systems. Engineers have a long tradition dataset has been analyzed statistically. We conclude that while the naive scenario of boil

Granick, Steve

45

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

46

Boiling Springs Geothermal Area | Open Energy Information  

Open Energy Info (EERE)

Boiling Springs Geothermal Area Boiling Springs Geothermal Area Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Geothermal Resource Area: Boiling Springs Geothermal Area Contents 1 Area Overview 2 History and Infrastructure 3 Regulatory and Environmental Issues 4 Exploration History 5 Well Field Description 6 Geology of the Area 7 Geofluid Geochemistry 8 NEPA-Related Analyses (0) 9 Exploration Activities (0) 10 References Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"TERRAIN","zoom":6,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"500px","height":"300px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":44.3641,"lon":-115.856,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

47

Trends in fireside corrosion damage to superheaters in air and oxy-firing of coal/biomass  

Science Journals Connector (OSTI)

Abstract This paper compares the laboratory-based fireside corrosion tests on superheater/reheater materials in simulated air-firing combustion conditions with oxy-firing combustion conditions (with hot gas recycling before flue gas de-sulphurisation). The gaseous combustion environment was calculated based on a specific co-firing ratio of CCP with Daw Mill coal. The fireside corrosion tests were carried out using the “deposit recoat” test method to simulate the damage anticipated in specific environments. A synthetic deposit (Na2SO4:K2SO4:Fe2O3 = 1.5:1.5:1 mol.) which has commonly been used in fireside corrosion screening trials and is a mix that forms alkali-iron tri-sulphate (identified in many investigations as a cause of fireside corrosion) was used in these tests. The air-fired tests were carried out at temperatures of 600, 650 and 700 °C and oxy-fired tests were carried out at temperatures of 600, 650, 700 and 750 °C to represent the superheater/reheater metal temperatures anticipated in future power plants with and without synthetic deposits, with four candidate materials: T92, HR3C and 347HFG steels; nickel-based alloy 625 (alloy 625 was only tested with screening deposits). The progress of the samples during their exposures was measured using mass change methods. After the exposures, the samples were examined by SEM/EDX to characterise the damage. To quantify the metal damage, pre-exposure micrometre measurements were compared to the post-exposure image analyser measurements on sample cross-sections. The trends in corrosion damage in both air and oxy-firing conditions showed a “bell-shaped” curve, with the highest metal damage levels (peak) observed at 650 °C for air-firing and 700 °C for oxy-firing tests. However, at 600 and 650 °C similar damage levels were observed in both environments. The shift in peak corrosion damage in oxy-firing condition is believed to be the presence of higher levels of SOx, which stabilised the alkali-iron tri-sulphate compounds. Generally, in both air and oxy-firing conditions the mean metal damage was reduced with increasing the amount of Cr in the alloys. However, at the highest temperatures in both air-firing (700 °C) and oxy-firing conditions (750 °C) the metal damage of nickel based superalloy 625 was higher than HR3C.

T. Hussain; A.U. Syed; N.J. Simms

2013-01-01T23:59:59.000Z

48

bonus.cdr  

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

decommissioned decommissioned Boiling Nuclear Superheater (BONUS) reactor, located northwest of RincĂłn, Puerto Rico, was developed as a prototype nuclear power plant to investigate the technical and economic feasibil- ity of the integral boiling-superheating concept. This small-scale nuclear reactor produced saturated steam in the central portion of the reactor core, superheated it in four surrounding "superheater" sections of the same core, and then used the superheated steam in a direct loop to drive a turbine generator. It was one of only two boiling-water superheater reactors ever developed in the United States. The reactor was designed to be large enough to evaluate the major features of the integral boiling-superheating concept realistically without the high construction and operating costs associated with a large plant. Construction of the began in 1960 through a

49

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

50

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

51

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

52

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

53

Operational control of boiling water reactor stability  

SciTech Connect

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

54

Nucleate boiling pressure drop in an annulus: Book 4  

SciTech Connect

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. This document consists of data plots and summary files of temperature measurements.

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

1992-11-01T23:59:59.000Z

55

EA-1394: Final Environmental Assessment | Department of Energy  

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

394: Final Environmental Assessment 394: Final Environmental Assessment EA-1394: Final Environmental Assessment Authorizing the Puerto Rico Electric Power Authority (PREPA) to allow Public Access to the Boiling Nuclear Superheat (BONUS) Reactor Building, Ricon, Puerto Rico This Environmental Assessment (EA) addresses the proposed action by the U.S. Department of Energy (DOE) to authorize the Puerto Rico Electric Power Authority (PREPA) to allow public access to the Boiling Nuclear Superheat (BONUS) reactor building located near RincĂłn, Puerto Rico for use as a museum. PREPA, the owner of the facility, is proposing development of the facility as a museum. Environmental Assessment for Authorizing the Puerto Rico Electric Power Authority (PREPA) to allow Public Access to the Boiling Nuclear Superheat

56

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....

57

Scalar Nature of the Nuclear Density Functional  

E-Print Network (OSTI)

Because of the rotational invariance of the nuclear Hamiltonian, there exists a density functional for nuclei that depends only on two scalar densities. Practical calculations boil down to radial, one-dimensional ones.

B. G. Giraud

2008-01-22T23:59:59.000Z

58

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

59

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

60

Reliquefaction of boil-off from liquefied natural gas  

SciTech Connect

This patent describes a process for liquifying boil-off gas resulting from the evaporation of liquified natural gas contained in a storage vessel. The boil-off gas is cooled and liquified in a closed-loop refrigeration system and then returned to the storage vessel wherein. The closed-loop refrigeration system comprises the steps: compressing nitrogen as a working fluid in a compressor system to form a compressed working fluid; splitting the compressed working fluid into a first and second stream; isenthalpically expanding the first stream to produce a cooled first stream, then warming against boil-off gas and compressed working fluid; and isentropically expanding the second stream to form a cooled expanded stream which is then warmed against boil-off gas to form at least partially condensed boil-off prior to warming against the working fluid and prior to return to the compressor system.

Cook, P.J.

1989-07-11T23:59:59.000Z

Note: This page contains sample records for the topic "boiling nuclear superheater" 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

Little low-power boiling never hurt anybody. [LMFBR  

SciTech Connect

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

62

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

E-Print Network (OSTI)

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

Lu, Ming-Chang

2010-01-01T23:59:59.000Z

63

Thermal analysis and design of a passive reflux condenser for the simplified boiling water reactor  

SciTech Connect

At present, the advanced light water reactors (ALWRS) in the United States are being designed to remove reactor decay heat for a period of 72 h following a postulated loss-of-coolant accident (LOCA). The water in the pools external to the containment is evaporated or boiled off to remove the decay heat. It is presumed that the water in the pools can be replenished within 72 h through operator actions or outside assistance. Some countries in Europe require that the plant be designed to remove the reactor decay heat for a much longer duration than 72 h without external assistance. This paper presents an analysis and design of a passive heat exchanger called a reflux condenser (RC), which was considered for an ALWR-the 600-MW(electric) simplified boiling water reactor. The RC is required to condense the steam formed when the water in the pool in which the passive containment cooling system (PCCS) is immersed boils following a LOCA. The RCs are nuclear non-safety related. This paper presents steady-state performance of an RC at various outdoor air dry-bulb temperatures under still air conditions.

Bijlani, C.; Patti, F. (Burns Roe Inc., Oradell, NJ (United States)); Prasad, V. (SUNY, Stony Brook, NY (United States))

1993-01-01T23:59:59.000Z

64

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

E-Print Network (OSTI)

DESIGN, CONSTRUCTION AND TESTING OF A SOILING AND CONVECTIVE CONDENSATION EXPERIMENT FOR USE IN A MICROGRAVITY ENVIRONMENT A Thesis by LEO JOSEPH KACHNIK Submitted to the Graduate College of Texas ASM University in partial fulfillment... of the requirements for the degree of MASTER OF SCIENCE May 1987 Major Subject: Nuclear Engineering DESIGN, CONSTRUCTION AND TESTING OF A BOILING AND CONVECTIVE CONDENSATION EXPERIMENT FOR USE IN A MICROGRAVITY ENVIRONMENT A Thesis by LEO JOSEPH KACHNIK...

Kachnik, Leo Joseph

2012-06-07T23:59:59.000Z

65

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

SciTech Connect

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

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

2006-10-20T23:59:59.000Z

66

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

67

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

68

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

69

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

70

Revisting the boiling of quark nuggets at nonzero chemical potential  

E-Print Network (OSTI)

The boiling of possible quark nuggets during the quark-hadron phase transition of the Universe at nonzero chemical potential is revisited within the microscopic Brueckner-Hartree-Fock approach employed for the hadron phase, using two kinds of baryon interactions as fundamental inputs. To describe the deconfined phase of quark matter, we use a recently developed quark mass density-dependent model with a fully self-consistent thermodynamic treatment of confinement. We study the baryon number limit $A_{\\rm boil}$ (above which boiling may be important) with three typical values for the confinement parameter $D$. It is firstly found that the baryon interaction with a softer equation of state for the hadron phase would only lead to a small increase of $A_{\\rm boil}$. However, results depend sensitively on the confinement parameter in the quark model. Specifically, boiling might be important during the Universe cooling for a limited parameter range around $D^{1/2} = 170$ MeV, a value satisfying recent lattice QCD calculations of the vacuum chiral condensate, while for other choices of this parameter, boiling might not happen and cosmological quark nuggets of $10^2 < A < 10^{50}$ could survive.

Ang Li; Tong Liu; Philipp Gubler; Ren-Xin Xu

2013-12-13T23:59:59.000Z

71

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

SciTech Connect

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

72

Modelling Power Output at Nuclear Power Plant by Neural Networks  

Science Journals Connector (OSTI)

In this paper, we propose two different neural network (NN) approaches for industrial process signal forecasting. Real data is available for this research from boiling water reactor type nuclear power reactors. N...

Jaakko Talonen; Miki Sirola; Eimontas Augilius

2010-01-01T23:59:59.000Z

73

Sodium boiling dryout correlation for LMFBR fuel assemblies  

SciTech Connect

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

74

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

75

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.

76

Experiments on adding a surfactant to water drops boiling on a hot surface  

Science Journals Connector (OSTI)

...photographs of droplets of water impacting on a hot surface...to film boiling for water and hydrocarbons. Baumeister & Simon...predicting TLeid for hydrocarbons and cryogens, but failed...surfactant to boiling water drops 685 Figure 8...

1997-01-01T23:59:59.000Z

77

Enhancing nuclear power safety  

Science Journals Connector (OSTI)

Through its ClydeUnion Pumps brand, SPX has a long history of providing pumps to the nuclear power industry and is working to help provide solutions that enhance vital safety systems on these plants. Compared with traditional alternatives, its TWL steam turbine driven pump is designed to increase the reliability of systems that provide heat removal from pressurised water reactors and boiling water reactors during extended emergency periods.

2014-01-01T23:59:59.000Z

78

Nucleation characteristics and stability considerations during flow boiling in microchannels  

E-Print Network (OSTI)

[4,5]. The major concerns relate to (i) increased effects of surface tension forces, (ii) reverse of Hsu [6]. Bubbles are formed over the cavities that are present on a heater surface. As a bubble coversNucleation characteristics and stability considerations during flow boiling in microchannels Satish

Kandlikar, Satish

79

Steady-state solutions in a nonlinear pool boiling model Michel Speetjens  

E-Print Network (OSTI)

convection as a means for heat transfer between a heater surface and the boiling fluid; it is the key mode dynamics, heat transfer from the heater to the fluid and phase transfer. Studies on boiling known within the heater and describes the heat exchange with the boiling fluid via a nonlinear boundary

80

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

Note: This page contains sample records for the topic "boiling nuclear superheater" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
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81

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

82

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

83

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

SciTech Connect

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

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

1989-12-01T23:59:59.000Z

84

Analysis of nuclear reactor instability phenomena  

SciTech Connect

The phenomena known as density-wave instability often occurs in phase change systems, such as boiling water nuclear reactors (BWRS). Our current understanding of density-wave oscillations is in fairly good shape for linear phenomena (eg, the onset of instabilities) but is not very advanced for non-linear phenomena [Lahey and Podowski, 1989]. In particular, limit cycle and chaotic instability modes are not well understood in boiling systems such as current and advanced generation BWRs (eg, SBWR). In particular, the SBWR relies on natural circulation and is thus inherently prone to problems with density-wave instabilities. The purpose of this research is to develop a quantitative understanding of nonlinear nuclear-coupled density-wave instability phenomena in BWRS. This research builds on the work of Achard et al [1985] and Clausse et al [1991] who showed, respectively, that Hopf bifurcations and chaotic oscillations may occur in boiling systems.

Lahey, R.T. Jr.

1993-01-01T23:59:59.000Z

85

Great Boiling Springs Geothermal Area | Open Energy Information  

Open Energy Info (EERE)

Boiling Springs Geothermal Area Boiling Springs Geothermal Area Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Geothermal Resource Area: Great Boiling Springs Geothermal Area Contents 1 Area Overview 2 History and Infrastructure 3 Regulatory and Environmental Issues 4 Exploration History 5 Well Field Description 6 Geology of the Area 7 Geofluid Geochemistry 8 NEPA-Related Analyses (0) 9 Exploration Activities (0) 10 References Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"TERRAIN","zoom":6,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"500px","height":"300px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":40.66166667,"lon":-119.3616667,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

86

Modelling power output at nuclear power plant by neural networks  

Science Journals Connector (OSTI)

In this paper, we propose two different neural network (NN) approaches for industrial process signal forecasting. Real data is available for this research from boiling water reactor type nuclear power reactors. NNs are widely used for time series prediction, ... Keywords: evaluation methods, model input selection, neural networks, nuclear power plant, one-step ahead prediction

Jaakko Talonen; Miki Sirola; Eimontas Augilius

2010-09-01T23:59:59.000Z

87

Study of plutonium disposition using existing GE advanced Boiling Water Reactors  

SciTech Connect

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

Not Available

1994-06-01T23:59:59.000Z

88

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

E-Print Network (OSTI)

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

Meholic, Michael

2011-01-01T23:59:59.000Z

89

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

E-Print Network (OSTI)

??General Electric plans to complete a design certification document for the Economic Simplified Boiling Water Reactor to have the new reactor design certified by the… (more)

Dawson, Phillip Eng

2007-01-01T23:59:59.000Z

90

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

SciTech Connect

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

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

2004-10-06T23:59:59.000Z

91

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

92

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

SciTech Connect

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

93

Test results of the US-LCT pool-boiling coils in the International Fusion Superconducting Magnet Test Facility (IFSMTF)  

SciTech Connect

The international Large Coil Task (LCT) has designed, built, and successfully tested six different toroidal field coils. Each has a 2.5- x 3.5-m D-shaped bore, a current between 10 and 18 kA, and is designed for stable operation at 8 T, with a superimposed pulsed field of 0.14 T in 1.0 s, and simulated nuclear heating. Included in the torus are two pool-boiling coils designed and fabricated by US firms, General Dynamics/Convair Division (GD) and General Electric/Oak Ridge National Laboratory (GE). Both coils were well instrumented for studies of electromagnetic, mechanical, and thermodynamic properties. Both coils performed well and met design specifications. In later ''extended-condition'' full-array tests beyond the design values, both operated stably at 100% design current and above 9 T, even with bath temperature higher than 4.3 K. The mechanical behavior of both coils was generally in good agreement with calculations. Both coils were also safely discharged several times in the extended-condition tests. All results indicate that the technology developed for these two pool-boiling LCT coils can be directly applied for future large-scale applications. 5 refs., 5 figs., 9 tabs.

Shen, S.S.; Dresner, L.; Lubell, M.S.; Lue, J.W.; Luton, J.N.; McManamy, T.J.; Wilson, C.T.; Wintenberg, R.E.

1987-01-01T23:59:59.000Z

94

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.

95

Scale effects on flow boiling heat transfer in microchannels: A fundamental perspective  

E-Print Network (OSTI)

pattern transitions and stability for flow boiling of water and FC-77 are evaluated. From the insight between heat transfer around a nucleating bubble in pool boiling and in the elongated bubble/slug flow on the high-speed visualization and localized thermal measurements made at the base of a nucleating bubble

Kandlikar, Satish

96

DOE - Office of Legacy Management -- Bonus  

Office of Legacy Management (LM)

Puerto Rico Puerto Rico Boiling Nuclear Superheater (BONUS), Puerto Rico, Decommissioned Reactor Site La Antiqua Central Nuclear de Aqua Hirviente Sobrecalentada Reactor Fuera de Servico Activo A D&D Program Site bonus_map3 As part of the DOE Defense Decontamination and Decommissioning (D&D) Program, the Office of Legacy Management manages the Boiling Nuclear Superheater (BONUS) Decommissioned Reactor Site and ensures compliance with applicable federal, state, and local environmental protection laws and regulations, executive orders, and internal DOE policies. The site transferred to the Office of Legacy Management in 2004 and requires routine inspection and maintenance, records-related activities, and stakeholder support. For more information about the BONUS site, view the fact sheet.

97

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

98

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

SciTech Connect

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

99

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

SciTech Connect

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

100

Nonlinear dynamics and chaos in boiling water reactors  

SciTech Connect

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

Note: This page contains sample records for the topic "boiling nuclear superheater" 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

Heat transfer enhancement mechanism of pool boiling with self-rewetting fluid  

Science Journals Connector (OSTI)

Abstract Self-rewetting fluid (SRWF) is believed to be a promising and useful working liquid for the application of boiling to the development of high efficient cooling devices with micro structure. To clarify the fundamental heat transfer characteristic and heat transfer enhancement mechanism of pool boiling with SRWF, by employing dilute heptanol aqueous solution as SRWF, a series of boiling experiments have been carried out. In pool boiling tests, a boiling system using a horizontal heated wire was employed. The experimental results show that, the critical heat flux (CHF) of the SRWF increased up to 2.52 times the CHF of water, and the heat transfer enhancement mechanism was discussed. With a high speed video camera, the nucleation boiling process on the heated wire has been recorded. It is found out that, the bubble size of the SRWF is much smaller than that of pure water, and the bubbles of SRWF were hard to coalesce, which is beneficial for the application in small thermal devices. Furthermore, when the heat flux was up to a certain value, the micro-bubble emission boiling (MEB) appeared in the SRWF. It can be concluded that the Marangoni convection induced by surface tension gradient of SRWF is probably one of the key factors causing the formation of MEB.

Yanxin Hu; Suling Zhang; Xuanyou Li; Shuangfeng Wang

2014-01-01T23:59:59.000Z

102

Analysis of nuclear reactor instability phenomena. Progress report  

SciTech Connect

The phenomena known as density-wave instability often occurs in phase change systems, such as boiling water nuclear reactors (BWRS). Our current understanding of density-wave oscillations is in fairly good shape for linear phenomena (eg, the onset of instabilities) but is not very advanced for non-linear phenomena [Lahey and Podowski, 1989]. In particular, limit cycle and chaotic instability modes are not well understood in boiling systems such as current and advanced generation BWRs (eg, SBWR). In particular, the SBWR relies on natural circulation and is thus inherently prone to problems with density-wave instabilities. The purpose of this research is to develop a quantitative understanding of nonlinear nuclear-coupled density-wave instability phenomena in BWRS. This research builds on the work of Achard et al [1985] and Clausse et al [1991] who showed, respectively, that Hopf bifurcations and chaotic oscillations may occur in boiling systems.

Lahey, R.T. Jr.

1993-03-01T23:59:59.000Z

103

DOE LM/GJ596  

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

LM/GJ596 LM/GJ596 2004 - - U.S. Department of Energy Long-Term Surveillance and Maintenance Plan for the Boiling Nuclear Superheater (BONUS) Reactor Facility, RincĂłn, Puerto Rico May 2005 Work Performed Under DOE Contract No. for the U.S. Department of Energy Office of Legacy Management. DE-AC01-02GJ79491 Approved for public release; distribution is unlimited. Office of Legacy Management Office of Legacy Management Office of Legacy Management Office of Legacy Management S0109100 DOE-LM/GJ596-2004 Long-Term Surveillance and Maintenance Plan for the Boiling Nuclear Superheater (BONUS) Reactor Facility RincĂłn, Puerto Rico May 2005 Work Performed by S.M. Stoller Corporation under DOE Contract No. DE-AC01-02GJ79491 for the U.S. Department of Energy Office of Legacy Management, Grand Junction, Colorado

104

DOE - Office of Legacy Management -- Bonus  

Office of Legacy Management (LM)

Puerto Rico Puerto Rico Boiling Nuclear Superheater (BONUS), Puerto Rico, Decommissioned Reactor Site This Site All Sites All LM Quick Search Key Documents and Links All documents are Adobe Acrobat files. pdf_icon Key Documents Fact Sheet BONUS, Puerto Rico, Reactor Clausurado, Hoja de Datos Long-Term Surveillance and Maintenance Plan Plan para la vigilance y mantenimiento a largo plaza Please be green. Do not print these documents unless absolutely necessary. Request a paper copy of any document by submitting a Document Request. All Site Documents All documents are Adobe Acrobat files. pdf_icon Fact Sheet Reports Other Documents Español Documents Fact Sheet Boiling Nuclear Superheater, Puerto Rico, Site Fact Sheet August 2012 Reports PREPA-DOE Letter of Agreement July 2010

105

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

106

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

E-Print Network (OSTI)

angle was measured both before and after the experiments. Nucleate pool boiling heat transfer was enhanced with increase in pillar height. Numerical predictions for R_(k) obtained from Molecular Dynamics (MD) simulations were found to be consistent...

Yang, Hongjoo

2014-08-10T23:59:59.000Z

107

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

108

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

109

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

2012-06-07T23:59:59.000Z

110

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

111

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

112

Metal boiling under the action of an electron-beam heat source  

Science Journals Connector (OSTI)

The dynamics of vapor bubble growth in a metal alloy under the action of a volume heat source are considered. The possibility of existence of a threshold superheating value below which the boiling process is i...

G. E. Gorelik; A. S. Lerman; N. V. Pavlyukevich…

1975-10-01T23:59:59.000Z

113

Method of controlling crystallite size in nuclear-reactor fuels  

DOE Patents (OSTI)

Improved spherules for making enhanced forms of nuclear-reactor fuels are prepared by internal gelation procedures within a sol-gel operation and are accomplished by first boiling the concentrated HMTA-urea feed solution before engaging in the spherule-forming operation thereby effectively controlling crystallite size in the product spherules.

Lloyd, Milton H. (Oak Ridge, TN); Collins, Jack L. (Knoxville, TN); Shell, Sam E. (Oak Ridge, TN)

1985-01-01T23:59:59.000Z

114

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

E-Print Network (OSTI)

has advan- tages, and the results are shown to be identical. The first method was used by Hale and Wallis [3) in a similar analysis, and. is an eigenfunction method using distributed parameters. This is followed by a simple lumped parameter.... Therefore, to apply Auditori's criterion to design problems involving boiling and to predict system be- havior under unstable conditions, the slope of the boiling curve, o , in the transition region, must 3T be known. Wallis and. Collier [2] found...

Qaim-Maqami, Hassan

2012-06-07T23:59:59.000Z

115

Boiling-Water Reactor internals aging degradation study. Phase 1  

SciTech Connect

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

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

1993-09-01T23:59:59.000Z

116

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

SciTech Connect

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

117

Model for boiling and dryout in particle beds. [LMFBR  

SciTech Connect

Over the last ten years experiments and modeling of dryout in particle beds have produced over fifty papers. Considering only volume-heated beds, over 250 dryout measurements have been made, and are listed in this work. In addition, fifteen models to predict dryout have been produced and are discussed. A model is developed in this report for one-dimensional boiling and dryout in a porous medium. It is based on conservation laws for mass, momentum, and energy. The initial coupled differential equations are reduced to a single first-order differential equation with an algebraic equation for the upper boundary condition. The model includes the effects of both laminar and turbulent flow, two-phase friction, and capillary force. The boundary condition at the bed bottom includes the possibility of inflowing liquid and either an adiabatic or a bottom-cooled support structure. The top of the bed may be either channeled or subcooled. In the first case the channel length and the saturation at the base of the channels are predicted. In the latter case, a criterion for penetration of the subcooled zone by channels is obtained.

Lipinski, R. J.

1982-06-01T23:59:59.000Z

118

Nuclear Energy  

Science Journals Connector (OSTI)

Nuclear Energy ... A brief summary of the history and key concepts of nuclear energy. ... Nuclear / Radiochemistry ...

Charles D. Mickey

1980-01-01T23:59:59.000Z

119

Nuclear batteries  

Science Journals Connector (OSTI)

Nuclear batteries ... Describes the structure, operation, and application of nuclear batteries. ... Nuclear / Radiochemistry ...

Alfred B. Garrett

1956-01-01T23:59:59.000Z

120

Assessment of typical BWR (boiling water reactor) vessel configurations and examination coverage  

SciTech Connect

Even though boiling water reactors (BWRs) are not susceptible to the kind of incident known as pressurized thermal shock that must be considered in the design and operation of pressurized water reactors, BWR reactor pressure vessels (RPVs) have experienced higher than expected embrittlement caused by fast neutron irradiation. This has required the vessel to be at a higher temperature than originally projected before the plant can be taken to power operation. In addition, many BWR plants have received exemption from the 10-year volumetric nondestructive evaluation (NDE) of the vessel as required by the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B PV) Code Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components,'' because NDE access is severely restricted. Since many RPV welds have not been examined after being placed in service and the potential for service-induced flaws exists, regulatory authorities are looking closely at examination relief requests. BWR reactor vessel examination coverage is typically limited by plant design. Most BWR plants were designed when inservice examination codes were in the early stages of development, and very little consideration was give to designing for NDE access. Consequently, there is restricted access for many areas of the RPV. Since an increase in examination requirements has been placed in ASME B PV Code Section XI in these areas, efforts have begun on a thorough analysis of the vessel weld volumes examined during inservice examination and an evaluation of possibility expanding the RPV examination coverage. Because of these concerns, an investigation of the accessibility of the reactor vessel for NDE was performed to define the present status and to determine the improvements in coverage that can be accomplished in the near future. 7 refs., 9 figs., 4 tabs.

Walker, S.M. (EPRI Nondestructive Evaluation Center, Charlotte, NC (USA)); Feige, E.J.; Ingamells, J.R. (Southwest Research Inst., San Antonio, TX (USA)); Calhoun, G.L.; Davis, J.; Kapoor, A. (Westinghouse Electric Corp., Pittsburgh, PA (USA))

1990-10-01T23:59:59.000Z

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121

Test results of the U. S. -LCT pool-boiling coils in the International Fusion Superconducting Magnet Test Facility (IFSMTF)  

SciTech Connect

The international Large Coil Task (LCT) has designed, built, and successfully tested six different toroidal field coils. Each has a 2.5- x 3.5-m D-shaped bore, a current between 10 and 18 kA, and is designed for stable operation at 8 T with a superimposed pulsed field of 0.14 T in 1.0 s and simulated nuclear heating. Included in the torus are two pool-boiling coils designed and fabricated by U.S. firms, General Dynamics/Convair Division (GD) and General Electric/Oak Ridge National Laboratory (GE). Both coils were well instrumented for studies of electromagnetic, mechanical, and thermodynamic properties. Testing of the torus started early in 1986 and was successfully completed on September 3, 1987, although the pulsed field tests with GD and GE had to be deleted from the test program because it was not feasible to devote the required few months to repair the mechanism for moving the pulse coil system to these two test coils. Both coils performed well and met design specifications. In later ''extended-condition'' full-array tests beyond the design values, both operated stably at 100% design current and above 9 T, even with bath temperature higher than 4.3 K. The mechanical behaviour of both coils was generally in good agreement with calculations. Both coils were also safely discharged several times in the extended-condition tests. All results indicate that the technology developed for these two pool-boiling LT coils can be directly applied for future large-scale applications.

Shen, S.S.; Dresner, L.; Lubell, M.S.; Lue, J.W.; Luton, J.N.; McManamy, T.J.; Wilson, C.T.; Wintenberg, R.E.

1988-03-01T23:59:59.000Z

122

Nuclear Forensics  

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nuclear forensics Nuclear Forensics AMS is a Powerful Tool for Nuclear Forensics Nuclear forensics, which can be applied to both interdicted materials and debris from a nuclear...

123

Development of Boiling Water Reactor Nuclear Power Plant Simulator for Human Reliability Analysis Education and Research.  

E-Print Network (OSTI)

??This thesis discusses the development of Full scope BWR Simulator developed for human reliability course initiated at The Ohio State University. Human System Interface (HSI)… (more)

Gupta, Atul

2013-01-01T23:59:59.000Z

124

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

125

Bubble dynamics and boiling heat transfer : a study in the absence and in the presence of electric fields.  

E-Print Network (OSTI)

??Since boiling heat transfer affords a very effective means to transfer heat, it is implemented in numerous technologies and industries ranging from large power generation… (more)

Siedel, Samuel

2012-01-01T23:59:59.000Z

126

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

SciTech Connect

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

127

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

SciTech Connect

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

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

1993-06-01T23:59:59.000Z

128

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

SciTech Connect

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

Lund, A.L.

1997-11-01T23:59:59.000Z

129

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

SciTech Connect

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

Barclay G. Jones

2008-10-01T23:59:59.000Z

130

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

131

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

E-Print Network (OSTI)

, 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... TWl Tvvo Heat flux of EHD enhancement of boiling (W/m ) Total heat flux with EHD at 10kV (W/m ) Total heat flux with no EHD (W/m ) Minimum cavity mouth radius (m) Rayleigh number Fluid temperature ('C) Pool Saturation temperature ('C) Tube...

Raghupathi, Sri Laxmi Priya

2012-06-07T23:59:59.000Z

132

Film Boiling in Presence of a Magnetic Field in Liquid Metals Within Framework of Taylor–Helmholtz Instabilities in Application to Fusion Reactor Project  

Science Journals Connector (OSTI)

Whereas a lot of research has been done on boiling of various fluids [1] including liquid metals [2] not much work exists on Magnetohydrodynamic MHD boiling [3] and although some theoretical aspects of MHD boilin...

F. J. Arias

2010-04-01T23:59:59.000Z

133

A Lattice Boltzmann Framework for the simulation of boiling hydrodynamics in BWRs.  

SciTech Connect

Multi phase and multi component flows are ubiquitous in nature as well as in many man-made processes. A specific example is the Boiling Water Reactor (BWR) core, in which the coolant enters the core as liquid, undergoes a phase change as it traverses the core and exits as a high quality two-phase mixture. Two-phase flows in BWRs typically manifest a wide variety of geometrical patterns of the co-existing phases depending on the local system conditions. Modeling of such flows currently relies on empirical correlations (for example, in the simulation of bubble nucleation, bubble growth and coalescence, and inter-phase surface topology transitions) that hinder the accurate simulation of two-phase phenomena using Computational Fluid Dynamics (CFD) approaches. The Lattice Boltzmann Method (LBM) is in rapid development as a modeling tool to understand these macro-phenomena by coupling them with their underlying micro-dynamics. This paper presents a consistent LBM formulation for the simulation of a two-phase water-steam system. Results of initial model validation in a range of thermodynamic conditions typical for BWRs are also shown. The interface between the two coexisting phases is captured from the dynamics of the model itself, i.e., no interface tracking is needed. The model is based on the Peng-Robinson (P-R) non-ideal equation of state and can quantitatively approximate the phase-coexistence curve for water at different temperatures ranging from 125 to 325 oC. Consequently, coexisting phases with large density ratios (up to {approx}1000) may be simulated. Two-phase models in the 200-300 C temperature range are of significant importance to nuclear engineers since most BWRs operate under similar thermodynamic conditions. Simulation of bubbles and droplets in a gravity-free environment of the corresponding coexisting phase until steady state is reached satisfies Laplace law at different temperatures and thus, yield the surface tension of the fluid. Comparing the LBM surface tension thus calculated using the LBM to the corresponding experimental values for water, the LBM lattice unit (lu) can be scaled to the physical units. Using this approach, spatial scaling of the LBM emerges from the model itself and is not imposed externally.

Jain, P. K.; Tentner, A.; Uddin, R. (Nuclear Engineering Division); (Univ. of Illinois)

2008-01-01T23:59:59.000Z

134

Experiments on adding a surfactant to water drops boiling on a hot surface  

Science Journals Connector (OSTI)

...surfactant to boiling water drops 675 done with three...0 ppm (i.e. pure water), 100 ppm and 1000...and ambient pressure (atmospheric). 2. Experimental...surfactant to 800 g of water. The water was distilled...solution in the droplet generator the syringe, needle...

1997-01-01T23:59:59.000Z

135

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

136

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

137

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

138

BUBBLE CHARACTERISTICS AND CONVECTIVE EFFECTS IN THE FLOW BOILING HEAT TRANSFER OF BINARY MIXTURES  

E-Print Network (OSTI)

BUBBLE CHARACTERISTICS AND CONVECTIVE EFFECTS IN THE FLOW BOILING HEAT TRANSFER OF BINARY MIXTURES on the bubble growth and associated heat transfer phenomena. The present work focuses on obtaining the bubble. The bubble growth is observed using a high speed camera (1000 fps) under a magnification of 290X. The bubble

Kandlikar, Satish

139

QSPR models of boiling point, octanolwater partition coefficient and retention time index of polycyclic aromatic hydrocarbons  

E-Print Network (OSTI)

QSPR models of boiling point, octanol­water partition coefficient and retention time index of polycyclic aromatic hydrocarbons Fabiana Alves de Lima Ribeiro, Ma´rcia Miguel Castro Ferreira* Laborato Structure­Property Relationship (QSPR) analysis and study of polycyclic aromatic hydrocarbons (PAHs

Ferreira, Márcia M. C.

140

Bubble departure in the direct-contact boiling field with a continuous liquid-liquid interface  

SciTech Connect

Behavior of vapor bubbles was experimentally investigated in the boiling field where a volatile liquid layer of per-fluorocarbon PF5050 (boiling point 306K) was directly in contact with an immiscible hot liquid layer of water above it. Heat was supplied to the continuous liquid-liquid interface by the impingement of the downward hot water jet. Vapor bubbles were generated not only from this continuous interface but from a large number of PF5050 droplets floating on it. According to precise observation, incipience of boiling did not occur at the liquid-liquid interface but in the PF5050 liquid close to the interface in both cases of continuous and dispersed interfaces. As a result, the bubbles broke up the thin PF5050 liquid film above them and rose up into the water layer. This bubble departure phenomenon, which does not occur in the ordinary pool boiling field on the solid heating wall, is very important to evaluate the heat transfer performance in the present direct-contact boiling system. For modeling this behavior, sizes of the bubbles were measured at the moment just after they were released into the water pool. Volumes of the bubbles were larger in the case of departing from the continuous liquid-liquid interface than from the droplets. This tendency could be explained by taking into account the buoyancy force acting on unit area of the thin PF5050 liquid film above the bubble before departure, which was one of the most important parameters for the liquid film breakdown. (author)

Kadoguchi, Katsuhiko [Energy Technology Research Institute, National Institute of Advanced Industrial Science and Technology (AIST), 16-1 Onogawa, Tsukuba, Ibaraki 305-8569 (Japan)

2007-01-15T23:59:59.000Z

Note: This page contains sample records for the topic "boiling nuclear superheater" 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

Hydrocarbon steam reforming using series steam superheaters  

SciTech Connect

In a process for steam reforming of a hydrocarbon gas feedstream wherein: the hydrocarbon gas feedstream is partially reformed at elevated temperatures in indirect heat exchange with hot combustion gases in a direct fired primary reforming furnace provided with a convection section for recovery of excess heat from said combustion gases; and the partially reformed feedstream is then further reformed in the presence of an oxygen-containing gas and steam in a secondary reformer to form a secondary reformer gaseous effluent; the improvement which comprises recovering waste heat from said secondary reformer effluent gas and from said primary reforming combustion products by heating a high pressure saturated steam in a first steam superheating zone by indirect heat exchange with at least a portion of said secondary reformer effluent gas to form a first superheated steam stream; and further heating said first superheated steam in a second steam superheating zone by indirect heat exchange with at least a portion of said primary reformer hot combustion gases for form a second superheated steam stream.

Osman, R. M.

1985-10-08T23:59:59.000Z

142

Nuclear Energy  

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Research Programs >> Nuclear Energy Error Error Nuclear Energy Home - RCC cannot be displayed due to a timeout error. We recommend: * Refresh Nuclear Energy Home - RCC * Increasing...

143

Acoustic method for measurements of the coolant boiling on heat generating surfaces  

Science Journals Connector (OSTI)

Acoustic method for determining the period of different duties of the coolant boiling is presented. The foundation of this method is the damping phenomenon of ultrasonic waves travelling through the boundary between different media (steam–liquid) differing widely in their acoustic properties. The experimental setup and the results of the investigations into the period of water film boiling on spherical samples are also presented. The emphasis is on aluminum and copper samples differing in their diameter (4 5 and 8 mm) for temperature interval ?t=180–690°C at atmospheric pressure and different surrounding water temperatures (?t=15–75°C). By analyzing the result it is illustrated that the precision of the method is well above that of thermocouples. It is demonstrated that the measurements using this acoustic method excludes the errors typical of traditional methods. ?

2001-01-01T23:59:59.000Z

144

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

SciTech Connect

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

145

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

SciTech Connect

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

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

1986-01-01T23:59:59.000Z

146

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

147

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

148

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

149

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

150

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

151

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

SciTech Connect

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

152

May 13, 1998 Gas Frac. Mol.Wt. Density Speci c Ht. Boil. Pt.  

E-Print Network (OSTI)

. Automatic switch from empty to full bottles DataLink ethernet 4 #12;Gas Mixing Station Four independent gas.Rate Normal Rate Station of Gas SCCM SCCM SCCM Barrel HFC-134a 0.32 10,000 3,200 1,240 Inner Ar 1.37 5,000 6K.Abe Gas System May 13, 1998 RPC Gas Gas Frac. Mol.Wt. Density Speci c Ht. Boil. Pt. g=l cal=g c c

Llope, William J.

153

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

154

Nuclear Debate  

Science Journals Connector (OSTI)

Nuclear Debate ... This month, the Senate will consider the nominations of two women to serve on the Nuclear Regulatory Commission. ... Svinicki is a nuclear engineer with experience in the Department of Energy’s nuclear energy programs. ...

JEFF JOHNSON

2012-06-11T23:59:59.000Z

155

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

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

156

Acoustic monitoring and signature analysis in nuclear and fossil energy generation  

Science Journals Connector (OSTI)

Acoustic monitoring and analysis in nuclear and fossil energy plants has been accompanied by transducer development for the hot environment. The Nuclear Regulatory Commission requires acoustic monitoring systems on nuclear reactors for detecting potential failures. Accelerometers are attached at critical points and their output is automatically analyzed to give warnings of loose parts or excessive vibration. In addition to providing a warning the system can monitor arrival time to be used for fault location. For use as a potential boiling detector of breeder reactors the acoustic signature of the sodium coolant boiling has been compared with background noise level. High temperature sodium?immersible microphones and waveguides for smooth energy transfer were developed for this investigation. High?temperature acoustic sensors have been used in a coal gasification plant. The presence of solids in a steam?char line has been automatically determined using passive monitoring of relative sound intensities of different frequency bands.

Henry B. Karplus

1982-01-01T23:59:59.000Z

157

Nuclear Resonance Fluorescence for Nuclear Materials Assay  

E-Print Network (OSTI)

Potential of Nuclear Resonance Fluorescence . . . . . . . .2.9.1 Nuclear ThomsonSections . . . . . . . . . . . . . . . Nuclear Resonance

Quiter, Brian Joseph

2010-01-01T23:59:59.000Z

158

Nuclear Returns  

Science Journals Connector (OSTI)

Nuclear Returns ... For the first time since 1978, the Nuclear Regulatory Commission has given the green light for a new U.S. nuclear power plant. ... NRC granted a license to Southern Co. to build and operate twin 1,100-MW reactors adjacent to two operating nuclear power plants at its Vogtle nuclear facility, near Waynesboro, Ga. ...

JEFF JOHNSON

2012-02-19T23:59:59.000Z

159

Experimental Study on Heat Transfer of Single-Phase Flow and Boiling Two-Phase Flow in Vertical Narrow Annuli  

SciTech Connect

Water single-phase and nucleate boiling heat transfer were experimentally investigated in vertical annuli with narrow gaps. The experimental data about water single-phase flow and boiling two-phase flow heat transfer in narrow annular channel were accumulated by two test sections with the narrow gaps of 1.0 mm and 1.5 mm. Empirical correlations to predict the heat transfer of the single-phase flow and boiling two-phase flow in the narrow annular channel were obtained, which were arranged in the forms of the Dittus-Boelter for heat transfer coefficients in a single-phase flow and the Jens-Lottes formula for a boiling two-phase flow in normal tubes, respectively. The mechanism of the difference between the normal channel and narrow annular channel were also explored. From experimental results, it was found that the turbulent heat transfer coefficients in narrow gaps are nearly the same to the normal channel in the experimental range, and the transition Reynolds number from a laminar flow to a turbulent flow in narrow annuli was much lower than that in normal channel, whereas the boiling heat transfer in narrow annular gap was greatly enhanced compared with the normal channel. (authors)

Suizheng Qiu; Guanghui Su; Dounan Jia [Xi'an Jiaotong University, No.28, Xianning West Road, Xi'an, Shaanxi, 710049 (China); Minoru Takahashi [Tokyo Institute of Technology, O-okayama, Meguro-ku, Tokyo 152 (Japan)

2002-07-01T23:59:59.000Z

160

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

SciTech Connect

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

Note: This page contains sample records for the topic "boiling nuclear superheater" 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

Piping benchmark problems for the General Electric Advanced Boiling Water Reactor  

SciTech Connect

To satisfy the need for verification of the computer programs and modeling techniques that will be used to perform the final piping analyses for an advanced boiling water reactor standard design, three benchmark problems were developed. The problems are representative piping systems subjected to representative dynamic loads with solutions developed using the methods being proposed for analysis for the advanced reactor standard design. It will be required that the combined license holders demonstrate that their solutions to these problems are in agreement with the benchmark problem set.

Bezler, P.; DeGrassi, G.; Braverman, J.; Wang, Y.K. [Brookhaven National Lab., Upton, NY (US)

1993-08-01T23:59:59.000Z

162

Nuclear Fusion  

Science Journals Connector (OSTI)

Although not yet developed at the commercial stage, nuclear fusion technology is still being considered as a ... used in nuclear warfare. Since research in nuclear fusion for the production of energy started abou...

Ricardo Guerrero-Lemus; José Manuel Martínez-Duart

2013-01-01T23:59:59.000Z

163

Nuclear Nonproliferation  

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

Nuclear Nonproliferation As more countries embrace nuclear power as a cost-effective and clean alternative to fossil fuels, the need exists to ensure that the nuclear fuel cycle is...

164

Nuclear Engineering Nuclear Criticality Safety  

E-Print Network (OSTI)

Nuclear Engineering Nuclear Criticality Safety The Nuclear Engineering Division (NE) of Argonne National Laboratory is experienced in performing criticality safety and shielding evaluations for nuclear, and neutron spectra. The NE nuclear criticality safety (NCS) capabilities are based on a staff with decades

Kemner, Ken

165

AtomicNuclear Properties  

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

HTML_PAGES HTML_PAGES This AtomicNuclearProperties page is under intermittent development. Suggestions and comments are welcome. Please report errors. Chemical elements: For entries in red, a pull-down menu permits selection of the physical state. Cryogenic liquid densties are at the boiling point at 1 atm. 0n 1Ps 1H 2He 3Li 4Be 5B 6C 7N 8O 9F 10Ne 11Na 12Mg 13Al 14Si 15P 16S 17Cl 18Ar 19K 20Ca 21Sc 22Ti 23V 24Cr 25Mn 26Fe 27Co 28Ni 29Cu 30Zn 31Ga 32Ge 33As 34Se 35Br 36Kr 37Rb 38Sr 39Y 40Zr 41Nb 42Mo 43Tc 44Ru 45Rh 46Pd 47Ag 48Cd 49In 50Sn 51Sb 52Te 53I 54Xe 55Cs 56Ba 57La 72Hf 73Ta 74W 75Re 76Os 77Ir 78Pt 79Au 80Hg 81Tl 82Pb 83Bi 84Po 85At 86Rn 87Fr 88Ra 89Ac 104Rf 105Db 106Sg 107Bh 108Hs 109Mt 110Ds 111Rg 112 113 114 115 116 mt 118

166

NUCLEAR REACTORS.  

E-Print Network (OSTI)

??Nuclear reactors are devices containing fissionable material in sufficient quantity and so arranged as to be capable of maintaining a controlled, self-sustaining NUCLEAR FISSION chain… (more)

Belachew, Dessalegn

2010-01-01T23:59:59.000Z

167

nuclear reactor  

Science Journals Connector (OSTI)

...a complex atomic apparatus used to obtain energy from nuclear fission chain reaction. Used to produce nuclear energy, radioactive isotopes, and artificial elements.... atomic pile ...

2009-01-01T23:59:59.000Z

168

Nuclear Energy  

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

Nuclear Energy Idaho National Laboratory is the Department of Energy's lead nuclear energy research and development facility. Building upon its legacy responsibilities,...

169

Nuclear Hydrogen  

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

Error Error Nuclear Hydrogen - RCC cannot be displayed due to a timeout error. We recommend: * Refresh Nuclear Hydrogen - RCC * Increasing your portlet timeout setting. *...

170

Nuclear Physics  

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

Underground Research Facility in South Dakota, which will search for neutrinoless double-beta decay. Strong Los Alamos programs in nuclear data and nuclear theory supports...

171

Experimental Investigation on Density Wave Instability of Sodium Boiling Two-Phase Flow in an Annulus  

SciTech Connect

Experiments of density wave instability in a liquid sodium boiling two-phase flow experiments in an annulus were carried out in the following parameters range: heat flux from 80 kW/m{sup 2} to 976 kW/m{sup 2}, inlet subcooling from 25.6 deg. C to 226.8 deg. C, mass flow rate from 7.92 kg/h to 68.9 kg/h, system pressure from 2600 Pa to 0.12 Mpa. Not only the mechanism of the instability, critical conditions and oscillation period, but also the effects of pressure, mass flow rate and inlet subcooling on the density wave instability were explored experimentally and theoretically. From the experimental data, it was found that the lower the inlet temperature was, the higher the system pressure and the mass flow rate that could result in a more stable boiling two-phase flow were. A correlation for the density wave instability was obtained on from the dimensional analysis for the conservation equations of mass, momentum and energy. (authors)

Suizheng Qiu; Dounan Jia [Xi'an Jiaotong University, No.28, Xianning West Road, Xi'an, Shaanxi, 710049 (China); Minoru Takahashi [Tokyo Institute of Technology, O-okayama, Meguro-ku, Tokyo 152 (Japan)

2002-07-01T23:59:59.000Z

172

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

SciTech Connect

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

173

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

SciTech Connect

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

174

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

SciTech Connect

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

175

Nuclear Matter and Nuclear Dynamics  

E-Print Network (OSTI)

Highlights on the recent research activity, carried out by the Italian Community involved in the "Nuclear Matter and Nuclear Dynamics" field, will be presented.

M Colonna

2009-02-26T23:59:59.000Z

176

Observations of the boiling process from a downward-facing torispherical surface: Confirmatory testing of the heavy water new production reactor flooded cavity design  

SciTech Connect

Reactor-scale ex-vessel boiling experiments were performed in the CYBL facility at Sandia National Laboratories. The boiling flow pattern outside the RPV bottom head shows a center pulsating region and an outer steady two-phase boundary layer region. The local heat transfer data can be correlated in terms of a modified Rohsenow correlation.

Chu, T.Y.; Bentz, J.H.; Simpson, R.B.

1995-06-01T23:59:59.000Z

177

NREL: Energy Analysis - Nuclear Power Results - Life Cycle Assessment  

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

Nuclear Power Results - Life Cycle Assessment Harmonization Nuclear Power Results - Life Cycle Assessment Harmonization Over the last 30 years, analysts have conducted life cycle assessments on the environmental impacts associated with a variety of nuclear power technologies and systems. These life cycle assessments have had wide-ranging results. To better understand greenhouse gas (GHG) emissions from nuclear power systems, NREL completed a comprehensive review and analysis of life cycle assessments focused on light water reactors (LWRs)-including both boiling water reactors (BWRs) and pressurized water reactors (PWRs)-published between 1980 and 2010. NREL developed and applied a systematic approach to review life cycle assessment literature, identify primary sources of variability and, where possible, reduce variability in GHG emissions

178

Nuclear choices  

SciTech Connect

This book contains part of the series New Liberal Arts, which is intended to make science and technology more accessible to students of the liberal arts. Volume in hand provides a comprehensive, multifaceted examination of nuclear energy, in nontechnical terms. Wolfson explains the basics of nuclear energy and radiation, nuclear power..., and nuclear weapons..., and he invites readers to make their own judgments on controversial nuclear issues. Illustrated with photos and diagrams. Each chapter contains suggestions for additional reading and a glossary. For policy, science, and general collections in all libraries. (ES) Topics contained include Atoms and nuclei. Effects and uses of radiation. Energy and People. Reactor safety. Nuclear strategy. Defense in the nuclear age. Nuclear power, nuclear weapons, and nuclear futures.

Wolfson, R.

1991-01-01T23:59:59.000Z

179

Visualization study of bubble behavior in a subcooled flow boiling channel under rolling motion  

Science Journals Connector (OSTI)

Abstract Boiling heat transfer equipment in a vessel can be affected by the additional force which is generated by the rolling, swing and heaving motion of the vessel. Bubble behavior is very important for the research of boiling phenomenon. Bubble behavior under rolling motion condition is experimentally studied by using a high speed camera. The experiment is conducted in a subcooled flow boiling rectangular channel, and the cross section size of the channel is 2 mm × 40 mm. Two types of bubbles with large discrepancies in sliding and condensation behaviors can be observed in the captured images. The first type bubbles disappear quickly after generation and the slide distance is only a few times of bubble maximum diameter, while the second type bubbles can survive a longer time after leaving the nucleation site and slide for a long distance with the flowing fluid. Bubble characteristics under rolling motion are separately studied for different type bubbles based on the above reasons. The results show that the lifetime, maximum diameter, nucleation frequency and sliding velocity of the first type bubble are periodically fluctuated and the period is same with the rolling motion. The fluctuation intensity of the bubble lifetime and maximum diameter can be enhanced by the increase of the rolling amplitude. The peak value of bubble lifetime, maximum diameter, and nucleation frequency appears when the rolling platform plate rolls to the maximum positive angle, while opposite trend can be observed in the variation of bubble sliding velocity. In view of the characteristics of the second type bubbles, lifetime and maximum diameter are not measured. And the variation of nucleation frequency and sliding velocity of the second type bubbles under the effect of rolling motion is same with the first type bubbles. Furthermore, the effects of additional force, variation of local pressure and flow rate oscillation on bubble behavior are analyzed. The results indicate that the fluctuations of the bubble parameters can be generated by the variation of local pressure caused by rolling motion even no influential flow rate fluctuation occurs. The effect of the acceleration variation vertical to the heated surface on bubble behavior is unclear and need more researches in the future work.

Shaodan Li; Sichao Tan; Chao Xu; Puzhen Gao

2015-01-01T23:59:59.000Z

180

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

Note: This page contains sample records for the topic "boiling nuclear superheater" 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

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.

182

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

E-Print Network (OSTI)

Boiling Water at Hot Creek--The Dangerous and Dynamic Thermal Springs in California's Long Valley.S. Geological Survey USGS Fact Sheet 2007-3045 2007 T Hot Creek flows through the Long Valley Caldera Airport Fish hatchery CH-10B 44-16 Well Well Long Valley C aldera Area of Map Californ i a The thermal

Torgersen, Christian

183

Nonlinear dynamics and stability of boiling water reactors: Part 2 - Quantitative analysis  

SciTech Connect

A physical model of nonlinear boiling water reactor (BWR) dynamics has been developed and employed to calculate the amplitude of limit cycle oscillations and their effects on fuel integrity over a wide range of operating conditions in the Vermont Yankee reactor. These calculations have confirmed that, beyond the threshold for linear stability, the reactor's state variables undergo limit cycle oscillations. This work shows that the amplitudes of these oscillations are very sensitive to changes in operating conditions and are not restricted to small magnitudes as observed in previous stability tests. Consequently, large-amplitude limit cycle oscillations become a possible scenario for BWR operation at low-flow conditions. The effects on fuel integrity of such large-amplitude oscillations have been studied in detail. In particular, it has been shown that limit cycles that oscillate with frequencies higher than 0.25 Hz and that reach the high-power safety scram level of 120 % are not likely to compromise fuel integrity.

March-Leuba, J.; Cacuci, D.G.; Perez, R.B.

1986-06-01T23:59:59.000Z

184

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

SciTech Connect

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

185

Further considerations of critical heat flux in saturated pool boiling during power transients  

SciTech Connect

In this paper, we further evaluate our previously postulated transient CHF model. First, we verify the steady-state CHF model on which the transient model is based by using recent macrolayer-thickness data. We also include the effect of thermal storage in the heater that we previously neglected. The use of a simplified approach in the prediction of the instantaneous surface heat flux for given pwoer generation rates considerably improves the predictive capability of the transient critical heat-flux (CHF) model. Finally, we discuss the statistical vapor mass behavior during transient boiling and its effect on the transient CHF model. We show that the data scatter within a small range may be partially explained through such an approach.

Pasamehmetoglu, K.O.; Nelson, R.A.

1988-01-01T23:59:59.000Z

186

defense nuclear security | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

nuclear security | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response...

187

Chernobyl Nuclear Accident | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Chernobyl Nuclear Accident | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response...

188

Countering Nuclear Terrorism and Trafficking | National Nuclear...  

National Nuclear Security Administration (NNSA)

Countering Nuclear Terrorism and Trafficking | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy...

189

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

SciTech Connect

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

190

GE Hitachi Nuclear Energy | Open Energy Information  

Open Energy Info (EERE)

GE Hitachi Nuclear Energy GE Hitachi Nuclear Energy Jump to: navigation, search Name GE Hitachi Nuclear Energy Place Wilmington, North Carolina Zip 28402 Sector Efficiency, Services Product GE Hitachi Nuclear Energy develops advanced light water reactors and offers products and services used by operators of boiling water reactor (BWR) nuclear power plants to improve efficiency and boost output. Coordinates 42.866922°, -72.868494° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":42.866922,"lon":-72.868494,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

191

Bruce Nuclear Generating Station B rapid cooldown test and validation of simulation model  

SciTech Connect

The SOPHT code was assessed against Bruce Nuclear Generating Station B commissioning data from a heat transport system rapid cooldown. It was found that (a) under a rapid upstream depressurization, the steam relief valves, like orifices, had a lower discharge coefficient than the corresponding steadystate value and (b) the flashing of water in the steam generators during depressurization causes the at-power boiling heat transfer correlations to overpredict the steam generator heat transfer.

Chang, Y.F.; Langan, M.D.; Sermer, P.; Watson, P.C.

1985-09-01T23:59:59.000Z

192

Top U.S. Nuclear Official Commends Industry for Submitting 3rd Combined  

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

Top U.S. Nuclear Official Commends Industry for Submitting 3rd Top U.S. Nuclear Official Commends Industry for Submitting 3rd Combined Construction & Operating License Application to the NRC Top U.S. Nuclear Official Commends Industry for Submitting 3rd Combined Construction & Operating License Application to the NRC November 28, 2007 - 4:45pm Addthis RICHMOND, VA - The U.S. Department of Energy (DOE) Assistant Secretary for Nuclear Energy Dennis Spurgeon today commended Dominion North Anna, LLC (Dominion) for submission of a combined Construction and Operating License (COL) application to the Nuclear Regulatory Commission (NRC) for construction of a new nuclear power plant in the United States. Dominion's application seeks approval to build and operate one General Electric-Hitachi Economic Simplified Boiling Water Reactor (ESBWR) at its

193

Nuclear Science  

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

Science Science and Engineering Education Sourcebook 2013 American Nuclear Society US Department of Energy Nuclear Science & Engineering Education Sourcebook 2013 North American Edition American Nuclear Society Education, Training, and Workforce Division US Department of Energy Office of Nuclear Energy Editor and Founder John Gilligan Professor of Nuclear Engineering North Carolina State University Version 5.13 Welcome to the 2013 Edition of the Nuclear Science and Engineering Education (NS&EE) Sourcebook. We have evolved and improved! The core mission of the Sourcebook has not changed, however. Our purpose is to facilitate interaction among faculty, students, industry, and government agencies to accomplish nuclear research, teaching and service activities. Since 1986 we have compiled critical information on nuclear

194

Nuclear reactions  

Science Journals Connector (OSTI)

Much reference has been made in the last chapter to nuclear energy levels and their various properties (e.g ... ways of doing this — the use of nuclear reactions, and studies of how excited nuclei...

R. J. Blin-Stoyle FRS

1991-01-01T23:59:59.000Z

195

nuclear security  

National Nuclear Security Administration (NNSA)

3%2A en Shaping the future of nuclear detection http:nnsa.energy.govblogshaping-future-nuclear-detection

196

Nuclear Ukraine  

Science Journals Connector (OSTI)

... SIR - Your article (Nature 365, 599; 1993) on the US-Ukraine stalemate over nuclear weapons prompts the following remarks. The United States made a mistake ... nuclear weapons prompts the following remarks. The United States made a mistake in not recognizing Ukraine as a legitimate successor state to the Soviet nuclear arsenal and is still insisting that ...

Arno Arrak

1994-01-13T23:59:59.000Z

197

Nuclear Engineer (Nuclear Safety Specialist)  

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

A successful candidate of this position will serve as a Nuclear Engineer (Nuclear Safety Specialist) responsible for day-to-day technical monitoring, and evaluation of aspects of authorization...

198

Limit cycle analysis of nuclear coupled density-wave oscillations  

SciTech Connect

Recent tests at commercial boiling water reactors (BWRs) have demonstrated the existence of limit cycles for nuclear coupled density-wave oscillations (NCDWOs) at off-normal conditions. This paper presents the application of a simplified nonlinear BWR core model to determine the potential magnitude and limiting mechanisms of severe NCDWOs, and an approximate determination of the limit cycle using singular perturbation analysis. In this model, the point kinetics equation with infinite-delayed approximation and linear reactivity feedback to both fuel temperature and coolant density is used. This model correctly predicts the magnitude of the Vermont Yankee power oscillations.

Ward, M.E.; Lee, J.C.

1986-01-01T23:59:59.000Z

199

Nuclear Deterrence  

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

Nuclear Deterrence Nuclear Deterrence Nuclear Deterrence LANL's mission is to develop and apply science and technology to ensure the safety, security, and effectiveness of the U.S. nuclear deterrent; reduce global threats; and solve other emerging national security and energy challenges. April 12, 2012 A B-2 Spirit bomber refuels from a KC-135 Stratotanker A B-2 Spirit bomber refuels from a KC-135 Stratotanker. Contact Operator Los Alamos National Laboratory (505) 667-5061 Charlie McMillan, Director: "For the last 70 years there has not been a world war, and I have to think that our strong deterrent has something to do with that fact." Mission nuclear weapons Charlie McMillan, Director of Los Alamos National Laboratory 1:06 Director McMillan on nuclear deterrence While the role and prominence of nuclear weapons in U.S. security policy

200

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

SciTech Connect

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

Note: This page contains sample records for the topic "boiling nuclear superheater" 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

Study of Heat Transfer in Non-boiling Two-phase Gas-liquid Flow in Pipes for Horizontal, Slightly Inclined, and Vertical Orientations.  

E-Print Network (OSTI)

??The main objective of this research is to establish a fundamental understanding of heat transfer in non-boiling two-phase pipe flow. The key processes that govern… (more)

Tang, Clement Chih-Wei

2011-01-01T23:59:59.000Z

202

Numerical Simulations of Bubble Dynamics and Heat Transfer in Pool Boiling--Including the Effects of Conjugate Conduction, Level of Gravity, and Noncondensable Gas Dissolved in the Liquid  

E-Print Network (OSTI)

boiling. ” Journal of heat transfer, 124(4), 4. Basu, N. ,development. ” Journal of Heat Transfer, 127(2), 5. CareyA Review. ” Journal of Heat Transfer, 135(6), 061502. 10.

Aktinol, Eduardo

2014-01-01T23:59:59.000Z

203

Numerical Simulations of Bubble Dynamics and Heat Transfer in Pool Boiling--Including the Effects of Conjugate Conduction, Level of Gravity, and Noncondensable Gas Dissolved in the Liquid  

E-Print Network (OSTI)

flow boiling. ” Journal of heat transfer, 124(4), 4. Basu,Dhir, V. K. (2005). “Wall heat flux partitioning duringdevelopment. ” Journal of Heat Transfer, 127(2), 5. Carey

Aktinol, Eduardo

2014-01-01T23:59:59.000Z

204

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

SciTech Connect

Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWe.

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

1980-06-01T23:59:59.000Z

205

Nonlinear dynamics and stability of boiling water reactors: qualitative and quantitative analyses  

SciTech Connect

A phenomenological model has been developed to simulate the qualitative behavior of boiling water reactors (BWRs) in the nonlinear regime under deterministic and stochastic excitations. After the linear stability threshold is crossed, limit cycle oscillations appear due to interactions between two unstable equilibrium points and the phase-space trajectories. This limit cycle becomes unstable when the feedback gain exceeds a certain critical value. Subsequent limit cycle instabilities produce a cascade of period-doubling bifurcations that leads to a periodic pulsed behavior. Under stochastic excitations, BWRs exhibit a single characteristic resonance, at approx.0.5 Hz, in the linear regime. By contrast, this work shows that harmonics of this characteristic frequency appear in the nonlinear regime. Furthermore, this work also demonstrates that amplitudes of the limit cycle oscillations do not depend on the variance of the stochastic excitation and remain bounded at all times. A physical model of nonlinear BWR dynamics has also been developed and employed to calculate the amplitude of limit cycle oscillations and their effects on fuel integrity over a wide range of operating conditions in the Vermont Yankee reactor. These calculations have confirmed that, beyond the threshold for linear stability, the reactor's state variable undergo limit cycle oscillations.

March-Leuba, J.; Cacuci, D.G.; Perez, R.B.

1985-11-01T23:59:59.000Z

206

Retrofit design of a boil-off gas handling process in liquefied natural gas receiving terminals  

Science Journals Connector (OSTI)

Generation of Boil-off gas (BOG) in liquefied natural gas (LNG) receiving terminals considerably affects operating costs and the safety of the facility. For the above reasons, a proper BOG handling process is a major determinant in the design of a LNG receiving terminal. This study proposes the concept of a retrofit design for a BOG the handling process using a fundamental analysis. A base design was determined for a minimum send-out case in which the BOG handling becomes the most difficult. In the proposed design, the cryogenic energy of the LNG stream is used to cool other streams inside the process. It leads to a reduction in the operating costs of the compressors in the BOG handling process. Design variables of the retrofit design were optimized with non-linear programming to maximize profitability. Optimization results were compared with the base design to show the effect of the proposed design. The proposed design provides a 22.7% energy saving ratio and a 0.176 year payback period.

Chansaem Park; Kiwook Song; Sangho Lee; Youngsub Lim; Chonghun Han

2012-01-01T23:59:59.000Z

207

EHD-based load controllers for \\{R134a\\} convective boiling heat exchangers  

Science Journals Connector (OSTI)

Abstract The objective of this study is to investigate the application of high voltage DC waveforms as a mechanism of load control for convective boiling systems. Electrohydrodynamics (EHD) induces flow pattern redistribution, which directly influences the system performance. EHD can provide a low power (<1 W), fast responding method of enhancing two phase flow systems such as heat exchangers. This study compares the use of EHD for load control with control via changing the refrigerant side flow rate in terms of required power, response time and effect on flow parameters. It was found that EHD responds faster and requires less power when a constant exit condition is required for the heat exchanger. Two EHD based controllers; PI controller and a Smith predictor were established using LabVIEW and compared in terms of their response time and regulation behaviour subject to dynamic loading. The Smith predictor resulted in less overshoot and approximately a 50% reduction in settling time in response to dynamic loading. It has been shown that this EHD based controller can regulate subject to ±25% deviation in load from the designed steady state load condition.

S. Nangle-Smith; J.S. Cotton

2014-01-01T23:59:59.000Z

208

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

SciTech Connect

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

209

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

SciTech Connect

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

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

1984-07-06T23:59:59.000Z

210

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

SciTech Connect

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

211

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

SciTech Connect

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

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

1997-03-01T23:59:59.000Z

212

A Safer Nuclear Enterprise  

Science Journals Connector (OSTI)

...2012 at the Nuclear Security...leadership in nuclear enterprise...multinational assessment of emerging risks and consequences...to assess nuclear risks in...or nuclear terrorism. States...and nuclear power. Since 1945...nuclear power plant can mean...

Sidney D. Drell; George P. Shultz; Steven P. Andreasen

2012-06-08T23:59:59.000Z

213

Nuclear astrophysics  

SciTech Connect

The problem of core-collapse supernovae is used to illustrate the many connections between nuclear astrophysics and the problems nuclear physicists study in terrestrial laboratories. Efforts to better understand the collapse and mantle ejection are also motivated by a variety of interdisciplinary issues in nuclear, particle, and astrophysics, including galactic chemical evolution, neutrino masses and mixing, and stellar cooling by the emission of new particles. The current status of theory and observations is summarized.

Haxton, W.C.

1992-12-31T23:59:59.000Z

214

Nuclear astrophysics  

SciTech Connect

The problem of core-collapse supernovae is used to illustrate the many connections between nuclear astrophysics and the problems nuclear physicists study in terrestrial laboratories. Efforts to better understand the collapse and mantle ejection are also motivated by a variety of interdisciplinary issues in nuclear, particle, and astrophysics, including galactic chemical evolution, neutrino masses and mixing, and stellar cooling by the emission of new particles. The current status of theory and observations is summarized.

Haxton, W.C.

1992-01-01T23:59:59.000Z

215

Nuclear Counterterrorism  

Directives, Delegations, and Requirements

The Order defines requirements for the protection of sensitive improvised nuclear device information and provides a framework to support DOE activities related to nuclear counterterrorism. (A supplemental DOE Manual, Control of and Access to Improvised Nuclear Device Information, provides requirements and procedures for protecting Sigma 20 information.) Appendices A and B are Official Use Only. Point of contact is Adam Boyd (NA-82), 202-586-0010. Cancels DOE O 457.1 and DOE M 457.1-1.

2013-08-26T23:59:59.000Z

216

Nuclear Power  

Science Journals Connector (OSTI)

Nuclear Power ... THIS WEEK’S issue contains six letters on nuclear power, a representative sample of the letters C&EN received in response to the editorial, “Resist Hysteria,” I wrote shortly after the earthquake and tsunami in Japan devastated the Fukushima Daiichi Nuclear Power Station (C&EN, March 21, page 5). ... Four of the six letters take sharp issue with the primary point I made in the editorial, which was that, despite the severity of the situation in Japan, nuclear power remains an essential component of our overall energy mix for the near to mid-term because it will help us avert the worst impacts of global climate disruption. ...

RUDY M. BAUM

2011-05-09T23:59:59.000Z

217

NUCLEAR STUDIES  

Science Journals Connector (OSTI)

Japanese nuclear power plant crisis sparks examination of U.S. REACTORS ... Calls are particularly zeroing in on reactors similar in location and design to those in Japan. ...

JEFF JOHNSON

2011-04-04T23:59:59.000Z

218

Nuclear radiation electronic gear  

Science Journals Connector (OSTI)

Nuclear radiation electronic gear ... Examines the line of nuclear radiation instrumentation offered by Nuclear-Chicago Corporation and Victoreen Instrument Company. ... Nuclear / Radiochemistry ...

S. Z. Lewin

1961-01-01T23:59:59.000Z

219

Nuclear Weapons Journal  

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

Nuclear Weapons Journal Nuclear Weapons Journal x The Nuclear Weapons Journal ceased publication after Issue 2, 2009. Below are Nuclear Weapons Journal archived issues. Issue 2,...

220

Nuclear Forces and Nuclear Systems  

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

Forces and Nuclear Systems Forces and Nuclear Systems Our goal is to achieve a description of nuclear systems ranging in size from the deuteron to nuclear matter and neutron stars using a single parameterization of the nuclear forces. Our work includes both the construction of two- and three-nucleon potentials and the development of many-body techniques for computing nuclear properties with these interactions. Detailed quantitative, computationally intense studies are essential parts of this work. In the last decade we have constructed several realistic two- and three-nucleon potential models. The NN potential, Argonne v18, has a dominant charge-independent piece plus additional charge-dependent and charge-symmetry-breaking terms, including a complete electromagnetic interaction. It fits 4301 pp and np elastic scattering data with a chi**2

Note: This page contains sample records for the topic "boiling nuclear superheater" 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

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

SciTech Connect

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

222

Film Boiling in Magnetic Field in Liquid Metals with Particular Reference to Fusion Reactor Project  

Science Journals Connector (OSTI)

Efficient heat removal at high temperatures is a key issue for blankets in nuclear fusion applications, for example, the EVOLVE (EVaporation...1], Wong et al. [2]). It utilizes the extremely high heat of vaporiza...

F. J. Arias

2010-04-01T23:59:59.000Z

223

Nuclear Systems Modeling, Simulation & Validation | Nuclear Science...  

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

Research Areas Fuel Cycle Science & Technology Fusion Nuclear Science Isotope Development and Production Nuclear Security Science & Technology Nuclear Systems Modeling, Simulation...

224

Nuclear Materials Management & Safeguards System | National Nuclear...  

National Nuclear Security Administration (NNSA)

System Nuclear Materials Management & Safeguards System NMMSS U.S. Department of Energy U.S. Nuclear Regulatory Commission Nuclear Materials Management & Safeguards...

225

Nuclear options  

Science Journals Connector (OSTI)

... sad if transient commercial expediency led the country to take risks now by adopting nuclear reactor designs from abroad which are in some respects technically less sound than those produced at ... much lower priority. It can be anticipated, however; that although the types of nuclear reactor selected as the best that Britain could build next may be suitable for unit designs ...

G. R. Bainbridge

1974-06-21T23:59:59.000Z

226

Nuclear Reactor Materials and Fuels  

Science Journals Connector (OSTI)

Nuclear reactor materials and fuels can be classified into six categories: Nuclear fuel materials Nuclear clad materials Nuclear coolant materials Nuclear poison materials Nuclear moderator materials

Dr. James S. Tulenko

2012-01-01T23:59:59.000Z

227

A nondiffusive solution method for RETRAN-03 boiling water reactor stability analysis  

SciTech Connect

This paper reports that boiling water reactors (BWRs) are susceptible to thermal-hydraulic instabilities that must be considered in BWR design and operation. Early BWRs were designed to be very stable while operating under natural-circulation conditions. As reactor designs have been modified, stability margins have been reduced, and the potential for stability events, such as occurred at the La Salle and Vermont Yankee plants, has increased. These events and other considerations point to the need for a reliable analysis tool for predicting the dynamic behavior of these events. Transient thermal-hydraulic systems analysis codes have been used to analyze hydrodynamic instabilities, and although the results are often reasonable and exhibit the expected behavior, they are sensitive to changes in node and time-step size and a converged solution cannot be demonstrated by reducing the node and time-step sizes. This sensitivity is due to numerical-diffusion that limits the use of most time domain system analysis codes for BWR stability analyses since it directly affects the decay (or growth) ratio compared for stability events. A conservation equation transport model using the method of characteristics has been developed for use with the RETRAN-03 mixture energy and vapor continuity equations. The model eliminates numerical diffusion in the RETRAN solution. The development and validation of a conservation equation transport model for the RETRAN-03 time domain thermal-hydraulic analysis code that extends the range of application to simulating the dynamic behavior of stability events are presented. RETRAN-03 analyses are presented that compare simulations of hydrodynamic instability events with data.

Paulsen, M.P.; Shatford, J.G.; Westacott, J.L. (Computer Simulation and Analysis, Inc., Idaho Falls, ID (United States)); Agee, L.J. (Electric Power Research Inst., Palo Alto, CA (United States))

1992-11-01T23:59:59.000Z

228

A pilot study for errors of commission for a boiling water reactor using the CESA method  

Science Journals Connector (OSTI)

Probabilistic Safety Assessment (PSA) typically focuses on the errors leading to the non-performance of required actions (Errors of Omission, EOOs). On the other hand, Errors Of Commission (EOCs) refer to inappropriate, undesired actions that aggravate an accident scenario. The challenges to their treatment in PSA relate to both their identification (which error events should be included in the PSA) and to the quantification of their probabilities. This paper presents the results from a plant-specific study to identify potential EOC vulnerabilities and quantify their risk significance. The study addresses a Boiling Water Reactor (BWR) in Switzerland. It is one of the first EOC analyses ever made for BWRs. The Commission Error Search and Assessment (CESA) method was used to identify EOC scenarios. The EOC probabilities were estimated using the elicitation approach developed as part of the ATHEANA method (A Technique for Human Event Analysis), with input from interviews with plant personnel (with oral as well as written questions). The basis for the quantification was a qualitative analysis of the scenario, the operator response and its procedural basis, and of the opportunities for the EOC and its recovery. The results suggest that the contribution to risk of the most important \\{EOCs\\} is comparable to that of the most important errors of omission, i.e. the required actions typically treated in a PSA; thus, they highlight the significance of \\{EOCs\\} in the overall risk profile of the plant. This study demonstrates the feasibility of a systematic treatment of \\{EOCs\\} for large-scale applications and contributes to understanding the importance of \\{EOCs\\} in the plant risk profile.

L. Podofillini; V.N. Dang; O. Nusbaumer; D. Dres

2013-01-01T23:59:59.000Z

229

Effect of rolling motion on critical heat flux for subcooled flow boiling in vertical tube  

SciTech Connect

This paper presents defining characteristics of the critical heat flux (CHF) for the boiling of R-134a in vertical tube operation under rolling motion in marine reactor. It is important to predict CHF of marine reactor having the rolling motion in order to increase the safety of the reactor. Marine Reactor Moving Simulator (MARMS) tests are conducted to measure the critical heat flux using R-134a flowing upward in a uniformly heated vertical tube under rolling motion. MARMS was rotated by motor and mechanical power transmission gear. The CHF tests were performed in a 9.5 mm I.D. test section with heated length of 1 m. Mass fluxes range from 285 to 1300 kg m{sup -2}s{sup -1}, inlet subcooling from 3 to 38 deg. C and outlet pressures from 13 to 24 bar. Amplitudes of rolling range from 15 to 40 degrees and periods from 6 to 12 sec. To convert the test conditions of CHF test using R-134a in water, Katto's fluid-to-fluid modeling was used in present investigation. A CHF correlation is presented which accounts for the effects of pressure, mass flux, inlet subcooling and rolling angle over all conditions tested. Unlike existing transient CHF experiments, CHF ratio of certain mass flux and pressure are different in rolling motion. For the mass fluxes below 500 kg m{sup -2}s{sup -1} at 13, 16 (region of relative low mass flux), CHF ratio was decreased but was increased above that mass flux (region of relative high mass flux). Moreover, CHF tend to enhance in entire mass flux at 24 bar. (authors)

Hwang, J. S.; Park, I. U.; Park, M. Y.; Park, G. C. [Dept. of Energy Systems Engineering, Seoul National Univ., 599 Gwanak-Ro, Gwanak-Gu, Seoul, 151-744 (Korea, Republic of)

2012-07-01T23:59:59.000Z

230

An analytical model of the swirl vane steam separator for boiling water reactors  

SciTech Connect

Currently, no comprehensive mechanistic model for the two-phase flow through a swirl vane steam separator is available. Therefore, an attempt has been made to develop an analytical model, using fundamental fluid mechanics, which is capable of predicting separator performance over a wide range of conditions. The developed model subdivides a typical boiling water reactor swirl vane steam separator into four distinct regions: the standpipe region, the swirl vane region, the transition region, and the free vortex region. In each region, the vapor and liquid components are treated separately and the behavior of individual droplets is determined from the drag force induced by the vapor continuum. The analytical model is used to first determine the vapor velocities throughout the separator. The drag force on the droplets is then determined, and the droplets are tracked through the separator in order to determine the exit position of each droplet. Separator performance can then be determined from this final position in terms of the fraction of droplets removed from the flow stream. In order to assess the validity of this model, the computer code SEPARATOR was developed. Among other capabilities, the code is capable of determining separator performance in terms of carryover, carryunder, and exit quality. However, due to the simplicity of the single-phase fluid treatment of the vapor continuum and the lack of data related to the average droplet diameter for flows of this nature, the results are not of significant quantitative value. The investigation performed does, however, suggest that the developed methodology, upon refinement of the single-phase fluids treatment, will yield quantitatively accurate results for nearly all separator operating conditions of interest.

Betts, C.M.; Galvin, M.R.; Green, J.R.; Guymon, V.M.; Slater, S.M.; Klein, A.C. (Oregon State Univ., Corvallis, OR (United States). Dept. of Nuclear Engineering)

1994-03-01T23:59:59.000Z

231

Nuclear fuel elements made from nanophase materials  

DOE Patents (OSTI)

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

Heubeck, N.B.

1998-09-08T23:59:59.000Z

232

(Nuclear theory). [Research in nuclear physics  

SciTech Connect

This report discusses research in nuclear physics. Topics covered in this paper are: symmetry principles; nuclear astrophysics; nuclear structure; quark-gluon plasma; quantum chromodynamics; symmetry breaking; nuclear deformation; and cold fusion. (LSP)

Haxton, W.

1990-01-01T23:59:59.000Z

233

Nuclear Astrophysics  

E-Print Network (OSTI)

Nuclear physics has a long and productive history of application to astrophysics which continues today. Advances in the accuracy and breadth of astrophysical data and theory drive the need for better experimental and theoretical understanding of the underlying nuclear physics. This paper will review some of the scenarios where nuclear physics plays an important role, including Big Bang Nucleosynthesis, neutrino production by our sun, nucleosynthesis in novae, the creation of elements heavier than iron, and neutron stars. Big-bang nucleosynthesis is concerned with the formation of elements with A nuclear physics inputs required are few-nucleon reaction cross sections. The nucleosynthesis of heavier elements involves a variety of proton-, alpha-, neutron-, and photon-induced reactions, coupled with radioactive decay. The advent of radioactive ion beam facilities has opened an important new avenue for studying these processes, as many involve radioactive species. Nuclear physics also plays an important role in neutron stars: both the nuclear equation of state and cooling processes involving neutrino emission play a very important role. Recent developments and also the interplay between nuclear physics and astrophysics will be highlighted.

Carl R. Brune

2005-02-28T23:59:59.000Z

234

nuclear security | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

security | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our...

235

Nuclear Incident Team | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Incident Team | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing...

236

nuclear navy | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

navy | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our...

237

nuclear threat science | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

threat science | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing...

238

Nuclear Operations | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure...

239

Nuclear Radius and Nuclear Forces  

Science Journals Connector (OSTI)

The difference between the radius of the nuclear matter distribution and the nuclear force radius, RN?1.4A13×10-13 cm, for heavy nuclei (A>100) is interpreted as a consequence of the finite range of nuclear forces. Assuming that the nuclear matter distribution coincides with the charge distribution as determined at Stanford (RC=1.12A13×10-13 cm is the distance at which the charge density falls to one half value) we sum up the nuclear interactions of an incident nucleon for various proposed internucleon potentials, V(r). We also evaluate contributions from the spin, charge, and matter polarizations induced in the nuclear distributions by the incident nucleon as a test of the convergence of these calculations. The aim here is to infer some features of nuclear forces which satisfy saturation requirements and at the same time give rise to an appreciable nuclear attraction for an incident nucleon at RN. Analyses of the scattering of neutrons and protons by heavy nuclei suggest a nuclear attraction ?14 Mev at a distance RN.These considerations are primarily sensitive to the long range behavior of the direct, central part of V(r). The key point which emerges from them is that the nuclear forces must contain long range (~ meson Compton wavelength) direct, central attractions which will be felt by an incident nucleon at RN before the shorter range repulsions (hard cores, many-body forces, or exchange interactions), which are responsible for saturation, become effective. Such interactions can be constructed phenomenologically, but are not found in recent meson-theoretically deduced potentials.

S. D. Drell

1955-10-01T23:59:59.000Z

240

Nuclear condensation  

Science Journals Connector (OSTI)

This work draws an analogy between a heated nucleus breaking up into clusters and a liquid undergoing a phase transition to a gas in which droplets appear. The critical temperature and density in the nucleus are investigated using a Skyrme effective interaction and finite temperature Hartree-Fock theory. The energy and pressure as a function of density are calculated. The effects of compressibility, effective mass, and binding energy per particle on the critical temperature and critical density of nuclear systems is developed. In some cases, analytic expressions for these quantities can be obtained.NUCLEAR REACTIONS Phase transitions in hot nuclear matter.

H. Jaqaman; A. Z. Mekjian; L. Zamick

1983-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "boiling nuclear superheater" 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

Nuclear War  

SciTech Connect

Several chapters in Last Aid warrant the attention of the medical profession. What is known and not known about acute biologic effects following a nuclear explosion is described. The social, physical, and environmental impact of nuclear war on urban population centers is described. How nuclear weapons could affect the composition of the ozone layer and the effects this could have on human survival, including possible interruption of the aquatic ecosystem to produce single-cell organisms for the food cycle, especially seafood is noted.

MacLeod, G.K.

1983-01-01T23:59:59.000Z

242

Climate Change, Nuclear Power and Nuclear  

E-Print Network (OSTI)

Climate Change, Nuclear Power and Nuclear Proliferation: Magnitude Matters Rob Goldston MIT IAP biomass wind hydro coal CCS coal nat gas CCS nat gas nuclear Gen IV nuclear Gen III nuclear Gen II 5-1 Electricity Generation: CCS and Nuclear Power Technology Options Available Global Electricity Generation WRE

243

Method and apparatus for steam mixing a nuclear fueled electricity generation system  

DOE Patents (OSTI)

A method and apparatus for improving the efficiency and performance of a nuclear electrical generation system that comprises the addition of steam handling equipment to an existing plant that results in a surprising increase in plant performance. More particularly, a gas turbine electrical generation system with heat recovery boiler is installed along with a micro-jet high pressure and a low pressure mixer superheater. Depending upon plant characteristics, the existing moisture separator reheater (MSR) can be either augmented or done away with. The instant invention enables a reduction in T.sub.hot without a derating of the reactor unit, and improves efficiency of the plant's electrical conversion cycle. Coupled with this advantage is a possible extension of the plant's fuel cycle length due to an increased electrical conversion efficiency. The reduction in T.sub.hot further allows for a surprising extension of steam generator life. An additional advantage is the reduction in erosion/corrosion of secondary system components including turbine blades and diaphragms. The gas turbine generator used in the instant invention can also replace or augment existing peak or emergency power needs. Another benefit of the instant invention is the extension of plant life and the reduction of downtime due to refueling.

Tsiklauri, Georgi V. (Richland, WA); Durst, Bruce M. (Kennewick, WA)

1996-01-01T23:59:59.000Z

244

Alcohol-free alkoxide process for containing nuclear waste  

DOE Patents (OSTI)

Disclosed is a method of containing nuclear waste. A composition is first prepared of about 25 to about 80%, calculated as SiO.sub.2, of a partially hydrolyzed silicon compound, up to about 30%, calculated as metal oxide, of a partially hydrolyzed aluminum or calcium compound, about 5 to about 20%, calculated as metal oxide, of a partially hydrolyzed boron or calcium compound, about 3 to about 25%, calculated as metal oxide, of a partially hydrolyzed sodium, potassium or lithium compound, an alcohol in a weight ratio to hydrolyzed alkoxide of about 1.5 to about 3% and sufficient water to remove at least 99% of the alcohol as an azeotrope. The azeotrope is boiled off and up to about 40%, based on solids in the product, of the nuclear waste, is mixed into the composition. The mixture is evaporated to about 25 to about 45% solids and is melted and cooled.

Pope, James M. (Monroeville, PA); Lahoda, Edward J. (Edgewood, PA)

1984-01-01T23:59:59.000Z

245

Nuclear Medicine  

Science Journals Connector (OSTI)

Nuclear medicine is the branch of medicine that is concerned with the use of in the diagnosis, management, and treatment of disease. It usually uses small amounts of radioactive materials or , substances th...

2008-01-01T23:59:59.000Z

246

Nuclear viscosity  

Science Journals Connector (OSTI)

The decay rate of momentum in a nuclear reaction is given by an exact formula expressed in terms of the T matrix. A special case, where a viscosity coefficient can be estimated, is considered.

B. Giraud; J. Le Tourneux; E. Osnes

1975-01-01T23:59:59.000Z

247

Nuclear Waste  

Science Journals Connector (OSTI)

Nuclear waste is radioactive material no longer considered valuable...238U, 235U, and 226Ra (where the latter decays to 222Rn gas by emitting an alpha particle) or formed through fission of fissile radioisotopes ...

Rob P. Rechard

2014-01-01T23:59:59.000Z

248

Nuclear Golf  

E-Print Network (OSTI)

Broadcast Transcript: Pay no attention to that nuclear warhead behind the 18th hole; just shout "Fore!" and drive your Titleist down the fairway. In a development that is bizarre even by North Korean standards, the country ...

Hacker, Randi; Tsutsui, William

2006-12-06T23:59:59.000Z

249

Nuclear Fuels  

Science Journals Connector (OSTI)

The core of a nuclear reactor is composed of a controlled critical configuration of a fissile material, which in strict a sense is the fuel. This fissile material is contained in a matrix, normally a ceramic c...

Rudy J. M. Konings; Thierry Wiss…

2011-01-01T23:59:59.000Z

250

Nuclear Energy!  

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

driver, see the Nuclear Clean Air Energy race car and receive a special clean energy patch on October 21 from 6:30 - 7:30 p.m. Space is limited RSVP by October 4 Hands-on...

251

Nuclear forces  

SciTech Connect

These lectures present an introduction into the theory of nuclear forces. We focus mainly on the modern approach, in which the forces between nucleons emerge from low-energy QCD via chiral effective field theory.

Machleidt, R. [Department of Physics, University of Idaho, Moscow, Idaho 83844 (United States)

2013-06-10T23:59:59.000Z

252

Nucleate pool boiling heat transfer characteristics of TiO{sub 2}-water nanofluids at very low concentrations  

SciTech Connect

A study of nucleate pool boiling heat transfer of TiO{sub 2}-water nanofluids is experimentally conducted. Nanofluids with various concentrations of 0.00005, 0.0001, 0.0005, 0.005, and 0.01 vol.% are employed. Horizontal circular plates made from copper and aluminium with different roughness values of 0.2 and 4 {mu}m are used as heating surfaces. The experiments are performed to explore the effects of nanofluids concentration as well as heating surface material and roughness on nucleate pool boiling characteristics and the heat transfer coefficient under ambient pressure. The results show that based on the copper heated surface which is tested with a concentration of 0.0001 vol.%, higher nucleate pool boiling heat transfer coefficient is obtained when compared with the base fluid. A 15% increase is obtained for the surface roughness of 0.2 {mu}m and a 4% increase is obtained for roughness of 4 {mu}m. For concentrations higher than 0.0001 vol.%, however, the higher the concentration, the lower the heat transfer coefficient. In the case of aluminium heated surface, the corresponding heat transfer coefficients are larger than for the copper surface by around 30% with a roughness of 0.2 {mu}m and around 27% with a roughness of 4 {mu}m. Moreover, the results also indicate that the heat transfer coefficient obtained based on a roughness of 4 {mu}m is higher than that for a roughness of 0.2 {mu}m by around 12% for aluminium and by around 13% for copper. (author)

Suriyawong, Adirek; Wongwises, Somchai [Fluid Mechanics, Thermal Engineering and Multiphase Flow Research Lab. (FUTURE), Department of Mechanical Engineering, King Mongkut's University of Technology Thonburi, Bangmod, Bangkok 10140 (Thailand)

2010-11-15T23:59:59.000Z

253

NYPA, Entergy begin nuclear management services plan  

SciTech Connect

The New York Power Authority (NYPA) and Entergy Corp. of New Orleans, La., announced recently the signing of a memorandum of understanding as a step toward a contract for Entergy to provide management services to NYPA`s two nuclear power plants. The agreement is the first of its kind. NYPA is the nation`s largest state-owned electric utility and supplier of one-quarter of New York`s electricity. Its nuclear plants are Indian Point 3 (IP3) in Buchanan, Westchester County, and James A. FitzPatrick in Scriba, Oswego County. Entergy is a utility holding company and its subsidiary, Entergy Operations Inc., is widely recognized as one of the leading nuclear operators in the United States. {open_quotes}NYPA`s nuclear plants are assets that belong to the people of New York,{close_quotes} said C.D. {open_quotes}Rapp{close_quotes} Rappleyea, NYPA`s chairman and CEO. {open_quotes}Our alliance with Entergy can provide the people of this state with added assurance that these plants will operate with the highest level of safety and efficiency.{close_quotes} FitzPatrick, an 800 MW boiling water reactor, has operated since 1975 and IP3, a 980 MW pressurized water reactor, since 1976. Although both are currently running well, they have had problems in recent years, and IP3 is on the US Nuclear Regulatory Commission`s (NRC) list of plants requiring increased regulatory attention. Entergy operated both types of reactors, has three single-unit sites like NYPA`s and is experienced in operating plants for different utility owners.

NONE

1996-10-01T23:59:59.000Z

254

Nuclear Physics for Nuclear Fusion  

SciTech Connect

The nuclear fusion data for deuteron-triton resonance near 100 keV are found to be consistent with the selective resonant tunneling model. The feature of this selective resonant tunneling is the selectivity. It selects not only the energy level, but also the damping rate (nuclear reaction rate). When the Coulomb barrier is thin and low, the resonance selects the fast reaction channel; however, when the Coulomb barrier is thick and high, the resonance selects the slow reaction channel. This mechanism might open an approach toward fusion energy with no strong nuclear radiation.

Li Xingzhong [Tsinghua University (China)

2002-01-15T23:59:59.000Z

255

Exergy analysis of second-generation micro heat sinks under single-phase and flow boiling conditions  

Science Journals Connector (OSTI)

A parametric study of exergy efficiency was conducted for five micro pin fin heat sinks of different spacing and shapes. Of the four micro pin fin heat sinks tested under single-phase flow conditions, those with better heat transfer performance yielded superior exergy efficiencies. The use of R-123 in place of water as working fluid was found to enhance exergetic performance at the expense of reduced heat transfer performance. The exergy analysis was also extended to the flow boiling of R-123 in an additional hydrofoil-based micro pin fin heat sink. It was found that exergy efficiencies decreased with mass velocity.

Ali Kosar

2010-01-01T23:59:59.000Z

256

Countering Nuclear Terrorism | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Countering Nuclear Terrorism | National Nuclear Security Administration Countering Nuclear Terrorism | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog The National Nuclear Security Administration Countering Nuclear Terrorism Home > Our Mission > Countering Nuclear Terrorism Countering Nuclear Terrorism NNSA provides expertise, practical tools, and technically informed policy

257

A general heat transfer correlation for non-boiling gasliquid flow with different flow patterns  

E-Print Network (OSTI)

, such as oil wells and pipelines, solar collectors, chemical reactors, and nuclear reactors, and its in horizontal pipes Jae-yong Kim, Afshin J. Ghajar * School of Mechanical and Aerospace Engineering, Oklahoma patterns in horizontal pipes is proposed. In order to overcome the effect of flow pattern on heat transfer

Ghajar, Afshin J.

258

Nuclear Induction  

Science Journals Connector (OSTI)

The magnetic moments of nuclei in normal matter will result in a nuclear paramagnetic polarization upon establishment of equilibrium in a constant magnetic field. It is shown that a radiofrequency field at right angles to the constant field causes a forced precession of the total polarization around the constant field with decreasing latitude as the Larmor frequency approaches adiabatically the frequency of the r-f field. Thus there results a component of the nuclear polarization at right angles to both the constant and the r-f field and it is shown that under normal laboratory conditions this component can induce observable voltages. In Section 3 we discuss this nuclear induction, considering the effect of external fields only, while in Section 4 those modifications are described which originate from internal fields and finite relaxation times.

F. Bloch

1946-10-01T23:59:59.000Z

259

Collaborating Organizations - Nuclear Data Program, Nuclear Engineering  

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

Collaborating Organizations Collaborating Organizations Nuclear Data Program Overview Current Projects & Recent Activities Collaborating Organizations Publications Nuclear Data Measurements (NDM) Reports Experimental Nuclear Data Resources Contact ND Program Related Resources Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Data Program Collaborating Organizations Bookmark and Share National Nuclear Data Center, Brookhaven National Laboratory, Upton, New York. International Nuclear Structure and Decay Data Network, coordinated by IAEA, Vienna, Austria Heavy-Ion Nuclear Physics Group, Physics Division, Argonne National Laboratory, Argonne, Illinois. Nuclear Spectroscopy Group, Department of Nuclear Physics,

260

Nuclear Data Program - Nuclear Engineering Division (Argonne)  

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

Data Program Data Program Nuclear Data Program Overview Current Projects & Recent Activities Collaborating Organizations Publications Nuclear Data Measurements (NDM) Reports Experimental Nuclear Data Resources Contact ND Program Related Resources Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Data Program We contribute to the development of comprehensive nuclear reactions and nuclear structure databases, including nuclear data measurement, analysis, modeling and evaluation methodologies, that are implemented in basic science research and advanced nuclear technologies. Bookmark and Share Recent Events Nuclear Structure 2012 Conference Argonne National Laboratory hosted the

Note: This page contains sample records for the topic "boiling nuclear superheater" 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

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

E-Print Network (OSTI)

of the macroscopic cross sections using General Electric fuel bundle design standard parameters and the powerful code CASMO-3 which is multigroup two-dimensional transport theory code for burnup calculations on BWR or PWR assemblies. This strategy results in a one... is a multigroup two-dimensional code for burnup and nuclear parameter calculation on BWR and PWR assemblies. It handles a geometry consisting of cylindrical fuel rods of varying composition in a square pitch anay with allowance for fuel rods loaded...

Cuevas Vivas, Gabriel Francisco

2012-06-07T23:59:59.000Z

262

Nuclear Science & Technology  

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

Nuclear Science & Technology Nuclear Science & Technology Nuclear Science & Technology1354608000000Nuclear Science & TechnologySome of these resources are LANL-only and will require Remote Access. /No/ Nuclear Science & Technology Some of these resources are LANL-only and will require Remote Access. Key Resources Databases Organizations Journals Key Resources International Atomic Energy Agency IAEA scientific and technical publications cover areas of nuclear power, radiation therapy, nuclear security, nuclear law, and emergency repose. Search under Publications/Books and Reports for scientific books, standards, technical guides and reports National Nuclear Data Center Nuclear physics data for basic nuclear research and for applied nuclear technologies, operated by Brookhaven.

263

NUCLEAR PROXIMITY FORCES  

E-Print Network (OSTI)

One might summarize of nuclear potential energy has beendegree of freedom) for the nuclear interaction between anyUniversity of California. Nuclear Proximity Forces 'I< at

Randrup, J.

2011-01-01T23:59:59.000Z

264

Nuclear Nonproliferation Programs | ORNL  

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

Nuclear Nonproliferation Programs SHARE Nuclear Nonproliferation Programs image Oak Ridge National Laboratory covers the entire spectrum of nuclear nonproliferation work, from...

265

Nuclear Data | More Science | ORNL  

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

Nuclear Data SHARE Nuclear Data Nuclear Data ORNL is a recognized, international leader in nuclear data research and development (R&D) to support nuclear applications analyses. For...

266

Nuclear Facilities | Department of Energy  

Energy Savers (EERE)

Nuclear Facilities Nuclear Facilities Nuclear Facilities Locator Map Numerical map data points indicate two or more nuclear facilities in the same geographic location. Nuclear...

267

Nuclear “waffles”  

Science Journals Connector (OSTI)

Background: The dense neutron-rich matter found in supernovae and inside neutron stars is expected to form complex nonuniform phases, often referred to as nuclear pasta. The pasta shapes depend on density, temperature and proton fraction and determine many transport properties in supernovae and neutron star crusts.

A. S. Schneider; D. K. Berry; C. M. Briggs; M. E. Caplan; C. J. Horowitz

2014-11-24T23:59:59.000Z

268

Nuclear cheap?  

Science Journals Connector (OSTI)

... account of the fact that if there had been no nuclear contribution the additional fossil fuel supplies would have had to come from expanded output at the marginal and most expensive ... a perfectly proper accountancy basis, including allowance for costs yet to be incurred, the price we would be paying for electricity would be higher now had fossil stations been preferred ...

P.M.S. JONES

1980-12-18T23:59:59.000Z

269

Nuclear electricity  

Science Journals Connector (OSTI)

... p.344-6) and referred to in my letter of 23 October. The retail price index (RPI) has been used to correct for inflation and a uniform interest rate ... as given by historic costs, and if a previously unconsidered effect of inflation on nuclear fuel costs is included, the margin becomes 34 per cent above that for coal.

J.W. JEFFERY

1981-08-27T23:59:59.000Z

270

Neutrino nuclear response and photo nuclear reaction  

E-Print Network (OSTI)

Photo nuclear reactions are shown to be used for studying neutrino/weak nuclear responses involved in astro-neutrino nuclear interactions and double beta decays. Charged current weak responses for ground and excited states are studied by using photo nuclear reactions through isobaric analog states of those states, while neutral current weak responses for excited states are studied by using photo nuclear reactions through the excited states. The weak interaction strengths are studied by measuring the cross sections of the photo nuclear reactions, and the spin and parity of the state are studied by measuring angular correlations of particles emitted from the photo nuclear reactions. Medium-energy polarized photons obtained from laser photons scattered off GeV electrons are very useful. Nuclear responses studied by photo nuclear reactions are used to evaluate neutrino/weak nuclear responses, i.e. nuclear beta and double beta matrix elements and neutrino nuclear interactions, and to verify theoretical calculations for them.

H. Ejiri; A. I. Titov; M. Boswell; A. Young

2013-11-10T23:59:59.000Z

271

Nuclear Medicine CT Angiography  

E-Print Network (OSTI)

Nuclear Medicine CT Angiography Stress Testing Rotation The Nuclear Medicine/CT angiography. Understand the indications for exercise treadmill testing and specific nuclear cardiology tests, safe use Level 2 proficiency in performing and interpreting cardiac nuclear imaging tests. Progression

Ford, James

272

Nuclear Forensics | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Forensics | National Nuclear Security Administration Forensics | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Nuclear Forensics Home > About Us > Our Programs > Emergency Response > Responding to Emergencies > Nuclear Forensics Nuclear Forensics Forensics Operations The National Technical Nuclear Forensics (NTNF) program is a Homeland Security Council and National Security

273

Nuclear structure and nuclear reactions | Argonne Leadership...  

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

the production Automatic Dynamic Load Balancing (ADLB) library on the BGP. Steve Pieper, Argonne National Laboratory Nuclear structure and nuclear reactions PI Name: James Vary PI...

274

Audit Report National Nuclear Security Administration Nuclear...  

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

National Nuclear Security Administration Nuclear Weapons Systems Configuration Management DOEIG-0902 March 2014 U.S. Department of Energy Office of Inspector General Office of...

275

Nuclear Resonance Fluorescence for Nuclear Materials Assay  

E-Print Network (OSTI)

to learn MCNPX and nuclear safeguards, Bill B. , Steve K. ,Introduction 1.1 Nuclear Safeguards . . . . . . . . . . . .Programme to IAEA Safeguards. STUK-YTO-TR 170. Helsinki

Quiter, Brian Joseph

2010-01-01T23:59:59.000Z

276

Civilian Nuclear Programs  

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

Civilian Nuclear Programs Civilian Nuclear Programs Civilian Nuclear Programs Los Alamos is committed to using its advanced nuclear expertise and unique facilities to meet the civilian nuclear national security demands of the future. CONTACT US Program Director Bruce Robinson (505) 667-1910 Email Los Alamos partners extensively with other laboratories, universities, industry, and the international nuclear community to address real-world technical challenges The Civilian Nuclear Programs Office is the focal point for nuclear energy research and development and next-generation repository science at Los Alamos National Laboratory. The Civilian Nuclear Programs Office manages projects funded by the Department of Energy's offices of Nuclear Energy Environmental Management Nuclear Regulatory Commission

277

Theory of nuclear reactions  

SciTech Connect

The book presents a theory of nuclear reaction. An account is given of the nonrelativistic nuclear reaction theory. The R - matrix description of nuclear reactions is considered and the dispersion method is formulated. Mechanisms of nuclear reactions and their relationship are studied in detail. Attention is paid to nuclear reactions involving the compound nuclear formation and to direct nuclear processes. The optical model the diffraction approach and high - energy diffraction nuclear processes involving composite particles are discussed.

Sitenko, A.G.

1990-01-01T23:59:59.000Z

278

An Evaluation of Superheat-Based Refrigerant Charge Diagnostics for  

E-Print Network (OSTI)

of residential cooling systems with fixed orifice metering devices, there has been little research to quantify temperature with a high degree of accuracy. Measurement of the wet bulb temperature in the return plenum showed a similar pattern for EER degradation. Laboratory test data indicate that some short-tube-orifice

279

Superheater Tube Corrosion in Wood Gasifier Ash Deposits  

SciTech Connect

The upper operating temperature of tubes in heat exchangers/steam generators is strongly influenced by the degradation that can occur because of the reaction of the exchanger/generator tubing with the deposits that accumulate on the surface of the tubes. In fact, severe corrosion has been observed in some biomass fired systems, particularly with elevated potassium and chlorine concentrations in the deposits. Wood gasifiers have recently been and are currently being constructed at several sites in North America. In these systems, the syngas is burned to produce steam and the performance of the heat exchanger tubes under ash deposits is of great concern. As temperatures of the heat exchangers are increased in an effort to increase their operating efficiency, the performance of the tubes is of greater interest. The corrosion behavior of alloy steel tubes as a function of temperature has been investigated by exposing samples of selected alloys to ash collected from the steam generator fired by syngas produced in wood gasifiers. This study compares corrosion rates from laboratory exposures of synthesis gas and ash at 500 C and 600 C. This study investigated the material performance of four ferritic steels and one austenitic steel exposed to conditions expected on the fireside of a wood gasifier. The purpose of this study was to identify an effective method for determining material performance for samples exposed to both the process gas and the fly ash that is typically observed within the steam generator for times up to 1000 hours. Mass changes were measured for all of the samples, but this information can be misleading concerning material performance due to the difficulty in sufficiently cleaning the samples after exposure in the ash. Therefore, small cross sections of the samples were collected and imaged using optical microscopy. Oxide thicknesses were measured along with metal losses. The metal loss information provides a clear indication of material performance. The metal loss rates for the ferritic steels at 500 C were almost half of those observed at 600 C and the rates decreased with increasing exposure time. It was also reported that the metal loss rates generally decrease with increasing chromium concentration.

Bestor, Michael A [ORNL] [ORNL; Keiser, James R [ORNL] [ORNL; Meisner, Roberta A [University of Tennessee, Knoxville (UTK) & Oak Ridge National Laboratory (ORNL)] [University of Tennessee, Knoxville (UTK) & Oak Ridge National Laboratory (ORNL)

2011-01-01T23:59:59.000Z

280

Review and evaluation of the RELAP5YA computer code and the Vermont Yankee LOCA (Loss-of-Coolant Accident) licensing analysis model for use in small and large break BWR (Boiling Water Reactor) LOCAS  

SciTech Connect

A review has been completed of the RELAP5YA computer code to determine its acceptability for performing licensing analyses. The review was limited to Boiling Water Reactor (BWR) reactor applications. In addition, a Loss-Of-Coolant Accident (LOCA) licensing analysis method, using the RELAP5YA computer code, has been reviewed. This method is applicable to the Vermont Yankee Nuclear Power Station to perform full break spectra LOCA and fuel cycle independent analyses. The review of the RELAP5YA code consisted of an evaluation of all Yankee Atomic Electric Company (YAEC) incorporated modifications to the RELAP5/MOD1 Cycle 18 computer code from which the licensing version of the code originated. Qualifying separate and integral effects assessment calculations were reviewed to evaluate the validity and proper implementation of the various added models. The LOCA licensing method was assessed by reviewing two RELAP5YA system input models and evaluating several small and large break qualifying transient calculations. A review of the RELAP5YA code modifications and their assessments, as well as the submitted LOCA licensing method, is given and the results of the review are provided.

Jones, J.L.

1987-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "boiling nuclear superheater" 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

Stability analysis of NbTi-Ta-based high field conductor cooled by pool boiling below 4 K  

SciTech Connect

Stability analysis has been performed for cabled NbTi-Ta-based superconductors intended for the high field (12 T) toroidal field coils for a large scale tokamak device such as ETF. Ternary NbTi-Ta was selected as the superconductor because of its superior critical current density at high field as compared to the binary alloy NbTi. The operating temperature was chosen to be 2.5 K or below to optimize the performance of the superconductor. A cabled conductor was selected to minimize the pulsed field losses. The conductor is cooled by pool boiling in a subcooled (approx. 2.5 K, 0.25 atm) bath, or in a superfluid helium (He-II) bath (approx. 1.8 K, 0.02 atm). The analysis was based on numerically simulating the evolution of a normal zone in the conductor. Appropriate superconductor properties and heat transfer characteristics were utilized in the simulation.

Chen, W.Y.; Alcorn, J.S.; Hsu, Y.H.; Purcell, J.R.

1980-09-01T23:59:59.000Z

282

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

SciTech Connect

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

283

Nuclear photonics  

SciTech Connect

With the planned new {gamma}-beam facilities like MEGa-ray at LLNL (USA) or ELI-NP at Bucharest (Romania) with 10{sup 13}{gamma}/s and a band width of {Delta}E{gamma}/E{gamma} Almost-Equal-To 10{sup -3}, a new era of {gamma} beams with energies up to 20MeV comes into operation, compared to the present world-leading HI{gamma}S facility at Duke University (USA) with 10{sup 8}{gamma}/s and {Delta}E{gamma}/E{gamma} Almost-Equal-To 3 Dot-Operator 10{sup -2}. In the long run even a seeded quantum FEL for {gamma} beams may become possible, with much higher brilliance and spectral flux. At the same time new exciting possibilities open up for focused {gamma} beams. Here we describe a new experiment at the {gamma} beam of the ILL reactor (Grenoble, France), where we observed for the first time that the index of refraction for {gamma} beams is determined by virtual pair creation. Using a combination of refractive and reflective optics, efficient monochromators for {gamma} beams are being developed. Thus, we have to optimize the total system: the {gamma}-beam facility, the {gamma}-beam optics and {gamma} detectors. We can trade {gamma} intensity for band width, going down to {Delta}E{gamma}/E{gamma} Almost-Equal-To 10{sup -6} and address individual nuclear levels. The term 'nuclear photonics' stresses the importance of nuclear applications. We can address with {gamma}-beams individual nuclear isotopes and not just elements like with X-ray beams. Compared to X rays, {gamma} beams can penetrate much deeper into big samples like radioactive waste barrels, motors or batteries. We can perform tomography and microscopy studies by focusing down to {mu}m resolution using Nuclear Resonance Fluorescence (NRF) for detection with eV resolution and high spatial resolution at the same time. We discuss the dominating M1 and E1 excitations like the scissors mode, two-phonon quadrupole octupole excitations, pygmy dipole excitations or giant dipole excitations under the new facet of applications. We find many new applications in biomedicine, green energy, radioactive waste management or homeland security. Also more brilliant secondary beams of neutrons and positrons can be produced.

Habs, D.; Guenther, M. M.; Jentschel, M.; Thirolf, P. G. [Ludwig-Maximilians-Universitaet Muenchen, D-85748 Garching (Germany); Max Planck Institut fuer Quantenoptik, D-85748 Garching (Germany); Institut Laue-Langevin, F-38042 Grenoble (Germany); Ludwig-Maximilians-Universitaet Muenchen, D-85748 Garching (Germany)

2012-07-09T23:59:59.000Z

284

Nuclear Hydrogen Initiative  

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

Advanced Nuclear Research Advanced Nuclear Research Office of Nuclear Energy, Science and Technology FY 2003 Programmatic Overview Nuclear Hydrogen Initiative Nuclear Hydrogen Initiative Office of Nuclear Energy, Science and Technology Henderson/2003 Hydrogen Initiative.ppt 2 Nuclear Hydrogen Initiative Nuclear Hydrogen Initiative Program Goal * Demonstrate the economic commercial-scale production of hydrogen using nuclear energy by 2015 Need for Nuclear Hydrogen * Hydrogen offers significant promise for reduced environmental impact of energy use, specifically in the transportation sector * The use of domestic energy sources to produce hydrogen reduces U.S. dependence on foreign oil and enhances national security * Existing hydrogen production methods are either inefficient or produce

285

Nuclear / Radiological Advisory Team | National Nuclear Security  

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

/ Radiological Advisory Team | National Nuclear Security / Radiological Advisory Team | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Nuclear / Radiological Advisory Team Home > About Us > Our Programs > Emergency Response > Responding to Emergencies > Operations > Nuclear / Radiological Advisory Team Nuclear / Radiological Advisory Team

286

Nuclear Nonproliferation Program Offices | National Nuclear Security  

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

Nonproliferation Program Offices | National Nuclear Security Nonproliferation Program Offices | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Nuclear Nonproliferation Program Offices Home > About Us > Our Programs > Nonproliferation > Nuclear Nonproliferation Program Offices Nuclear Nonproliferation Program Offices One of the gravest threats the United States and the international

287

Nuclear Nonproliferation Program Offices | National Nuclear Security  

National Nuclear Security Administration (NNSA)

Nonproliferation Program Offices | National Nuclear Security Nonproliferation Program Offices | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Nuclear Nonproliferation Program Offices Home > About Us > Our Programs > Nonproliferation > Nuclear Nonproliferation Program Offices Nuclear Nonproliferation Program Offices One of the gravest threats the United States and the international

288

Nuclear Systems Technology | Nuclear Science | ORNL  

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

Advanced Fuel Cycle Systems Criticality Safety Irradiation Experiment Development and Execution Robotics & Remote Systems Engineering and Applications Thermal & Hydraulic Experiments & Analysis Used Nuclear Fuel Storage, Transportation, and Disposal Reactor Technology Nuclear Science Home | Science & Discovery | Nuclear Science | Research Areas | Nuclear Systems Technology SHARE Nuclear Systems Technology Nuclear Systems Technology Image 2 ORNL has had historic involvement in a broad set of nuclear research areas: irradiated materials and isotopes R&D, fission and fusion reactors development, neutron scattering, fuel enrichment, used fuel recycling and disposal, etc. The skills and knowledge required to succeed in these research areas often cultivated core areas of expertise in which ORNL is

289

Nuclear power, nuclear eapons link argued  

Science Journals Connector (OSTI)

Nuclear power, nuclear eapons link argued ... The problem of the spread of nuclear weapons to nations not currently possessing them—so-called horizontal proliferation—often is linked to development of commercial nuclear power. ... However, John P. Holdren, professor of energy and resources at the University of California, Berkeley, maintains that commercial nuclear power is linked intimately to horizontal proliferation and that the development of alternative energy technologies is crucial to prevent the spread. ...

1982-02-08T23:59:59.000Z

290

The Nuclear Revolution, Relative Gains, and International Nuclear Assistance  

E-Print Network (OSTI)

international nuclear assistance dataset, this article findsinternational nuclear assistance dataset. Table 2 presentsinternational nuclear assistance dataset. Table 3 presents

Kroenig, Matthew

2006-01-01T23:59:59.000Z

291

Collecting and recirculating condensate in a nuclear reactor containment  

DOE Patents (OSTI)

An arrangement passively cools a nuclear reactor in the event of an emergency, condensing and recycling vaporized cooling water. The reactor is surrounded by a containment structure and has a storage tank for cooling liquid, such as water, vented to the containment structure by a port. The storage tank preferably is located inside the containment structure and is thermally coupleable to the reactor, e.g. by a heat exchanger, such that water in the storage tank is boiled off to carry away heat energy. The water is released as a vapor (steam) and condenses on the cooler interior surfaces of the containment structure. The condensed water flows downwardly due to gravity and is collected and routed back to the storage tank. One or more gutters are disposed along the interior wall of the containment structure for collecting the condensate from the wall. Piping is provided for communicating the condensate from the gutters to the storage tank.

Schultz, Terry L. (Murrysville Boro, PA)

1993-01-01T23:59:59.000Z

292

Nuclear Forces  

Science Journals Connector (OSTI)

One-meson-exchange Feynman diagrams are nonrelativistically reduced and unitarized via Schrödinger's equation. Properties of nucleon-nucleon scattering are calculated at incident laboratory energies of 25-310 MeV. Bound-state properties of the deuteron and of nuclear matter are also calculated. Mesons included are the ?, ?, ?, ?, ?, and ?. Very good over-all agreement with the experimental data is obtained. Important features of this "potential" include its momentum dependence, properly treated, and the contribution of the ? "meson," which qualitatively changes the central/tensor force ratio from that of previous phenomenological potentials.

Lester Ingber

1968-10-20T23:59:59.000Z

293

Nuclear Waffles  

E-Print Network (OSTI)

The dense neutron-rich matter found in supernovae and neutron stars is expected to form complex nonuniform phases referred to as nuclear pasta. The pasta shapes depend on density, temperature and proton fraction and determine many transport properties in supernovae and neutron star crusts. We use two recently developed hybrid CPU/GPU codes to perform large scale molecular dynamics (MD) simulations with $51200$ and $409600$ nucleons of nuclear pasta. From the output of the MD simulations we characterize the topology and compute two observables, the radial distribution function $g(r)$ and the structure factor $S(q)$, for systems with proton fractions $Y_p=0.10, 0.20, 0.30$ and $0.40$ at about one third of nuclear saturation density and temperatures near $1.0$ MeV. We observe that the two lowest proton fraction systems simulated, $Y_p=0.10$ and $0.20$, equilibrate quickly and form liquid-like structures. Meanwhile, the two higher proton fraction systems, $Y_p=0.30$ and $0.40$, take a longer time to equilibrate and organize themselves in solid-like periodic structures. Furthermore, the $Y_p=0.40$ system is made up of slabs, lasagna phase, interconnected by defects while the $Y_p=0.30$ systems consist of a stack of perforated plates, the nuclear waffle phase. The periodic configurations observed in our MD simulations for proton fractions $Y_p\\ge0.30$ have important consequences for the structure factors $S(q)$ of protons and neutrons, which relate to many transport properties of supernovae and neutron star crust. A detailed study of the waffle phase and how its structure depends on temperature, size of the simulation and the screening length showed that finite-size effects appear to be under control and, also, that the plates in the waffle phase merge at temperatures slightly above $1.0$ MeV and the holes in the plates form an hexagonal lattice at temperatures slightly lower than $1.0$ MeV.

A. S. Schneider; D. K. Berry; C. M. Briggs; M. E. Caplan; C. J. Horowitz

2014-09-08T23:59:59.000Z

294

Global Nuclear Energy Partnership Fact Sheet - Minimize Nuclear...  

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

Minimize Nuclear Waste Global Nuclear Energy Partnership Fact Sheet - Minimize Nuclear Waste GNEP will increase the efficiency in the management of used nuclear fuel, also known as...

295

Nuclear radiation electronic gear (continued)  

Science Journals Connector (OSTI)

Nuclear radiation electronic gear (continued) ... Examines nuclear instrumentation available from several major U.S. manufacturers. ... Nuclear / Radiochemistry ...

S. Z. Lewin

1961-01-01T23:59:59.000Z

296

Innovations in Nuclear Infrastructure  

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

Innovations in Nuclear Infrastructure Innovations in Nuclear Infrastructure and Education (INIE) Innovations in Nuclear Infrastructure and Education (INIE) Presented to the Nuclear Energy Research Advisory Committee Crystal City, Virginia John Gutteridge Director, University Programs Office of Nuclear Energy, Science and Technology September 30 - October 1, 2002 Office of Nuclear Energy, Science and Technology Gutteridge/Sep-Oct_02 INIE-NERAC.ppt (2) INIE The Stimuli .... INIE The Stimuli .... 6 Declining number of operating university research/training reactors 6 Dwindling student population in nuclear engineering 6 Closing or loss of identity of university nuclear engineering programs 6 Looming shortage of nuclear engineering graduates 6 Threat of additional reactor closures -- Cornell, Michigan, MIT

297

Reconversion of nuclear weapons  

E-Print Network (OSTI)

The nuclear predicament or nuclear option. Synopsis of three lectures : 1- The physical basis of nuclear technology. Physics of fission. Chain reaction in reactors and weapons. Fission fragments. Separration of isotopes. Radiochemistry.2- Nuclear reactors with slow and fast neutrons. Power, size, fuel and waste. Plutonium production. Dose rate, shielding and health hazard. The lessons of Chernobyl3- Nuclear weapons. Types, energy, blast and fallout. Fusion and hydrogen bombs. What to do with nuclear weapons when you cannot use them? Testing. Nonmilittary use. Can we get rid of the nuclear weapon? Nuclear proliferation. Is there a nuclear future?

Kapitza, Sergei P

1993-01-01T23:59:59.000Z

298

Nuclear Security Enterprise | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Enterprise | National Nuclear Security Administration Enterprise | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Nuclear Security Enterprise Home > About Us > Our Programs > Defense Programs > Nuclear Security Enterprise Nuclear Security Enterprise The Nuclear Security Enterprise (NSE) mission is to ensure the Nation sustains a safe, secure, and effective nuclear deterrent through the

299

National Nuclear Data Center  

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

Internal Radiation Dose Evaluated Nuclear (reaction) Data File Experimental nuclear reaction data Sigma Retrieval & Plotting Nuclear structure & decay Data Nuclear Science References Experimental Unevaluated Nuclear Data List Evaluated Nuclear Structure Data File NNDC databases Ground and isomeric states properties Nuclear structure & decay data journal Nuclear reaction model code Tools and Publications US Nuclear Data Program Cross Section Evaluation Working Group Nuclear data networks Basic properties of atomic nuclei Parameters & thermal values Basic properties of atomic nuclei Internal Radiation Dose Evaluated Nuclear (reaction) Data File Experimental nuclear reaction data Sigma Retrieval & Plotting Nuclear structure & decay Data Nuclear Science References Experimental Unevaluated Nuclear Data List Evaluated Nuclear Structure Data File NNDC databases Ground and isomeric states properties Nuclear structure & decay data journal Nuclear reaction model code Tools and Publications US Nuclear Data Program Cross Section Evaluation Working Group Nuclear data networks Basic properties of atomic nuclei Parameters & thermal values Basic properties of atomic nuclei Homepage BNL Home Site Index - Go USDNP and CSEWG November 18-22! USNDP CSEWG Agenda Thanks for attending! EXFOR 20,000 Milestone EXFOR Milestone 20,000 experimental works are now in the EXFOR database!

300

INSTRUCTIONS FOR SUBMITTING NUCLEAR  

E-Print Network (OSTI)

waste management proceedings. Keywords Nuclear, nuclear power plant, spent fuel, nuclear waste, dataCALIFORNIA ENERGY COMMISSION INSTRUCTIONS FOR SUBMITTING NUCLEAR POWER PLANT-RELATED DATA of Submitted Data 3 NUCLEAR POWER PLANT DATA REQUESTS 6 A. Environmental Impacts 6 B. Spent Fuel Generation 8 C

Note: This page contains sample records for the topic "boiling nuclear superheater" 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

If Terrorists Go Nuclear  

Science Journals Connector (OSTI)

...officials, two nuclear indus-try...urging the nuclear nations to...a terrorist attack is increasing...in the same risk category as...Prevention ofNuclear Terrorism," by the...to protect nuclear weapons against...security at civil plants. * As civil...The nuclear power industry should...

ELIOT MARSHALL

1986-07-11T23:59:59.000Z

302

If Terrorists Go Nuclear  

Science Journals Connector (OSTI)

...officials, two nuclear indus-try...urging the nuclear nations to...terrorist attack is increasing...the same risk category...ofNuclear Terrorism," by the...to protect nuclear weapons against...aid U.S. security, O'Keefe...at civil plants. * As civil...The nuclear power industry...

ELIOT MARSHALL

1986-07-11T23:59:59.000Z

303

Reactor & Nuclear Systems Publications | ORNL  

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

Nuclear Science Home | Science & Discovery | Nuclear Science | Publications and Reports | Reactor and Nuclear Systems Publications SHARE Reactor and Nuclear Systems Publications...

304

Nuclear Forces and Nuclear Energetics  

Science Journals Connector (OSTI)

Both a static and a momentum-dependent potential are derived from one-meson-exchange Born amplitudes, and are adjusted to fit (i) the deuteron binding energy and quadrupole moment, (ii) S, P, and D partial waves from 25 to 310 MeV, and (iii) the binding energy and saturation property of nuclear matter. This is possible through a different form of the central and tensor potentials which has not been used previously to calculate problems (i), (ii), and (iii) above. We find the ? meson unsuitable to describe the two-pion-exchange region in that a potential with meson parameters common to all partial waves is not achieved.

Lester Ingber

1970-01-01T23:59:59.000Z

305

Nuclear power: an outlook  

Science Journals Connector (OSTI)

Nuclear power: an outlook ... For nuclear power to regain public acceptance and investor confidence, the nation's nuclear plants must sustain an unblemished safety record, reflecting an industrywide commitment to the highest professional standards. ...

1983-11-14T23:59:59.000Z

306

Press Release: Nuclear Power  

Science Journals Connector (OSTI)

Two nuclear physicists, a nuclear engineer, and an economistmmembers of the Union of Concerned Scientists--released a report today that examined a new problem with nuclear reactor safety. According to the repo...

Henry W. Kendall

2000-01-01T23:59:59.000Z

307

Nuclear Data Links  

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

Links to Other Useful Sites Online Journals Institutions and Programs Related to Nuclear Physics U.S. Nuclear Data Program: All evaluated nuclear data supported by the U.S....

308

Nuclear functions of prefoldin  

Science Journals Connector (OSTI)

...original author and source are credited. Nuclear functions of prefoldin Gonzalo Millan-Zambrano...and are functionally connected with nuclear processes in yeast and metazoa. Plant...available on the involvement of prefoldin in nuclear phenomena, place special emphasis on...

2014-01-01T23:59:59.000Z

309

Nuclear Workforce Initiative - SRSCRO  

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

nuclear Nuclear Workforce Initiative The United States stands on the brink of a nuclear renaissance - a resurging confidence in the power of the clean, safe atom to finally conquer...

310

Nuclear chemistry at Harvard  

Science Journals Connector (OSTI)

Nuclear chemistry at Harvard ... This article points out the potential of the chemistry department at Harvard University for research in nuclear chemistry for students who wish to do work in the field for the Ph.D. degree. ... Nuclear / Radiochemistry ...

Geoffrey Wilkinson; Richard M. Diamond; Eugene G. Rochow

1954-01-01T23:59:59.000Z

311

Nuclear Explosive Safety  

Directives, Delegations, and Requirements

The Order establishes requirements to implement the nuclear explosive safety (NES) elements of DOE O 452.1E, Nuclear Explosive and Weapon Surety Program, for routine and planned nuclear explosive operations (NEOs).

2014-07-10T23:59:59.000Z

312

Nuclear Explosive Safety  

Directives, Delegations, and Requirements

This Department of Energy (DOE) Order establishes requirements to implement the nuclear explosive safety (NES) elements of DOE O 452.1E, Nuclear Explosive and Weapon Surety Program, or successor directive, for routine and planned nuclear explosive operations (NEOs).

2015-01-26T23:59:59.000Z

313

High Energy Nuclear Events  

Science Journals Connector (OSTI)

......research-article Articles High Energy Nuclear Events Enrico Fermi Institute...Distribution of Pions produced in High Energy Nuclear Collisions Yoshihiro Yamamoto...Possible Interpretation of High Energy Nuclear Events Nobuo Yajima, Shuji Takagi......

Enrico Fermi

1950-07-01T23:59:59.000Z

314

Nuclear Fuel Cycle & Vulnerabilities  

SciTech Connect

The objective of safeguards is the timely detection of diversion of significant quantities of nuclear material from peaceful nuclear activities to the manufacture of nuclear weapons or of other nuclear explosive devices or for purposes unknown, and deterrence of such diversion by the risk of early detection. The safeguards system should be designed to provide credible assurances that there has been no diversion of declared nuclear material and no undeclared nuclear material and activities.

Boyer, Brian D. [Los Alamos National Laboratory

2012-06-18T23:59:59.000Z

315

Nuclear Security 101 | National Nuclear Security Administration  

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

101 | National Nuclear Security Administration 101 | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Fact Sheets > Nuclear Security 101 Fact Sheet Nuclear Security 101 Mar 23, 2012 The goal of United States Government's nuclear security programs is to prevent the illegal possession, use or transfer of nuclear material,

316

Nuclear Security | National Nuclear Security Administration  

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

| National Nuclear Security Administration | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Nuclear Security Home > About Us > Our Programs > Nuclear Security Nuclear Security The Office of Defense Nuclear Security (DNS) is responsible for the development and implementation of security programs for NNSA. In this capacity, DNS is the NNSA line management organization responsible for

317

Nuclear Security 101 | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

101 | National Nuclear Security Administration 101 | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Fact Sheets > Nuclear Security 101 Fact Sheet Nuclear Security 101 Mar 23, 2012 The goal of United States Government's nuclear security programs is to prevent the illegal possession, use or transfer of nuclear material,

318

Nuclear Security | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

| National Nuclear Security Administration | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Nuclear Security Home > About Us > Our Programs > Nuclear Security Nuclear Security The Office of Defense Nuclear Security (DNS) is responsible for the development and implementation of security programs for NNSA. In this capacity, DNS is the NNSA line management organization responsible for

319

Nuclear Structure and Nuclear Reactions | Argonne Leadership...  

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

the ab initio no-core full configuration approach," Phys. Rev. C 86, 034325 (2012) Nuclear Structure and Nuclear Reactions PI Name: James Vary PI Email: jvary@iastate.edu...

320

Nuclear Structure and Nuclear Reactions | Argonne Leadership...  

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

value of 92.16 MeV and the point rms radius is 2.35 fm vs 2.33 from experiment. Nuclear Structure and Nuclear Reactions PI Name: James Vary PI Email: jvary@iastate.edu...

Note: This page contains sample records for the topic "boiling nuclear superheater" 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

Nuclear Quadrupole Moments and Nuclear Shell Structure  

DOE R&D Accomplishments (OSTI)

Describes a simple model, based on nuclear shell considerations, which leads to the proper behavior of known nuclear quadrupole moments, although predictions of the magnitudes of some quadrupole moments are seriously in error.

Townes, C. H.; Foley, H. M.; Low, W.

1950-06-23T23:59:59.000Z

322

International Nuclear Security | National Nuclear Security Administrat...  

National Nuclear Security Administration (NNSA)

Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure...

323

Nuclear Forensics | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure...

324

6 Nuclear Fuel Designs  

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

Message from the Director Message from the Director 2 Nuclear Power & Researrh Reactors 3 Discovery of Promethium 4 Nuclear Isotopes 4 Nuclear Medicine 5 Nuclear Fuel Processes & Software 6 Nuclear Fuel Designs 6 Nuclear Safety 7 Nuclear Desalination 7 Nuclear Nonproliferation 8 Neutron Scattering 9 Semiconductors & Superconductors 10 lon-Implanted Joints 10 Environmental Impact Analyses 11 Environmental Quality 12 Space Exploration 12 Graphite & Carbon Products 13 Advanced Materials: Alloys 14 Advanced Materials: Ceramics 15 Biological Systems 16 Biological Systems 17 Computational Biology 18 Biomedical Technologies 19 Intelligent Machines 20 Health Physics & Radiation Dosimetry 21 Radiation Shielding 21 Information Centers 22 Energy Efficiency: Cooling & Heating

325

LANL | Physics | Nuclear Physics  

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

Leaders in nuclear physics Physics Division scientists and engineers play an important role in the Laboratory's Nuclear Physics program, funded by the Department of Energy's Office...

326

Nuclear and Particle Futures  

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

Nuclear and Particle Futures Nuclear and Particle Futures The Lab's four Science Pillars harness capabilities for solutions to threats- on national and global scales. Contacts...

327

Nuclear Energy Advisory Committee  

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

The Nuclear Energy Advisory Committee (NEAC), formerly the Nuclear Energy Research Advisory Committee (NERAC), was established on October 1, 1998, to provide independent advice to the Office of...

328

Nuclear Safety Regulatory Framework  

Energy Savers (EERE)

Department of Energy Nuclear Safety Regulatory Framework DOE's Nuclear Safety Enabling Legislation Regulatory Enforcement & Oversight Regulatory Governance Atomic Energy Act 1946...

329

Assessment of Nuclear Resonance Fluorescence for Spent Nuclear Fuel Assay  

E-Print Network (OSTI)

Security of the National Nuclear Security Administration, USof Energys National Nuclear Security Administration (NNSA)

Quiter, Brian

2012-01-01T23:59:59.000Z

330

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

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

331

Office of Nuclear Safety  

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

Office of Nuclear Safety (HS-30) Office of Nuclear Safety (HS-30) Office of Nuclear Safety Home » Directives » Nuclear and Facility Safety Policy Rules » Nuclear Safety Workshops Technical Standards Program » Search » Approved Standards » Recently Approved » RevCom for TSP » Monthly Status Reports » Archive » Feedback DOE Nuclear Safety Research & Development Program Office of Nuclear Safety Basis & Facility Design (HS-31) Office of Nuclear Safety Basis & Facility Design - About Us » Nuclear Policy Technical Positions/Interpretations » Risk Assessment Working Group » Criticality Safety » DOE O 420.1C Facility Safety » Beyond Design Basis Events Office of Nuclear Facility Safety Programs (HS-32) Office of Nuclear Facility Safety Programs - About Us

332

FY13 Summary Report on the Augmentation of the Spent Fuel Composition Dataset for Nuclear Forensics: SFCOMPO/NF  

SciTech Connect

This report documents the FY13 efforts to enhance a dataset of spent nuclear fuel isotopic composition data for use in developing intrinsic signatures for nuclear forensics. A review and collection of data from the open literature was performed in FY10. In FY11, the Spent Fuel COMPOsition (SFCOMPO) excel-based dataset for nuclear forensics (NF), SFCOMPO/NF was established and measured data for graphite production reactors, Boiling Water Reactors (BWRs) and Pressurized Water Reactors (PWRs) were added to the dataset and expanded to include a consistent set of data simulated by calculations. A test was performed to determine whether the SFCOMPO/NF dataset will be useful for the analysis and identification of reactor types from isotopic ratios observed in interdicted samples.

Brady Raap, Michaele C.; Lyons, Jennifer A.; Collins, Brian A.; Livingston, James V.

2014-03-31T23:59:59.000Z

333

The Joys of Nuclear Engineering  

ScienceCinema (OSTI)

Nuclear fuels researcher Jon Carmack talks about the satisfactions of a career in nuclear engineering.

Jon Carmack

2010-01-08T23:59:59.000Z

334

Nuclear reactor  

DOE Patents (OSTI)

A nuclear reactor comprising a cylindrical pressure vessel, an elongated annular core centrally disposed within and spaced from the pressure vessel, and a plurality of ducts disposed longitudinally of the pressure vessel about the periphery thereof, said core comprising an annular active portion, an annular reflector just inside the active portion, and an annular reflector just outside the active a portion, said annular active portion comprising rectangular slab, porous fuel elements radially disposed around the inner reflector and extending the length of the active portion, wedge-shaped, porous moderator elements disposed adjacent one face of each fuel element and extending the length of the fuel element, the fuel and moderator elements being oriented so that the fuel elements face each other and the moderator elements do likewise, adjacent moderator elements being spaced to provide air inlet channels, and adjacent fuel elements being spaced to provide air outlet channels which communicate with the interior of the peripheral ducts, and means for introducing air into the air inlet channels which passes through the porous moderator elements and porous fuel elements to the outlet channel.

Thomson, Wallace B. (Severna Park, MD)

2004-03-16T23:59:59.000Z

335

Advanced nuclear fuel  

SciTech Connect

Kurt Terrani uses his expertise in materials science to develop safer fuel for nuclear power plants.

Terrani, Kurt

2014-07-14T23:59:59.000Z

336

TERRORISM AND NUCLEAR POWER  

Science Journals Connector (OSTI)

TERRORISM AND NUCLEAR POWER ... The attacks of Sept. 11 raise fear that U.S. nuclear power plants may be vulnerable ... THE TERRORIST ATTACKS ON THE World Trade Center and Pentagon are forcing a reexamination of the security of the nation's 103 nuclear power plants by nuclear's advocates and foes alike. ...

JEFF JOHNSON

2001-10-08T23:59:59.000Z

337

Nuclear Science & Engineering  

E-Print Network (OSTI)

. 1 Nuclear Science & Engineering Nuclear Energy Present and Future Ian H. Hutchinson Head, Department of Nuclear Science and Engineering CoPrincipal, Alcator Tokamak Project, Plasma Science and Fusion Center Massachusetts Institute of Technology Outline: Nuclear Power in the US and the World Limitations

338

SPOTLIGHT ON NUCLEAR POWER  

Science Journals Connector (OSTI)

SPOTLIGHT ON NUCLEAR POWER ... TOUGHER RULES are needed to improve the safety of U.S. nuclear power facilities and to better protect the public from the type of disaster that occurred this spring at Japan’s Fukushima Daiichi nuclear energy plant, says a preliminary report released by the Nuclear Regulatory Commission (NRC) on July 12. ...

GLENN HESS

2011-07-18T23:59:59.000Z

339

Advanced nuclear fuel  

ScienceCinema (OSTI)

Kurt Terrani uses his expertise in materials science to develop safer fuel for nuclear power plants.

Terrani, Kurt

2014-07-15T23:59:59.000Z

340

Nuclear Waste: Knowledge Waste?  

Science Journals Connector (OSTI)

...06520, USA. Nuclear power is re-emerging...proclaiming a “nuclear renaissance...example, plant safety...liabilities, terrorism at plants and in transport...high-level nuclear wastes (HLW...factor in risk perceptions...supporting nuclear power in the abstract...

Eugene A. Rosa; Seth P. Tuler; Baruch Fischhoff; Thomas Webler; Sharon M. Friedman; Richard E. Sclove; Kristin Shrader-Frechette; Mary R. English; Roger E. Kasperson; Robert L. Goble; Thomas M. Leschine; William Freudenburg; Caron Chess; Charles Perrow; Kai Erikson; James F. Short

2010-08-13T23:59:59.000Z

Note: This page contains sample records for the topic "boiling nuclear superheater" 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

Global Nuclear Energy Partnership Fact Sheet - Develop Enhanced Nuclear  

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

Global Nuclear Energy Partnership Fact Sheet - Develop Enhanced Global Nuclear Energy Partnership Fact Sheet - Develop Enhanced Nuclear Safeguards Global Nuclear Energy Partnership Fact Sheet - Develop Enhanced Nuclear Safeguards GNEP will help prevent misuse of civilian nuclear facilities for nonpeaceful purposes by developing enhanced safeguards programs and technologies. International nuclear safeguards are integral to implementing the GNEP vision of a peaceful expansion of nuclear energy and demonstration of more proliferation-resistant fuel cycle technologies. Global Nuclear Energy Partnership Fact Sheet - Develop Enhanced Nuclear Safeguards More Documents & Publications GNEP Element:Develop Enhanced Nuclear Safeguards Global Nuclear Energy Partnership Fact Sheet Global Nuclear Energy Partnership Fact Sheet - Demonstrate Small-Scale

342

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

343

NUCLEAR MATERIALTRANSACTION REPORT | Department of Energy  

Energy Savers (EERE)

NUCLEAR MATERIALTRANSACTION REPORT NUCLEAR MATERIALTRANSACTION REPORT Form used to support nuclear materials accountability and control. NUCLEAR MATERIALTRANSACTION REPORT More...

344

Nuclear Science and Engineering | ornl.gov  

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

Supporting Organizations Nuclear Science Engineering Nuclear Science Home | Science & Discovery | Nuclear Science | Supporting Organizations | Nuclear Science Engineering SHARE...

345

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

SciTech Connect

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

346

Environmental Assessments (EA) | Department of Energy  

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

21, 2003 21, 2003 EA-1446: Final Environmental Assessment Test Capabilities Revitalization at Sandia National Laboratories/New Mexico, Department of Energy, Office of Kirtland Site Operations January 1, 2003 EA-1394: Final Environmental Assessment Authorizing the Puerto Rico Electric Power Authority (PREPA) to allow Public Access to the Boiling Nuclear Superheat (BONUS) Reactor Building, Ricon, Puerto Rico December 11, 2002 EA-1430: Final Environmental Assessment Installation and Operation of Combustion Turbine Generators at Los Alamos National Laboratory, Los Alamos, New Mexico December 2, 2002 EA-1426: Final Environmental Assessment Linac Coherent Light Source Experimental Facility December 2, 2002 EA-1442: Final Environmental Assessment Proposed Construction and Operation of a Biosafety Level 3 Facility at

347

Page not found | Department of Energy  

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

41 - 6350 of 26,764 results. 41 - 6350 of 26,764 results. Download CX-002426: Categorical Exclusion Determination Development of an Energy Efficiency and Conservation Strategy CX(s) Applied: A9, A11, B5.1 Date: 05/17/2010 Location(s): Attleboro, Massachusetts Office(s): Energy Efficiency and Renewable Energy http://energy.gov/nepa/downloads/cx-002426-categorical-exclusion-determination Download Competitive Sourcing Competitive Sourcing http://energy.gov/management/downloads/competitive-sourcing-2 Download EA-1394: Final Environmental Assessment Authorizing the Puerto Rico Electric Power Authority (PREPA) to allow Public Access to the Boiling Nuclear Superheat (BONUS) Reactor Building, Ricon, Puerto Rico http://energy.gov/nepa/downloads/ea-1394-final-environmental-assessment Download EA-1814: Final Environmental Assessment

348

Page not found | Department of Energy  

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

41 - 6650 of 9,640 results. 41 - 6650 of 9,640 results. Download EA-1744: Final Environmental Assessment Brea Power II, LLC's Olinda Combined Cycle Electric Generating Plant Fueled By Waste Landfill Gas, Brea, California http://energy.gov/nepa/downloads/ea-1744-final-environmental-assessment Download EA-1345: Final Environmental Assessment Cleanup and Closure of the Energy Technology Engineering Center http://energy.gov/nepa/downloads/ea-1345-final-environmental-assessment Download EA-1394: Final Environmental Assessment Authorizing the Puerto Rico Electric Power Authority (PREPA) to allow Public Access to the Boiling Nuclear Superheat (BONUS) Reactor Building, Ricon, Puerto Rico http://energy.gov/nepa/downloads/ea-1394-final-environmental-assessment Download EIS-0425: Draft Environmental Impact Statement

349

Inspection/Sampling Schedule | Department of Energy  

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

Inspection/Sampling Schedule Inspection/Sampling Schedule Inspection/Sampling Schedule Site Inspection and Water Sampling Schedules Note: The following schedules are subject to change without prior notice and will be updated periodically. Site Name Inspection Date Sampling Week Ambrosia Lake, NM, Disposal Site August 18, 2014 November 20, 2013 Bluewater, NM, Disposal Site August 18, 2014 November 20, 2013 January 28, 2014 May 12, 2014 Boiling Nuclear Superheater (BONUS), PR, Decommissioned Reactor Site Next event 2017 Burrell, PA, Disposal Site December 9, 2013 November 20, 2013 Canonsburg, PA, Disposal Site December 9, 2013 November 19, 2013 Durango, CO, Disposal Site May 19, 2014 June 2, 2014 Durango, CO, Processing Site N/A June 2, 2014 September 1, 2014 Edgemont, SD, Disposal Site June 23, 2014 N/A

350

Nuclear Structure Aspects in Nuclear Astrophysics  

SciTech Connect

Nuclear Astrophysics as a broad and diverse field of study can be viewed as a magnifier of the impact of microscopic processes on the evolution of macroscopic events. One of the primary goals in Nuclear Astrophysics is the understanding of the nucleosynthesis processes that take place in the cosmos and the simulation of the correlated stellar and explosive burning scenarios. These simulations are strongly dependent on the input from Nuclear Physics which sets the time scale for all stellar dynamic processes--from giga-years of stellar evolution to milliseconds of stellar explosions--and provides the basis for most of the signatures that we have for the interpretation of these events--from stellar luminosities, elemental and isotopic abundances to neutrino flux from distant supernovae. The Nuclear Physics input comes through nuclear structure, low energy reaction rates, nuclear masses, and decay rates. There is a common perception that low energy reaction rates are the most important component of the required nuclear physics input; however, in this article we take a broader approach and present an overview of the close correlation between various nuclear structure aspects and their impact on nuclear astrophysics. We discuss the interplay between the weak and the strong forces on stellar time scales due to the limitations they provide for the evolution of slow and rapid burning processes. The effects of shell structure in nuclei on stellar burning processes as well as the impact of clustering in nuclei is outlined. Furthermore we illustrate the effects of the various nuclear structure aspects on the major nucleosynthesis processes that have been identified in the last few decades. We summarize and provide a coherent overview of the impact of all aspects of nuclear structure on nuclear astrophysics.

Smith, Michael Scott [ORNL

2006-12-01T23:59:59.000Z

351

The Nuclear Revolution, Relative Gains, and International Nuclear Assistance  

E-Print Network (OSTI)

Organizations, accidents, and nuclear weapons. Princeton,the likelihood of a nuclear accident (Sagan 1993, 1995). “potential for a nuclear accident. Yet it seems implausible

Kroenig, Matthew

2006-01-01T23:59:59.000Z

352

Belgium Nuclear Security Summit: Fact Sheet | National Nuclear...  

National Nuclear Security Administration (NNSA)

Nuclear Security Summit: Fact Sheet | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency...

353

Italy Nuclear Security Summit: Fact Sheet | National Nuclear...  

National Nuclear Security Administration (NNSA)

Nuclear Security Summit: Fact Sheet | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency...

354

COLLOQUIUM: Nuclear Famine: The Threat to Humanity from Nuclear...  

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

MBG Auditorium COLLOQUIUM: Nuclear Famine: The Threat to Humanity from Nuclear Weapons Dr. Alan Robock Rutgers University A nuclear war between India and Pakistan, with...

355

The Nuclear Revolution, Relative Gains, and International Nuclear Assistance  

E-Print Network (OSTI)

nature of the nuclear recipient’s security environment. ThisKeywords: Nuclear weapons proliferation; security; securitynature of the nuclear recipient’s security environment. This

Kroenig, Matthew

2006-01-01T23:59:59.000Z

356

Tennessee Nuclear Profile - Watts Bar Nuclear Plant  

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

Watts Bar Nuclear Plant" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration...

357

Wisconsin Nuclear Profile - Point Beach Nuclear Plant  

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

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

358

Massachusetts Nuclear Profile - Pilgrim Nuclear Power Station  

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

Pilgrim Nuclear Power Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer cpacity factor (percent)","Type","Commercial operation date","License...

359

Arkansas Nuclear Profile - Arkansas Nuclear One  

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

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

360

A Citation-Based Assessment Of The Performance Of U.S. Boiling Water Reactors Following Extended Power Up-Rates.  

E-Print Network (OSTI)

??Nuclear power plants produce 20 percent of the electricity generated in the U.S. Nuclear generated electricity is increasingly valuable to a utility because it can… (more)

Heidrich, Brenden

2012-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "boiling nuclear superheater" 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

Nuclear Science at NERSC  

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

Accelerator Science Accelerator Science Astrophysics Biological Sciences Chemistry & Materials Science Climate & Earth Science Energy Science Engineering Science Environmental Science Fusion Science Math & Computer Science Nuclear Science Science Highlights NERSC Citations HPC Requirements Reviews Home » Science at NERSC » Nuclear Science Nuclear Science Experimental and theoretical nuclear research carried out at NERSC is driven by the quest for improving our understanding of the building blocks of matter. This includes discovering the origins of nuclei and identifying the forces that transform matter. Specific topics include: Nuclear astrophysics and the synthesis of nuclei in stars and elsewhere in the cosmos; Nuclear forces and quantum chromodynamics (QCD), the quantum field

362

Neutron and Nuclear Science News  

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

News Recent news and events related to neutron and nuclear science at LANSCE. Neutron and Nuclear Science News Nuclear science observations and opportunities at the Los Alamos...

363

Nuclear & Radiological Activity Center (NRAC)  

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

Nuclear & Radiological Activity Center (NRAC) Where nuclear research and deployment capabilities come together to solve nuclear nonproliferation challenges. Skip Navigation Links...

364

NUCLEAR SCIENCE ANNUAL REPORT 1975  

E-Print Network (OSTI)

Gove and A. H. Wapstra, Nuclear Data Tables 11, 127 (1972).P. Jackson, Chalk River Nuclear Laboratories Report (1975)national Conference on Nuclear Structure and Spec­ troscopy,

Authors, Various

2010-01-01T23:59:59.000Z

365

Nuclear Energy University Programs (NEUP)  

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

DOE-NE Fosters Novel International Investments in U.S. Nuclear Energy Research October 14, 2014 Nuclear energy is an international industry, but nuclear research and development...

366

Counterterrorism | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

a unique Counterterrorism Counterterrorism Policy and CooperationNuclear Threat Science Office of Nuclear Threat Science The Office of Nuclear Threat Science is responsible...

367

Supporting Organizations | Nuclear Science | ORNL  

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

Educational Outreach Publications and Reports News and Awards Supporting Organizations Nuclear Science Engineering Fusion & Materials for Nuclear Systems Nuclear Science Home |...

368

Is Nuclear Energy the Solution?  

E-Print Network (OSTI)

009-0270-y Is Nuclear Energy the Solution? Milton H. Saier &in the last 50 years, nuclear energy subsidies have totaledadministration, the Global Nuclear Energy Partnership (GNEP)

Saier, Milton H.; Trevors, Jack T.

2010-01-01T23:59:59.000Z

369

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

SciTech Connect

Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWE. This volume contains the appendices.

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

1980-06-01T23:59:59.000Z

370

Nuclear Energy Program  

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

April 15, 2002 April 15, 2002 NERAC Spring 2002 Meeting Office of Nuclear Energy, Science and Technology Magwood/April15_02 NERAC.ppt (2) 2002 Will Be A Transition Year 2002 Will Be A Transition Year 6 Nuclear Power 2010 6 Major Program Developments 6 FY 2003 Budget Request Office of Nuclear Energy, Science and Technology Magwood/April15_02 NERAC.ppt (3) Nuclear Power 2010 Nuclear Power 2010 Nuclear Power 2010 is a new R&D initiative announced by Secretary Abraham on February 14, 2002. This initiative is designed to clear the way for the construction of new nuclear power plants by 2010. Office of Nuclear Energy, Science and Technology Magwood/April15_02 NERAC.ppt (4) Can We Build New U.S. Reactors By 2010? Yes! Can We Build New U.S. Reactors By 2010? Yes! Can Be Deployed by 2010

371

Promulgating Nuclear Safety Requirements  

Directives, Delegations, and Requirements

Applies to all Nuclear Safety Requirements Adopted by the Department to Govern the Conduct of its Nuclear Activities. Cancels DOE P 410.1. Canceled by DOE N 251.85.

1996-05-15T23:59:59.000Z

372

Nuclear energy in Argentina  

Science Journals Connector (OSTI)

After early interest in the possible uses of uranium in 1937, Argentina's scientists and politicians showed an inclination to support nuclear development that has kept quite steady compared with other areas. The Argentinean government prohibited the export of uranium in 1945, because of the emerging possibility of producing nuclear energy. The creation of the Atomic Energy Commission soon followed, and the first experimental reactor was set critical in 1958. Since then, nuclear development has allowed the successful operation of two nuclear power reactors, a quite integrated nuclear fuel cycle, and sustained activity in the development, production and use of radioisotopes. Nowadays an Argentinean company competes with success in the experimental nuclear reactor market. After a period in which the nuclear sector has been largely ignored in the official interest, Argentina's authorities have launched a comprehensive plan intended to rehabilitate all aspects of nuclear activity.

Gabriel N. Barcelo

2007-01-01T23:59:59.000Z

373

Nuclear Energy Production  

Science Journals Connector (OSTI)

We shall limit ourselves here to a very rough summary of the most important features of nuclear reactions in stars. This will suffice completely ... , while the study of particular aspects of nuclear astrophysics...

Professor Dr. Rudolf Kippenhahn…

1990-01-01T23:59:59.000Z

374

Marine Nuclear Propulsion  

Science Journals Connector (OSTI)

... June 30 about 95 qualified scientists and engineers were engaged on research and development on marine nuclear ... nuclear propulsion within his Department, including the Atomic Energy Authority and the Ship Research Association. This ...

1965-07-31T23:59:59.000Z

375

Nuclear Power Plants  

Science Journals Connector (OSTI)

A third issue related to the production, use and transportation of nuclear materials is the safety issue associated with ... an act of war or an act of terrorism. While the containment buildings of typical nuclear

Efstathios E. (Stathis) Michaelides

2012-01-01T23:59:59.000Z

376

Nuclear Engineer (Criticality Safety)  

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

This position is located in the Nuclear Safety Division (NSD) which has specific responsibility for managing the development, analysis, review, and approval of non-reactor nuclear facility safety...

377

Nuclear Energy & Energy Security  

Science Journals Connector (OSTI)

Safety issues related to use of nuclear energy and secure operation of nuclear installations are mail stones of great importance. Although none of technologies producing energy are absolutely safe it is obvious t...

Jumber Mamasakhlisi

2010-01-01T23:59:59.000Z

378

On Nuclear Energy Levels  

Science Journals Connector (OSTI)

...research-article On Nuclear Energy Levels K. M. Guggenheimer The formula for the energy levels of the rigid rotator...nuclei. Two kinds of nuclear rotation are discussed...an A relation for the energy levels of different nuclei...

1942-01-01T23:59:59.000Z

379

Nuclear radiation actuated valve  

DOE Patents (OSTI)

A nuclear radiation actuated valve for a nuclear reactor. The valve has a valve first part (such as a valve rod with piston) and a valve second part (such as a valve tube surrounding the valve rod, with the valve tube having side slots surrounding the piston). Both valve parts have known nuclear radiation swelling characteristics. The valve's first part is positioned to receive nuclear radiation from the nuclear reactor's fuel region. The valve's second part is positioned so that its nuclear radiation induced swelling is different from that of the valve's first part. The valve's second part also is positioned so that the valve's first and second parts create a valve orifice which changes in size due to the different nuclear radiation caused swelling of the valve's first part compared to the valve's second part. The valve may be used in a nuclear reactor's core coolant system.

Christiansen, David W. (Kennewick, WA); Schively, Dixon P. (Richland, WA)

1985-01-01T23:59:59.000Z

380

General Engineer (Nuclear Safety)  

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

The Chief of Nuclear Safety (CNS) reports the US/M&P; in serving as the Central Technical Authority (CTA) for M&P; activities, ensuring the Departments nuclear safety policies and...

Note: This page contains sample records for the topic "boiling nuclear superheater" 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

NNSA: Working to Prevent Nuclear Proliferation | National Nuclear...  

National Nuclear Security Administration (NNSA)

to Prevent Nuclear Proliferation | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation...

382

Nuclear Weapons Testing Resumes | National Nuclear Security Administra...  

National Nuclear Security Administration (NNSA)

Testing Resumes | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response...

383

Nuclear power browning out  

SciTech Connect

When the sad history of nuclear power is written, April 26, 1986, will be recorded as the day the dream died. The explosion at the Chernobyl plant was a terrible human tragedy- and it delivered a stark verdict on the hope that nuclear power will one day replace fossil fuel-based energy systems. Nuclear advocates may soldier on, but a decade after Chernobyl it is clear that nuclear power is no longer a viable energy option for the twenty-first century.

Flavin, C.; Lenssen, N.

1996-05-01T23:59:59.000Z

384

Nuclear Explosive Safety Manual  

Directives, Delegations, and Requirements

This Manual provides supplemental details to support the requirements of DOE O 452.2D, Nuclear Explosive Safety.

2009-04-14T23:59:59.000Z

385

3D NUCLEAR SEGMENTAT  

Energy Science and Technology Software Center (OSTI)

003029WKSTN00 Delineation of nuclear structures in 3D multicellular systems  https://vision.lbl.gov/Software/3DMorphometry/ 

386

FIBWR: a steady-state core flow distribution code for boiling water reactors code verification and qualification report. Final report  

SciTech Connect

A steady-state core flow distribution code (FIBWR) is described. The ability of the recommended models to predict various pressure drop components and void distribution is shown by comparison to the experimental data. Application of the FIBWR code to the Vermont Yankee Nuclear Power Station is shown by comparison to the plant measured data.

Ansari, A.F.; Gay, R.R.; Gitnick, B.J.

1981-07-01T23:59:59.000Z

387

Preparing Non-nuclear Engineers for the Nuclear Field  

E-Print Network (OSTI)

Preparing Non-nuclear Engineers for the Nuclear Field Elizabeth K. Ervin The University. An understanding of power generation is important for all modern-day engineers, and nuclear energy serves as a good-four universities have nuclear- related programs, including Nuclear or Radiological Engineering, Nuclear Science

Ervin, Elizabeth K.

388

Nuclear Eclectic Power  

Science Journals Connector (OSTI)

...much higher future costs for oil and natural gas. However, the...ELECTRICITY GENERATION FROM COAL, OIL, AND NUCLEAR FUEL, NUCLEAR...electricity generation from coal, oil, and nuclear fuel, cite about...possibility that stimu-lated a marathon debate between the Union of...

David J. Rose

1974-04-19T23:59:59.000Z

389

Nuclear Power for Italy  

Science Journals Connector (OSTI)

ITALY HAS DECIDED to use British know-how to build its first big nuclear power plant. A.G.I.P. Nucleare, a subsidiary of the Italian government-owned petroleum organization, E.N.I., and Britain's Nuclear Power Plant Co. will sign final agreement next ...

1957-12-02T23:59:59.000Z

390

Catechism for nuclear power  

Science Journals Connector (OSTI)

... doses of radiation exposure are potentially harmful to people, and should be avoided. -"Nuclear power stations, and the nuclear industry in general, are sources of artificial radiation to which ... general, are sources of artificial radiation to which people may be exposed." Therefore nuclear power stations should not be built."Hither explain in no more than 250 words which ...

1986-07-31T23:59:59.000Z

391

Nuclear Physics with trapped  

E-Print Network (OSTI)

Nuclear Physics with trapped atoms and ions #12;2/2/2013Dan Melconian #12;2/2/2013Dan Melconian Outline · Scope and applications of nuclear physics precision frontier compliments LHC properties and aquifers in the Sahara #12;2/2/2013Dan Melconian What is Nuclear Physics? · Began with the study

Boas, Harold P.

392

NUCLEAR POWER in CALIFORNIA  

E-Print Network (OSTI)

NUCLEAR POWER in CALIFORNIA: 2007 STATUS REPORT CALIFORNIA ENERGY COMMISSION October 2007 CEC-100, California Contract No. 700-05-002 Prepared For: California Energy Commission Barbara Byron, Senior Nuclear public workshops on nuclear power. The Integrated Energy Policy Report Committee, led by Commissioners

393

Nuclear Lamins and Neurobiology  

Science Journals Connector (OSTI)

...August 2014 review-article Minireview Nuclear Lamins and Neurobiology Stephen G. Young...California, USA Much of the work on nuclear lamins during the past 15 years has focused...papers have identified important roles for nuclear lamins in the central nervous system...

Stephen G. Young; Hea-Jin Jung; John M. Lee; Loren G. Fong

2014-05-19T23:59:59.000Z

394

Nuclear Explosive Safety  

Directives, Delegations, and Requirements

This Department of Energy (DOE) Order establishes requirements to implement the nuclear explosive safety (NES) elements of DOE O 452.1D, Nuclear Explosive and Weapon Surety Program, for routine and planned nuclear explosive operations (NEOs). Cancels DOE O 452.2C. Admin Chg 1, dated 7-10-13, cancels DOE O 452.2D.

2009-04-14T23:59:59.000Z

395

NUCLEAR PLANT AND CONTROL  

E-Print Network (OSTI)

for the digital protection systems of a nuclear power plant. When spec- ifying requirements for software and CRSA processes are described using shutdown system 2 of the Wolsong nuclear power plants as the digital, the missiles, and the digital protection systems embed- ded in nuclear power plants. Obviously, safety

396

Nuclear Explosive Safety  

Directives, Delegations, and Requirements

This Order establishes requirements to implement the nuclear explosive safety elements of DOE O 452.1D, Nuclear Explosive and Weapon Surety Program, for routine and planned nuclear explosive operations. Cancels DOE O 452.2C. Admin Chg 1, 7-10-13

2009-04-14T23:59:59.000Z

397

Nuclear Research Reactors  

Science Journals Connector (OSTI)

... their countries for the advent of nuclear power. A few countries had built large research reactors for the production of isotopes and to study the behaviour of nuclear fuel, but ... production of isotopes and to study the behaviour of nuclear fuel, but the small training reactor had not been developed. Since then, research ...

T. E. ALLIBONE

1963-07-20T23:59:59.000Z

398

Nuclear Energy Institutes  

Science Journals Connector (OSTI)

Nuclear Energy Institutes ... The Atomic Energy Commission and the American Society for Engineering Education offer their nuclear energy courses for engineering and science teachers again in the summer of 1960. ... At least 160 college and university teachers will study nuclear science in the seven institutes scheduled. ...

1960-01-11T23:59:59.000Z

399

ANNOUNCEMENT NUCLEAR ENGINEERING FACULTY POSITION  

E-Print Network (OSTI)

ANNOUNCEMENT NUCLEAR ENGINEERING FACULTY POSITION The Department of Nuclear Engineering undergraduate and graduate courses in general nuclear engineering. The Knoxville campus of the University, Associate Professor of Nuclear Engineering; The University of Tennessee; 312 Pasqua Engineering Bldg

Tennessee, University of

400

Counterterrorism and Counterproliferation | National Nuclear...  

National Nuclear Security Administration (NNSA)

and Counterproliferation | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response...

Note: This page contains sample records for the topic "boiling nuclear superheater" 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

Relativistic nuclear structure. I. Nuclear matter  

Science Journals Connector (OSTI)

The formalism for the Dirac-Brueckner approach to the nuclear many-body problem is described including its basis in relativistic two-nucleon scattering. A family of relativistic meson-exchange potentials is constructed which (apart from the usual coupling terms for heavy mesons) apply the pseudovector (gradient) coupling for the interaction of pseudoscalar mesons (?,?) with nucleons. These potentials describe low-energy two-nucleon scattering and the deuteron data accurately. Using these potentials, the properties of nuclear matter are calculated in the Dirac-Brueckner-Hartree-Fock approximation, in which the empirical nuclear matter saturation is explained quantitatively. The effective two-body interaction in the nuclear matter medium (G matrix) is calculated directly in the nuclear matter rest frame. Thus, cumbersome transformations between the two-nucleon center-of-mass frame and the nuclear matter rest frame are avoided. Size and nature of relativistic effects included in the present approach are examined in detail. The formalism, the potentials, and the results of this paper may also serve as a basis and a realistic starting point for systematic relativistic nuclear structure studies as well as for the investigation of further relativistic many-body corrections and of contributions of higher order.

R. Brockmann and R. Machleidt

1990-11-01T23:59:59.000Z

402

Nuclear Safety Regulatory Framework  

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

Department of Energy Department of Energy Nuclear Safety Regulatory Framework DOE's Nuclear Safety Enabling Legislation Regulatory Enforcement & Oversight Regulatory Governance Atomic Energy Act 1946 Atomic Energy Act 1954 Energy Reorganization Act 1974 DOE Act 1977 Authority and responsibility to regulate nuclear safety at DOE facilities 10 CFR 830 10 CFR 835 10 CFR 820 Regulatory Implementation Nuclear Safety Radiological Safety Procedural Rules ISMS-QA; Operating Experience; Metrics and Analysis Cross Cutting DOE Directives & Manuals DOE Standards Central Technical Authorities (CTA) Office of Health, Safety, and Security (HSS) Line Management SSO/ FAC Reps 48 CFR 970 48 CFR 952 Federal Acquisition Regulations External Oversight *Defense Nuclear Facility

403

Nuclear spirals in galaxies  

E-Print Network (OSTI)

Recent high-resolution observations indicate that nuclear spirals are often present in the innermost few hundred parsecs of disc galaxies. My models show that nuclear spirals form naturally as a gas response to non-axisymmetry in the gravitational potential. Some nuclear spirals take the form of spiral shocks, resulting in streaming motions in the gas, and in inflow comparable to the accretion rates needed to power local Active Galactic Nuclei. Recently streaming motions of amplitude expected from the models have been observed in nuclear spirals, confirming the role of nuclear spirals in feeding of the central massive black holes.

Witold Maciejewski

2006-11-08T23:59:59.000Z

404

Office of Nuclear Threat Science | National Nuclear Security Administration  

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

Nuclear Threat Science | National Nuclear Security Administration Nuclear Threat Science | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog The National Nuclear Security Administration Office of Nuclear Threat Science Home > About Us > Our Programs > Counterterrorism and Counterproliferation > Office of Nuclear Threat Science Office of Nuclear Threat Science

405

Nuclear | Department of Energy  

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

Nuclear Nuclear Nuclear Radioisotope Power Systems, a strong partnership between the Energy Department's Office of Nuclear Energy and NASA, has been providing the energy for deep space exploration. Nuclear power is the use of sustained nuclear fission to generate heat and electricity. Nuclear power plants provide about 6 percent of the world's energy and 13-14 percent of the world's electricity. Featured Five Years of Building the Next Generation of Reactors Simulated three-dimensional fission power distribution of a single 17x17 rod PWR fuel assembly. | Photo courtesy of the Consortium for Advanced Simulation of Light Water Reactors (CASL). A two-year update on the Consortium for Advanced Simulation of Light Water Reactors and the progress being made in overcoming barriers to national

406

Initiating Event Rates at U.S. Nuclear Power Plants 1988–2013  

SciTech Connect

Analyzing initiating event rates is important because it indicates performance among plants and also provides inputs to several U.S. Nuclear Regulatory Commission (NRC) risk-informed regulatory activities. This report presents an analysis of initiating event frequencies at U.S. commercial nuclear power plants since each plant’s low-power license date. The evaluation is based on the operating experience from fiscal year 1988 through 2013 as reported in licensee event reports. Engineers with nuclear power plant experience staff reviewed each event report since the last update to this report for the presence of valid scrams or reactor trips at power. To be included in the study, an event had to meet all of the following criteria: includes an unplanned reactor trip (not a scheduled reactor trip on the daily operations schedule), sequence of events starts when reactor is critical and at or above the point of adding heat, occurs at a U.S. commercial nuclear power plant (excluding Fort St. Vrain and LaCrosse), and is reported by a licensee event report. This report displays occurrence rates (baseline frequencies) for the categories of initiating events that contribute to the NRC’s Industry Trends Program. Sixteen initiating event groupings are trended and displayed. Initiators are plotted separately for initiating events with different occurrence rates for boiling water reactors and pressurized water reactors. p-values are given for the possible presence of a trend over the most recent 10 years.

John A. Schroeder; Gordon R. Bower

2014-02-01T23:59:59.000Z

407

The Office of Nuclear Verification | National Nuclear Security  

National Nuclear Security Administration (NNSA)

Nuclear Verification | National Nuclear Security Nuclear Verification | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog The Office of Nuclear Verification Home > About Us > Our Programs > Nonproliferation > Nonproliferation & International Security > The Office of Nuclear Verification The Office of Nuclear Verification

408

Eisenhower Halts Nuclear Weapons Testing | National Nuclear Security  

National Nuclear Security Administration (NNSA)

Eisenhower Halts Nuclear Weapons Testing | National Nuclear Security Eisenhower Halts Nuclear Weapons Testing | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our History > NNSA Timeline > Eisenhower Halts Nuclear Weapons Testing Eisenhower Halts Nuclear Weapons Testing August 22, 1958 Washington, DC Eisenhower Halts Nuclear Weapons Testing

409

Nuclear Science | ORNL  

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

Educational Outreach Educational Outreach Publications and Reports News and Awards Home | Science & Discovery | Nuclear Science Nuclear Science | Nuclear Science SHARE In World War II's Manhattan Project, ORNL helped usher in the nuclear age. Today, laboratory scientists are leaders in using nuclear technologies and systems to improve human health; explore safer, more environmentally friendly power; and better understand the structure of matter. Thanks to its nuclear heritage, ORNL is a world leader in the production of isotopes for medical purposes and research. The lab's High Flux Isotope Reactor (HFIR) and Radiochemical Engineering Development Center (REDC) together provide the western world's sole supply of californium-252, an isotope instrumental in a wide variety of uses including cancer therapy,

410

nuclear | OpenEI  

Open Energy Info (EERE)

nuclear nuclear Dataset Summary Description This dataset presents summary information related to world nuclear energy. It is part of a supporting dataset for the book World On the Edge: How to Prevent Environmental and Economic Collapse by Lester R. Source Earth Policy Institute Date Released January 12th, 2011 (3 years ago) Date Updated Unknown Keywords EU nuclear nuclear electricity world Data application/vnd.ms-excel icon Summary nuclear energy consumption data (xls, 68.6 KiB) Quality Metrics Level of Review Some Review Comment Temporal and Spatial Coverage Frequency Time Period License License Open Data Commons Attribution License Comment "Reuse of our data is permitted. We merely ask that wherever it is listed, it be appropriately cited" Rate this dataset

411

Nuclear Science References Database  

E-Print Network (OSTI)

The Nuclear Science References (NSR) database together with its associated Web interface, is the world's only comprehensive source of easily accessible low- and intermediate-energy nuclear physics bibliographic information for more than 210,000 articles since the beginning of nuclear science. The weekly-updated NSR database provides essential support for nuclear data evaluation, compilation and research activities. The principles of the database and Web application development and maintenance are described. Examples of nuclear structure, reaction and decay applications are specifically included. The complete NSR database is freely available at the websites of the National Nuclear Data Center http://www.nndc.bnl.gov/nsr and the International Atomic Energy Agency http://www-nds.iaea.org/nsr.

B. Pritychenko; E. B?ták; B. Singh; J. Totans

2014-07-08T23:59:59.000Z

412

Aging Management Guideline for commercial nuclear power plants: Motor control centers; Final report  

SciTech Connect

This Aging Management Guideline (AMG) provides recommended methods for effective detection and mitigation of age-related degradation mechanisms in Boiling Water Reactor (BWR) and Pressurized Water Reactor (PWR) commercial nuclear power plant motor control centers important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein.

Toman, G.; Gazdzinski, R.; O`Hearn, E. [Ogden Environmental and Energy Services Co., Inc., Blue Bell, PA (United States)

1994-02-01T23:59:59.000Z

413

National Nuclear Security Administration  

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

National Nuclear Security Administration National Nuclear Security Administration Ofice of Secure Transportation mKlK= Box RQMM= ^luquerqueI= kj= UTNUR= ;JAN 03 213 MEMORANDUM FOR GREGORY eK= WOODS GENERAL COUNSEL DEPARTMENT OF ENERGY FROM: SUBJECT: JEFFREY P. HARREL ASSIST ANT DEPU FOR SECURE 2013 ANNUAL PLANNING SUMMARY In response to your memorandum of December TI= 2012, the following information is provided for the National Nuclear Security Administration Ofice of Secure

414

Absolute nuclear material assay  

DOE Patents (OSTI)

A method of absolute nuclear material assay of an unknown source comprising counting neutrons from the unknown source and providing an absolute nuclear material assay utilizing a model to optimally compare to the measured count distributions. In one embodiment, the step of providing an absolute nuclear material assay comprises utilizing a random sampling of analytically computed fission chain distributions to generate a continuous time-evolving sequence of event-counts by spreading the fission chain distribution in time.

Prasad, Manoj K. (Pleasanton, CA); Snyderman, Neal J. (Berkeley, CA); Rowland, Mark S. (Alamo, CA)

2012-05-15T23:59:59.000Z

415

Energy from nuclear power  

SciTech Connect

Nuclear power should play a pivotal and expanded role in supplying world energy, the authors says. Risks must be minimized by designing a new generation of safe reactors. Atomic energy's vast potential can be harnessed only if issues of safety, waste and nuclear-weapon proliferation are addressed by a globally administered institution. The current situation in nuclear power is described before addressing its future.

Haefele, W.

1990-09-01T23:59:59.000Z

416

Nuclear rearrangement energy  

Science Journals Connector (OSTI)

The concept of rearrangement energy in nuclear particle removal is carefully defined by specifying several energies associated with the process and its analysis. Connection is made between the present definition and closely related concepts apt to be confused with "rearrangement energy" so defined. Remarks are made concerning the implications of rearrangement to analysis and interpretation of experimental data.NUCLEAR STRUCTURE Nuclear rearrangement energy theoretically defined and differentiated from related energies. Reaction theories examined regarding rearrangement.

William A. Friedman

1975-07-01T23:59:59.000Z

417

Nuclear Fabrication Consortium  

SciTech Connect

This report summarizes the activities undertaken by EWI while under contract from the Department of Energy (DOE) � Office of Nuclear Energy (NE) for the management and operation of the Nuclear Fabrication Consortium (NFC). The NFC was established by EWI to independently develop, evaluate, and deploy fabrication approaches and data that support the re-establishment of the U.S. nuclear industry: ensuring that the supply chain will be competitive on a global stage, enabling more cost-effective and reliable nuclear power in a carbon constrained environment. The NFC provided a forum for member original equipment manufactures (OEM), fabricators, manufacturers, and materials suppliers to effectively engage with each other and rebuild the capacity of this supply chain by : � Identifying and removing impediments to the implementation of new construction and fabrication techniques and approaches for nuclear equipment, including system components and nuclear plants. � Providing and facilitating detailed scientific-based studies on new approaches and technologies that will have positive impacts on the cost of building of nuclear plants. � Analyzing and disseminating information about future nuclear fabrication technologies and how they could impact the North American and the International Nuclear Marketplace. � Facilitating dialog and initiate alignment among fabricators, owners, trade associations, and government agencies. � Supporting industry in helping to create a larger qualified nuclear supplier network. � Acting as an unbiased technology resource to evaluate, develop, and demonstrate new manufacturing technologies. � Creating welder and inspector training programs to help enable the necessary workforce for the upcoming construction work. � Serving as a focal point for technology, policy, and politically interested parties to share ideas and concepts associated with fabrication across the nuclear industry. The report the objectives and summaries of the Nuclear Fabrication Consortium projects. Full technical reports for each of the projects have been submitted as well.

Levesque, Stephen

2013-04-05T23:59:59.000Z

418

NUCLEAR REGULATORY COMMISSION  

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

December 21, 1999 (Volume 64, Number 244)] December 21, 1999 (Volume 64, Number 244)] [Proposed Rules] [Page 71331-71333] From the Federal Register Online via GPO Access [wais.access.gpo.gov] [DOCID:fr21de99-21] ======================================================================= ----------------------------------------------------------------------- NUCLEAR REGULATORY COMMISSION 10 CFR Parts 71 and 73 RIN 3150-AG41 Advance Notification to Native American Tribes of Transportation of Certain Types of Nuclear Waste AGENCY: Nuclear Regulatory Commission. ACTION: Advance notice of proposed rulemaking. ----------------------------------------------------------------------- SUMMARY: The Nuclear Regulatory Commission (NRC) is considering an amendment to its regulations that would require NRC licensees to notify

419

Controlled Nuclear Fusion Reactions  

Science Journals Connector (OSTI)

... THE presentation of full and authoritative accounts of research on controlled nuclear fusion reactions was a major feature of the second Geneva Conference on the Peaceful Uses of ...

R. S. PEASE

1958-10-18T23:59:59.000Z

420

Unclassified Controlled Nuclear Information  

Directives, Delegations, and Requirements

To prevent unauthorized dissemination of Unclassified Controlled Nuclear Information (UCNI). Cancels DOE 5635.4 and DOE 5650.3A

1995-09-25T23:59:59.000Z

Note: This page contains sample records for the topic "boiling nuclear superheater" 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

Nuclear Energy Systems  

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

Role of Synchrotron Radiation in Solving Scientific Challenges in Advanced Nuclear Energy Systems 27 to 28 January 2010 at Argonne's Advanced Photon Source Scope Third-generation...

422

Comprehensive Nuclear Materials  

SciTech Connect

This book encompasses a rich seam of current information on the vast and multidisciplinary field of nuclear materials employed in fission and prototype fusion systems. Discussion includes both historical and contemporary international research in nuclear materials, from Actinides to Zirconium alloys, from the worlds leading scientists and engineers. Synthesizes pertinent current science to support the selection, assessment, validation and engineering of materials in extreme nuclear environments. The work discusses the major classes of materials suitable for usage in nuclear fission, fusion reactors and high power accelerators, and for diverse functions in fuels, cladding, moderator and control materials, structural, functional, and waste materials.

Konings, Dr. Rudy J. M. [European Commission Joint Research Centre; Allen, Todd R. [University of Wisconsin, Madison; Stoller, Roger E [ORNL; Yamanaka, Prof. Shinsuke [Osaka University

2012-01-01T23:59:59.000Z

423

Nuclear criticality safety guide  

SciTech Connect

This technical reference document cites information related to nuclear criticality safety principles, experience, and practice. The document also provides general guidance for criticality safety personnel and regulators.

Pruvost, N.L.; Paxton, H.C. [eds.] [eds.

1996-09-01T23:59:59.000Z

424

Nuclear Physics: Experiment Research  

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

search Nuclear Physics Program Please upgrade your browser. This site's design is only visible in a graphical browser that supports web standards, but its content is accessible to...

425

Nuclear Power in Idaho  

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

Look at Issues Dr. Ralph Bennett Idaho National Laboratory 2 What's been Changing? 1. Nuclear Regulatory Commission (NRC) * Combined constructionoperating license (COL) * Early...

426

Nuclear Data Links  

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

Links to Useful Online Nuclear Physics Journals Important Online Resources Science Direct American Institute of Physics Journals APS Journals Online: Physical Review A, B, C, D, E,...

427

Nuclear Science Series: Radiochemistry  

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

eBooks Radiochemistry Nuclear Science Series: Radiochemistry These volumes are publicly accessible via the Library Catalog or the links below. Question? 667-5809 Email Scope...

428

EIA - State Nuclear Profiles  

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

Massachusetts Nuclear Profile 2010 Massachusetts profile Massachusetts total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy...

429

EIA - State Nuclear Profiles  

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

Iowa Nuclear Profile 2010 Iowa profile Iowa total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw)...

430

EIA - State Nuclear Profiles  

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

Illinois Nuclear Profile 2010 Illinois profile Illinois total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer...

431

Nuclear magnetic resonance imaging  

Science Journals Connector (OSTI)

Nuclear magnetic resonance imaging (NMRI) is a powerful imaging modality having a range of important applications to medicine and industry. The basic principles of NMRI are reviewed in...

Rothwell, William P

1985-01-01T23:59:59.000Z

432

EIA - State Nuclear Profiles  

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

Louisiana Nuclear Profile 2010 Louisiana profile Louisiana total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer...

433

Nuclear Physics from QCD  

E-Print Network (OSTI)

Effective field theories provide a bridge between QCD and nuclear physics. I discuss light nuclei from this perspective, emphasizing the role of fine-tuning.

U. van Kolck

2008-12-20T23:59:59.000Z

434

The Chernobyl Nuclear Accident  

Science Journals Connector (OSTI)

...often repeated belief of the opponents of nuclear power that the risks, whatever they are, outweigh the need for and the known value of nuclear energy in developing electric power in the world. We are some 44 years away from the first development of nuclear energy, and yet the authors of this editorial... To the Editor: Cassel and Leaning began their editorial (July 27 issue)1 with a review of the report on the Chernobyl nuclear accident by Baranov et al.2 in the same issue, but they very quickly shifted to a barrage of warning shots across the bow of the ...

1990-02-08T23:59:59.000Z

435

Nuclear Physics Program  

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

Office Data Acquisition Group Detector & Imaging Group Electronics Group User Liaison Nuclear Physics Program HALL A Hall A wide shot of detectors Scientists from across the...

436

National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

University of California Extend Management Contracts For Defense Labs The Department of Energy (DOE), the National Nuclear Security Administration (NNSA) and the University of...

437

Nuclear Magnetic Moments  

Science Journals Connector (OSTI)

This paper contains approximate formulas (Eqs. (5) and (6) for the calculation of nuclear magnetic moments from observed hyperfine structure separations.

S. Goudsmit

1933-04-15T23:59:59.000Z

438

Management of Nuclear Materials  

Directives, Delegations, and Requirements

To establish requirements for the lifecycle management of DOE owned and/or managed accountable nuclear materials. Cancels DOE O 5660.1B.

2009-08-17T23:59:59.000Z

439

Nuclear Power Facilities (2008) | Department of Energy  

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

Nuclear Power Facilities (2008) Nuclear Power Facilities (2008) Nuclear Power Facilities (2008) More Documents & Publications Financial Institution Partnership Program - Commercial...

440

Unclassified Controlled Nuclear Information (UCNI) | Department...  

Energy Savers (EERE)

Unclassified Controlled Nuclear Information (UCNI) Unclassified Controlled Nuclear Information (UCNI) Welcome to the Unclassified Controlled Nuclear Information (UCNI) webpage....

Note: This page contains sample records for the topic "boiling nuclear superheater" 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

National Nuclear Security Administration | Department of Energy  

Office of Environmental Management (EM)

National Nuclear Security Administration National Nuclear Security Administration National Nuclear Security Administration More Documents & Publications Global Threat Reduction...

442

Nuclear Transportation Management Services | Department of Energy  

Office of Environmental Management (EM)

Nuclear Transportation Management Services Nuclear Transportation Management Services Nuclear Transportation Management Services More Documents & Publications Transportation and...

443

Unclassified Controlled Nuclear Information Training | Department...  

Office of Environmental Management (EM)

Unclassified Controlled Nuclear Information Training Unclassified Controlled Nuclear Information Training Training Unclassified Controlled Nuclear Information for persons with...

444

Advanced Nuclear Energy Projects Solicitation | Department of...  

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

Advanced Nuclear Energy Projects Solicitation Advanced Nuclear Energy Projects Solicitation INFORMATIONAL MATERIALS ADVANCED NUCLEAR ENERGY PROJECTS SOLICITATION Solicitation...

445

Draft Advanced Nuclear Energy Projects Solicitation | Department...  

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

Draft Advanced Nuclear Energy Projects Solicitation Draft Advanced Nuclear Energy Projects Solicitation INFORMATIONAL MATERIALS DRAFT ADVANCED NUCLEAR ENERGY PROJECTS SOLICITATION...

446

Nuclear fuel cycle information workshop  

SciTech Connect

This overview of the nuclear fuel cycle is divided into three parts. First, is a brief discussion of the basic principles of how nuclear reactors work; second, is a look at the major types of nuclear reactors being used and world-wide nuclear capacity; and third, is an overview of the nuclear fuel cycle and the present industrial capability in the US.

Not Available

1983-01-01T23:59:59.000Z

447

Generation IV Nuclear Energy Systems ...  

E-Print Network (OSTI)

Generation IV Nuclear Energy Systems ... The U.S. Department of Energy's Office of Nuclear Energy enhance safety and security, and develop nuclear power as an energy source for industrial applications Information ... U.S. Department of Energy www.energy.gov DOE Office of Nuclear Energy www.nuclear

Kemner, Ken

448

National Nuclear Science Week 2012 - SRSCRO  

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

to Know Nuclear National Nuclear Science Week January 23 - 27, 2012 Fostering a deeper public understanding Logos for: National Nuclear Science Week, Nuclear Workforce Initiative,...

449

Civilian Nuclear Programs, SPO-CNP: LANL  

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

Nuclear Office of Science Civilian Nuclear Programs Home Advanced Nuclear Energy Programs Yucca Mountain and Nevada Test Site Programs WIPP and Actinide Science Programs Nuclear...

450

Nuclear Resonance Fluorescence for Materials Assay  

E-Print Network (OSTI)

nuclear forensics, and safeguards for nuclear fuel cyclesIndex Terms—Nuclear Safeguards, non-destructive analysis,radiological source, nuclear safeguards including measuring

Quiter, Brian

2010-01-01T23:59:59.000Z

451

We study the continuous extractive distillation of minimum and maximum boiling azeotropic mixtures A-B with a heavy or a light entrainer E, intending to assess its feasibility based on thermodynamic insights.  

E-Print Network (OSTI)

#12;#12;Abstract We study the continuous extractive distillation of minimum and maximum boiling on operating parameters: distillate product purity and recovery, reflux ratio R and entrainer ­ feed flow rate. For the 1.0-2 class both A and B can be distillated. For one of them there exists a maximum entrainer - feed

Mailhes, Corinne

452

The Office of Nuclear Energy Announces Central Europe Nuclear Safety  

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

The Office of Nuclear Energy Announces Central Europe Nuclear The Office of Nuclear Energy Announces Central Europe Nuclear Safety Workshop in Prague The Office of Nuclear Energy Announces Central Europe Nuclear Safety Workshop in Prague October 3, 2011 - 2:04pm Addthis The Office of Nuclear Energy, in partnership with Czech Republic Ministry of Industry and Trade, Ministry of Foreign Affairs, the State Agency for Nuclear Safety of the Czech Republic, and Argonne National Laboratory, is conducting a regional Nuclear Safety Workshop on Trends in Nuclear Power Plant Safety for Robust Civil Nuclear Programs on Oct. 10-13, 2011 in Prague. U.S. Ambassador Norman Eisen and Department of Energy Assistant Secretary for Nuclear Energy Dr. Pete Lyons will deliver speeches welcoming participants. Representatives from the Czech Republic, Bulgaria, Lithuania,

453

The Nuclear Revolution, Relative Gains, and International Nuclear Assistance  

E-Print Network (OSTI)

204. Bhatia, Shyam. 1988. Nuclear rivals in the Middle East.of the merits of selective nuclear proliferation. Journal ofThe Case for a Ukranian nuclear deterrent. Foreign Affairs.

Kroenig, Matthew

2006-01-01T23:59:59.000Z

454

Density content of nuclear symmetry energy from nuclear observables  

Science Journals Connector (OSTI)

The nuclear symmetry energy at a given density measures the energy transferred in converting symmetric nuclear matter into the pure neutron matter. The density content of nuclear symmetry energy remains poorly co...

B K AGRAWAL

2014-11-01T23:59:59.000Z

455

NUCLEAR ENERGY PERGAMON Annals of Nuclear Energy 27 (2000) 138551398  

E-Print Network (OSTI)

annafs of NUCLEAR ENERGY PERGAMON Annals of Nuclear Energy 27 (2000) 138551398 www-4549(00)00033-5 #12;1386 I. Phi!, V. Arzhanov. /Annals qf Nuclear Energy 27 (2000) 1385-1398 subcritical systems (ADS

Pázsit, Imre

456

Nuclear Waste Management using Electrometallurgical Technology - Nuclear  

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

Technology Technology Nuclear Fuel Cycle and Waste Management Technologies Overview Modeling and analysis Unit Process Modeling Mass Tracking System Software Waste Form Performance Modeling Safety Analysis, Hazard and Risk Evaluations Development, Design, Operation Overview Systems and Components Development Expertise System Engineering Design Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Waste Management using Electrometallurgical Technology Bookmark and Share The NE system engineering activities involve the conceptual design, through the manufacturing and qualification testing of the Mk-IV and Mk-V electrorefiner and the cathode processor. These first-of-a-kind large scale

457

Controlled Nuclear Fusion  

Science Journals Connector (OSTI)

... papers have an English abstract. Translations of the Russian papers have already been published in Nuclear Fusion. It is a great pity, for Western readers at least, that the Russian ... two volumes are obviously going to be standard reference books for those interested in controlled nuclear fusion. They also contain a large amount of information, particularly on the theoretical side, ...

GEORGE ROWLANDS

1970-01-31T23:59:59.000Z

458

Lithium and nuclear fusion  

Science Journals Connector (OSTI)

... the EEC of a decision on the siting of the Joint European Torus (JET) nuclear fusion project, worrying setbacks though these are for European fusion research, should not be allowed ... gain is the highest (about 1,800 per fusion reaction). The first generation of nuclear fusion reactors will therefore need a continuous supply of both deuterium and tritium fuel.

Nick Walton, Ed Spooner

1976-06-17T23:59:59.000Z

459

Polyploidy and Nuclear Fusion  

Science Journals Connector (OSTI)

... mitotic figures, reported during delayed wound healing in Rhodnius11, are likewise the result of nuclear fusion. Polyploid nuclei are far more plentiful in the fat body of Rhodnius after extreme ... starved for long periods. It is probable that this occasional polyploidy also is due to nuclear fusion. Endomitosis, however, occurs regularly in the fat body of Rhodnius as in other ...

V. B. WIGGLESWORTH

1966-12-31T23:59:59.000Z

460

Nuclear Regulatory Commission issuances  

SciTech Connect

This thirty-second volume of issuances (1--496) of the Nuclear Regulatory Commission and its Atomic Safety and Licensing Appeal Boards, Atomic Safety and Licensing Boards, and Administrative Law Judges it covers the period from July 1, 1990 to December 31, 1990. The hardbound edition of the Nuclear Regulatory commission Issuances is a final compilation of the monthly issuances. It includes all of the legal precedents for the agency within a six-month period. Any opinions, decisions, denials, memoranda and orders of the Commission inadvertently omitted from the monthly softbounds and any corrections submitted by the NRC legal staff to the printed softbound issuances are contained in the hardbound edition. Cross references in the text and indexes are to the NRCI page numbers which are the same as the page numbers in this publication. Issuances are referred to as follows: Commission--CLI, Atomic Safety and Licensing Appeal Boards--ALAB, Atomic Safety and Licensing Boards--LBP, Administrative Law Judges--ALJ, Directors'Decisions--DD, and Denial of Petitions for Rulemaking--DPRM. Specific facilities discussed are: Carroll County Nuclear Station; Palo Verde Nuclear Generating Station; Perry Nuclear Power Plant; Quad Cities Nuclear Power Stations; Seabrook Station; Shoreham Nuclear Generating Plant; Vermont Yankee Nuclear Power Station; and Vogtle Electric Generating Plant.

Not Available

1990-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "boiling nuclear superheater" 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

New Nuclear Reaction  

Science Journals Connector (OSTI)

Thermonuclear-like reaction points to possibilities for better kind of nuclear energy ... FISSION can make a chain reaction take place, as can fusion. ... To these two, scientists at University of California Radiation Laboratory have added a third: a "catalyzed nuclear reaction," a reaction that yields energy and is akin to fusion (thermonuclear) reactions. ...

1957-01-14T23:59:59.000Z

462

Nuclear power engineering  

Science Journals Connector (OSTI)

... been easy to write 950 pages of unrelenting tedium. But both volumes of Pedersen's Nuclear Power read like computer printouts, an avalanche of factual information recited in a dogged monotone, ... even the most ingenious intricacy is embalmed lifeless on the page. Indeed both volumes of Nuclear Power read disconcertingly like each other. The first is called ...

Walt Patterson

1979-01-25T23:59:59.000Z

463

Whither Nuclear Physics ?  

E-Print Network (OSTI)

Nuclear Physics has had its ups and downs. However in recent years, bucked up by some new and often puzzling data, it has become a potentially very rich field. We review some of these exciting developments in a few important sectors of nuclear physics. Emphasis shall be on the study of exotic nuclei and the new physics that these nuclei are teaching us.

Syed Afsar Abbas

2008-01-07T23:59:59.000Z

464

Physics in nuclear safeguards  

Science Journals Connector (OSTI)

International agreements demand that rigorous control procedures are applied to nuclear material. Containment and surveillance techniques are used to monitor the security aspects of dealing with the material whilst accountancy provides quantitative information. The author shows that the methods used to control nuclear material can be conveniently broken down into these two parts

B.W. Hooton

1984-01-01T23:59:59.000Z

465

Nuclear wastes: Small disposals  

Science Journals Connector (OSTI)

... Much to the relief of many east coast hospitals, universities and medical schools, the Nuclear Regulatory Commission (NRC) is proposing that liquid scintillation media used for detecting low levels ... for detecting low levels of radioactivity in biological samples need no longer be buried in nuclear ...

David Dickson

1980-10-16T23:59:59.000Z

466

Nuclear Explosive Safety  

Directives, Delegations, and Requirements

The directive establishes specific nuclear explosive safety (NES) program requirements to implement the DOE NES standards and other NES criteria for routine and planned nuclear explosive operations. Cancels DOE O 452.2B. Canceled by DOE O 452.2D.

2006-06-12T23:59:59.000Z

467

Instrumentation of Nuclear Reactors  

Science Journals Connector (OSTI)

... s Lecture Theatre on January 8, a symposium of papers on the instrumentation of nuclear reactors was organized, at which about five hundred members and visitors attended, including guests from ... the Institution, took the chair and introduced Sir John Cockcroft, whose lecture on "Nuclear Reactors and their Applications" provided a general background for the three specialized papers which followed. ...

1953-03-07T23:59:59.000Z

468

[Nuclear theory: Annual report  

SciTech Connect

This report discusses topics on : nuclear structure models; algebraic models of hadronic structure; nuclear reactions; hot rotating nuclei; chaos in nuclei; signatures of the quark-gluon plasma; hadronic spectroscopy; octupole collectivity in nuclei; finite-temperature methods for the many-body problem; and classical limit of algebraic hamiltonians. (LSP)

Iachello, F.; Alhassid, Y.; Kusnezov, D.

1991-12-31T23:59:59.000Z

469

(Nuclear theory: Annual report)  

SciTech Connect

This report discusses topics on : nuclear structure models; algebraic models of hadronic structure; nuclear reactions; hot rotating nuclei; chaos in nuclei; signatures of the quark-gluon plasma; hadronic spectroscopy; octupole collectivity in nuclei; finite-temperature methods for the many-body problem; and classical limit of algebraic hamiltonians. (LSP)

Iachello, F.; Alhassid, Y.; Kusnezov, D.

1991-01-01T23:59:59.000Z

470

Nuclear physics and cosmology  

SciTech Connect

There are important aspects of Cosmology, the scientific study of the large scale properties of the universe as a whole, for which nuclear physics can provide insights. Here, we will focus on Standard Big-Bang Nucleosynthesis and we refer to the previous edition of the School [1] for the aspects concerning the variations of constants in nuclear cosmo-physics.

Coc, Alain [Centre de Sciences Nucléaires et de Sciences de la Matičre (CSNSM), CNRS/IN2P3, Université Paris Sud 11, UMR 8609, Bâtiment 104, F-91405 Orsay Campus (France)

2014-05-09T23:59:59.000Z

471

Office of Nuclear Threat Science | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Threat Science | National Nuclear Security Administration Threat Science | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog The National Nuclear Security Administration Office of Nuclear Threat Science Home > About Us > Our Programs > Counterterrorism and Counterproliferation > Office of Nuclear Threat Science Office of Nuclear Threat Science

472

Savannah River Nuclear Solutions Celebrates Nuclear Science Week...  

National Nuclear Security Administration (NNSA)

Celebrates Nuclear Science Week With Students | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing...

473

Electric Power Produced from Nuclear Reactor | National Nuclear...  

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

Electric Power Produced from Nuclear Reactor | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing...

474

Nuclear Waste Policy Act Signed | National Nuclear Security Administra...  

National Nuclear Security Administration (NNSA)

Waste Policy Act Signed | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response...

475

Nuclear disarmament with a personal touch | National Nuclear...  

National Nuclear Security Administration (NNSA)

disarmament with a personal touch | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency...

476

NNSA: Working To Prevent Nuclear Terrorism | National Nuclear...  

National Nuclear Security Administration (NNSA)

secure weapons-grade nuclear material at the Mayak Production Association in Ozersk, Russia. Completed MPC&A upgrades to 15 nuclear material buildings outside of Russia. Returned...

477

Reducing the Nuclear Weapons Stockpile | National Nuclear Security...  

National Nuclear Security Administration (NNSA)

the Nuclear Weapons Stockpile | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering...

478

JPRS report supplement: Nuclear developments. Iraq -- Nuclear and missile proliferation  

SciTech Connect

This document contains articles from foreign periodicals from throughout the world, translated into English, that concern nuclear developments, specifically nuclear and missile proliferation in Iraq.

NONE

1990-09-14T23:59:59.000Z

479

Ultrafast nuclear spin polarization for isotopes with large nuclear spin  

Science Journals Connector (OSTI)

We theoretically investigate the temporal dynamics of nuclear spin induced by short laser pulses. To realize ultrafast nuclear spin polarization, we coherently excite the hyperfine...

Nakajima, Takashi

2009-01-01T23:59:59.000Z

480

NUCLEAR ISLANDS International Leasing  

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

ISLANDS ISLANDS International Leasing of Nuclear Fuel Cycle Sites to Provide Enduring Assurance of Peaceful Use Christopher E. Paine and Thomas B. Cochran Current International Atomic Energy Agency safeguards do not provide adequate protection against the diversion to military use of materials or technology from certain types of sensitive nuclear fuel cycle facilities. In view of highly enriched uranium's relatively greater ease of use as a nuclear explosive material than plutonium and the significant diseconomies of commercial spent fuel reprocessing, this article focuses on the need for improved international controls over uranium enrichment facilities as the proximate justification for creation of an International Nuclear Fuel Cycle Association (INFCA). In principle, the proposal is equally applicable to alleviating the proliferation concerns provoked by nuclear fuel

Note: This page contains sample records for the topic "boiling nuclear superheater" 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

Nuclear Facility Design  

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

Design Design FUNCTIONAL AREA GOAL: Headquarters and Field organizations and their contractors ensure that nuclear facilities are designed to assure adequate protection for the public, workers, and the environment from nuclear hazards. REQUIREMENTS: ď‚· 10 CFR 830.120 ď‚· 10 CFR 830 subpart B ď‚· DOE O 413.3 ď‚· DOE O 420.1B ď‚· DOE O 414.1C ď‚· DOE O 226.1 ď‚· DOE M 426.1 ď‚· DEAR 970-5404-2 Guidance: ď‚· DOE G 420.1-1 ď‚· Project Management Practices, Integrated Quality ( Rev E, June 2003) ď‚· DOE Implementation Plan for DNSB Recommendation 2004-2 Performance Objective 1: Contractor Program Documentation Contracts between and the contractors who operate nuclear facilities contain adequate requirements concerning the conduct of nuclear facility safety design for nuclear facility capital projects and major modifications and the

482

World nuclear outlook 1995  

SciTech Connect

As part of the EIA program to provide energy information, this analysis report presents the current status and projections through 2015 of nuclear capacity, generation, and fuel cycle requirements for all countries in the world using nuclear power to generate electricity for commercial use. It also contains information and forecasts of developments in the uranium market. Long-term projections of US nuclear capacity, generation, and spent fuel discharges for two different scenarios through 2040 are developed for the Department of Energy`s Office of Civilian Radioactive Waste Management (OCRWM). In turn, the OCRWM provides partial funding for preparation of this report. The projections of uranium requirements are provided to the Organization for Economic Cooperation and Development (OECD) for preparation of the Nuclear Energy Agency/OECD report, Summary of Nuclear Power and Fuel Cycle Data in OECD Member Countries.

NONE

1995-09-29T23:59:59.000Z

483

THz Dynamic Nuclear Polarization NMR  

E-Print Network (OSTI)

Dynamic nuclear polarization (DNP) increases the sensitivity of nuclear magnetic resonance (NMR) spectroscopy by using high frequency microwaves to transfer the polarization of the electrons to the nuclear spins. The ...

Nanni, Emilio Alessandro

484

Neutron and Nuclear Science News  

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

News Recent news and events related to neutron and nuclear science at LANSCE. Neutron and Nuclear Science News Links Neutron and Nuclear Science News Media Links Profiles Events at...

485

Is Nuclear Energy the Solution?  

E-Print Network (OSTI)

10.1007/s11270-009-0270-y Is Nuclear Energy the Solution?MHS) attended a lecture on “Nuclear Responsibility” on theof the Alliance for Nuclear Responsibility. The information

Saier, Milton H.; Trevors, Jack T.

2010-01-01T23:59:59.000Z

486

Supporting Our Nation's Nuclear Industry  

ScienceCinema (OSTI)

On the 60th anniversary of the world's first nuclear power plant to produce electricity, Assistant Secretary for Nuclear Energy Peter Lyons discusses the Energy Department's and the Administration's commitment to promoting a nuclear renaissance in the United States.

Lyons, Peter

2013-05-29T23:59:59.000Z

487

NUCLEAR CHEMISTRY ANNUAL REPORT 1970  

E-Print Network (OSTI)

Letters 24, 1507 (1970); Nuclear Data B4, 663 (1970). 5. R.S. Hager and E. C. Seltzer, Nuclear Data A4, 1 (1968). 6. H.J. Nijgh, and R. Van Lieshout, Nuclear Spectroscopy Tables (

Authors, Various

2011-01-01T23:59:59.000Z

488

A Perspective on Nuclear Waste  

Science Journals Connector (OSTI)

The management of spent nuclear fuel and high-level nuclear waste has the deserved reputation as one of ... facing the United States and other nations using nuclear reactors for electric power generation. This pa...

D. Warner North

1999-08-01T23:59:59.000Z

489

The Discovery of Nuclear Waste  

Science Journals Connector (OSTI)

When did man discover nuclear waste? To answer this question, we first have to ask if nuclear waste really is something that could be called ... Prize in physics. In early writings within nuclear energy research ...

Göran Sundqvist

2002-01-01T23:59:59.000Z

490

Nuclear Waste Disposal Plan Drafted  

Science Journals Connector (OSTI)

Nuclear Waste Disposal Plan Drafted ... Of all the issues haunting nuclear power plants, that of disposing of the radioactive wastes and spent nuclear fuel they generate has been the most vexing. ...

1984-01-09T23:59:59.000Z

491

Relativistic Nuclear Energy Density Functionals  

Science Journals Connector (OSTI)

......research-article Articles Relativistic Nuclear Energy Density Functionals Dario Vretenar...196, 2012 137 Relativistic Nuclear Energy Density Functionals Dario Vretenar...and P. Ring 2. Relativistic nuclear energy density functionals Even though......

Dario Vretenar; Tamara Niksic; Peter Ring

2012-10-01T23:59:59.000Z

492

Energy requirements for nuclear transformations  

Science Journals Connector (OSTI)

Energy requirements for nuclear transformations ... There are several conservation requirements that must be met in nuclear reactions, including the conservation of energy (E = mc2), charge, angular and linear momentum. ... Nuclear / Radiochemistry ...

Benjamin Carrol; Peter F. E. Marapodi

1951-01-01T23:59:59.000Z

493

Antineutrino Detection for Nuclear Monitoring  

E-Print Network (OSTI)

covertly acquire these special nuclear materials from: Assembled weapons Raw uranium ore Enriched uranium antineutrino monitoring infrastructure will help avert the spread of covert nuclear reactors and weaponsAntineutrino Detection for Nuclear Monitoring Draft #12;Graphic courtesy Lawrence Livermore

Mcdonough, William F.

494

US nuclear weapons policy  

SciTech Connect

We are closing chapter one'' of the nuclear age. Whatever happens to the Soviet Union and to Europe, some of the major determinants of nuclear policy will not be what they have been for the last forty-five years. Part of the task for US nuclear weapons policy is to adapt its nuclear forces and the oganizations managing them to the present, highly uncertain, but not urgently competitive situation between the US and the Soviet Union. Containment is no longer the appropriate watchword. Stabilization in the face of uncertainty, a more complicated and politically less readily communicable goal, may come closer. A second and more difficult part of the task is to deal with what may be the greatest potential source of danger to come out of the end of the cold war: the breakup of some of the cooperative institutions that managed the nuclear threat and were created by the cold war. These cooperative institutions, principally the North Atlantic Treaty Organization (NATO), the Warsaw Pact, the US-Japan alliance, were not created specifically to manage the nuclear threat, but manage it they did. A third task for nuclear weapons policy is that of dealing with nuclear proliferation under modern conditions when the technologies needed to field effective nuclear weapons systems and their command and control apparatus are ever more widely available, and the leverage over some potential proliferators, which stemmed from superpower military support, is likely to be on the wane. This paper will make some suggestions regarding these tasks, bearing in mind that the unsettled nature of that part of the world most likely to become involved in nuclear weapons decisions today must make any suggestions tentative and the allowance for surprise more than usually important.

May, M.

1990-12-05T23:59:59.000Z

495

An expert display system and nuclear power plant control rooms  

SciTech Connect

An expert display system controls automatically the display of segments on a cathode ray tube's screen to form an image of plant operations. The image consists of an icon of: 1) the process (heat engine cycle), 2) plant control systems, and 3) safety systems. A set of data-driven, forward-chaining computer stored rules control the display of segments. As plant operation changes, measured plant data are processed through the rules, and the results control the deletion and addition of segments to the display format. The icon contains information needed by control rooms operators to monitor plant operations. One example of an expert display is illustrated for the operator's task of monitoring leakage from a safety valve in a steam line of a boiling water reactor (BWR). In another example, the use of an expert display to monitor plant operations during pre-trip, trip, and post-trip operations is discussed as a universal display. The viewpoints and opinions expressed herein are the author's personal ones, and they are not to be interpreted as Nuclear Regulatory Commission criteria, requirements, or guidelines.

Beltracchi, L.

1988-04-01T23:59:59.000Z

496

Nuclear excitation and precompound nuclear reactions  

Science Journals Connector (OSTI)

The angular distribution of nucleons emitted in nucleon-induced precompound nuclear reactions are calculated taking into account the effect of excitation on the kinematics of nucleon-nucleon scattering inside the target-plus-projectile system. The results are compared with quantum mechanical calculations and those of reaction models based on a pure nucleon-nucleon collision picture.

Anuradha De; Siddhartha Ray; Sudip Kumar Ghosh

1988-06-01T23:59:59.000Z

497

Nuclear Plant Dynamics and Safety - Nuclear Engineering Division (Argonne)  

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

Nuclear Systems Nuclear Systems Modeling and Design Analysis > Nuclear Plant Dynamics and Safety Capabilities Nuclear Systems Modeling and Design Analysis Reactor Physics and Fuel Cycle Analysis Overview Current Projects Software Nuclear Plant Dynamics and Safety Nuclear Data Program Advanced Reactor Development Nuclear Waste Form and Repository Performance Modeling Nuclear Energy Systems Design and Development Other Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Reactor Physics and Fuel Cycle Analysis Nuclear Plant Dynamics and Safety Bookmark and Share Activities in Nuclear Plant Dynamics and Safety research and development fulfill a primary goal of the Nuclear Engineering (NE) Division to promote improvements in safe and reliable operation of present and future

498

Chapter 19 - Nuclear Waste Fund  

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

Nuclear Waste Fund 19-1 Nuclear Waste Fund 19-1 CHAPTER 19 NUCLEAR WASTE FUND 1. INTRODUCTION. a. Purpose. This chapter establishes the financial, accounting, and budget policies and procedures for civilian and defense nuclear waste activities, as authorized in Public Law 97-425, the Nuclear Waste Policy Act, as amended, referred to hereafter as the Act. b. Applicability. This chapter applies to all Departmental elements, including the National Nuclear Security Administration, and activities that are funded by the Nuclear Waste Fund (NWF) or the Defense Nuclear Waste Disposal appropriation. c. Background. The Act established the Office of Civilian Radioactive Waste Management (OCRWM) and assigned it responsibility for the management

499

Is Nuclear Energy the Solution?  

Science Journals Connector (OSTI)

In the event of a major radioactive release from a nuclear power plant, public opinion would likely react strongly against nuclear power...

Milton H. Saier; Jack T. Trevors

2010-05-01T23:59:59.000Z

500

Jordan | National Nuclear Security Administration  

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

Jordan | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy...