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Note: This page contains sample records for the topic "lighting manufacturing water" from the National Library of EnergyBeta (NLEBeta).
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1

Light Water Reactor Sustainability  

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

3 Light Water Reactor Sustainability Program ACCOMPLISHMENTS REPORT 2013 Accomplishments Report | Light Water Reactor Sustainability 2 T he mission of the Light Water Reactor...

2

Light Water Reactor Sustainability  

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

4 Light Water Reactor Sustainability ACCOMPLISHMENTS REPORT 2014 Accomplishments Report | Light Water Reactor Sustainability 2 T he mission of the Light Water Reactor...

3

Solid-State Lighting Manufacturing Research and Development ...  

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

to achieve cost reduction of solid-state lighting (SSL) for general illumination through improvements in manufacturing equipment, processes, or techniques. It is anticipated that...

4

Clean Energy Manufacturing Initiative Solid-State Lighting  

SciTech Connect (OSTI)

The importance of U.S. manufacturing for clean energy technologies, such as solid-state lighting (SSL), is paramount to increasing competitiveness in a global marketplace. SSLs are poised to drive the lighting market, worldwide. In order to continue that competitiveness and support further innovation, the time to invest in U.S. manufacturing of clean energy technologies is now. Across the country, companies developing innovative clean energy technologies find competitive advantages to manufacturing in the U.S. The Department of Energy's Building Technology Office SSL Manufacturing Roadmap is just one example of how we support manufacturing through convening industry perspectives on opportunities to significantly reduce risk, improve quality, increase yields, and lower costs.

Thomas, Sunil; Edmond, John; Krames, Michael; Raman, Sudhakar

2014-09-23T23:59:59.000Z

5

Clean Energy Manufacturing Initiative Solid-State Lighting  

ScienceCinema (OSTI)

The importance of U.S. manufacturing for clean energy technologies, such as solid-state lighting (SSL), is paramount to increasing competitiveness in a global marketplace. SSLs are poised to drive the lighting market, worldwide. In order to continue that competitiveness and support further innovation, the time to invest in U.S. manufacturing of clean energy technologies is now. Across the country, companies developing innovative clean energy technologies find competitive advantages to manufacturing in the U.S. The Department of Energy's Building Technology Office SSL Manufacturing Roadmap is just one example of how we support manufacturing through convening industry perspectives on opportunities to significantly reduce risk, improve quality, increase yields, and lower costs.

Thomas, Sunil; Edmond, John; Krames, Michael; Raman, Sudhakar

2014-12-03T23:59:59.000Z

6

Problems and Opportunities in OLED Lighting Manufacturing  

Energy Savers [EERE]

NY. * Our first product was introduced last year - an amber marker light for the health care market. * We have will soon complete our commercialization of a competitive...

7

Light Water Reactor Sustainability Newsletter  

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

hydraulics software RELAP-7 (which is under development in the Light Water Reactor Sustainability LWRS Program). A novel interaction between the probabilistic part (i.e., RAVEN)...

8

Light Water Reactor Sustainability Newsletter  

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

30-35, August 2012. Clayton, D. A. and M. S. Hileman, 2012, Light Water Reactor Sustainability Non-Destructive Evaluation for Concrete Research and Development Roadmap, ORNLTM-...

9

2014 Solid-State Lighting Manufacturing R&D Workshop Presentations...  

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

Moderator U.S. OLED Lighting Manufacturing Status and Trends John Hamer, OLEDWorks DOE-SSL Manufacturing Workshop Eric Armour, Veeco Instruments Perspectives on Domestic...

10

2013 Solid-State Lighting Manufacturing R&D Workshop Presentations...  

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

Manufacturability and Quality Jose Sierra, Lighting Science The Next Step in Optics Manufacturing Imro Wong, LUXeXceL Advanced Materials and Methods for Luminaires Brad...

11

LIGHT WATER REACTOR SUSTAINABILITY PROGRAM: INTRODUCTION  

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

LIGHT WATER REACTOR SUSTAINABILITY PROGRAM: INTRODUCTION The Light Water Reactor Sustainability (LWRS) Program is the primary programmatic activity that addresses Objective 1...

12

Columbia Water and Light- HVAC and Lighting Efficiency Rebates  

Broader source: Energy.gov [DOE]

Columbia Water and Light (CWL) offers rebates to its commercial and industrial customers for the purchase of high efficiency HVAC installations and efficient lighting. Incentives for certain...

13

Light Water Reactor Sustainability (LWRS) Program  

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

Light Water Reactor Sustainability (LWRS) Program Login Instructions go here. User ID: Password: Log In Forgot your password?...

14

Cooling Semiconductor Manufacturing Facilities with Chilled Water Storage  

E-Print Network [OSTI]

This paper examines the 5.2 million gallon chilled water storage system installed at TI's Expressway manufacturing complex in Dallas, Texas. During the peak cooling season ending September 30, 1994, it provided 3,750 tons of additional peak cooling...

Fiorino, D. P.

15

Light-Water Breeder Reactor  

DOE Patents [OSTI]

Described is a light-water-moderated and -cooled nuclear breeder reactor of the seed-blanket type characterized by core modules comprising loosely packed blanket zones enriched with fissile fuel and axial zoning in the seed and blanket regions within each core module. Reactivity control over lifetime is achieved by axial displacement of movable seed zones without the use of poison rods in the embodiment illustrated. The seed is further characterized by a hydrogen-to-uranium-233 atom ratio in the range 10 to 200 and a uranium-233-to-thorium-232 atom ratio ranging from 0.012 to 0.200. The seed occupies from 10 to 35 percent of the core volume in the form of one or more individual islands or annuli. (NSA 26: 55130)

Beaudoin, B. R.; Cohen, J. D.; Jones, D. H.; Marier, Jr, L. J.; Raab, H. F.

1972-06-20T23:59:59.000Z

16

Light Water Reactor Sustainability Program Contact Information  

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

Program Organization LWRS Program Management Richard Reister Federal Project Director Light Water Reactor Deployment Office of Nuclear Energy U.S. Department of Energy...

17

Columbia Water and Light- Solar Rebates  

Broader source: Energy.gov [DOE]

Columbia Water and Light (CWL) offers rebates to its commercial and residential customers for the purchase of solar water heaters and solar photovoltaic systems. These rebates are available for...

18

Light Water Reactor Sustainability Newsletter  

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

and nuclear waste disposal. Dr. Corradini has extensive research experience in the phenomenology of beyond design basis Meet the New LWRS Program Pathway Lead accidents in light...

19

US manufacturers of commercially available stand-alone photovoltaic lighting systems  

SciTech Connect (OSTI)

This report introduces photovoltaic (PV) lighting systems, gives some specifications for ordering these systems, and provides a list of some of the manufacturers of these systems in the United States. These PV lighting systems are all commercially available. They are stand-alone systems because they are not tied to the electric utility power grid.

McNutt, P.

1994-05-01T23:59:59.000Z

20

Manufacturing  

Office of Environmental Management (EM)

Flow of Materials through Industry Sustainable 1 Manufacturing 2 Technology Assessment 3 Contents 4 1. Introduction to the TechnologySystem ......

Note: This page contains sample records for the topic "lighting manufacturing water" 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

Sustained water cleavage by visible light  

SciTech Connect (OSTI)

Sustained cleavage of water by 4 quanta of visible light is achieved in aqueous solutions by using a bifunctional redox catalyst composed of Pt and RuO/sub 2/ cosupported by colloidal TiO/sub 2/ particles. A photochemical model system containing Ru(bpy)/sub 3//sup 2 +/ as a sensitizer and methyl viologen (MV/sup 2 +/) as an electron relay is used to test the effect of catalyst composition, sensitizer concentration, pH, and temperature on the efficiency of light-induced water decomposition. Electron relay free systems also exhibit high photoactivity. Direct band gap irradiation by uv light leads to efficient water cleavage in the absence of sensitizer and relay.

Borgarello, E.; Kiwi, J.; Pelizzetti, E.; Visca, M.; Graetzel, M.

1981-10-21T23:59:59.000Z

22

Creation of a U.S. Phosphorescent OLED Lighting Panel Manufacturing Facility  

SciTech Connect (OSTI)

Universal Display Corporation (UDC) has pioneered high efficacy phosphorescent OLED (PHOLED™) technology to enable the realization of an exciting new form of high quality, energy saving solid-date lighting. In laboratory test devices, we have demonstrated greater than 100 lm/W conversion efficacy. In this program, Universal Display will demonstrate the scalability of its proprietary UniversalPHOLED technology and materials for the manufacture of white OLED lighting panels that meet commercial lighting targets. Moser Baer Technologies will design and build a U.S.- based pilot facility. The objective of this project is to establish a pilot phosphorescent OLED (PHOLED) manufacturing line in the U.S. Our goal is that at the end of the project, prototype lighting panels could be provided to U.S. luminaire manufacturers for incorporation into products to facilitate the testing of design concepts and to gauge customer acceptance, so as to facilitate the growth of the embryonic U.S. OLED lighting industry. In addition, the team will provide a cost of ownership analysis to quantify production costs including OLED performance metrics which relate to OLED cost such as yield, materials usage, cycle time, substrate area, and capital depreciation. This project was part of a new DOE initiative designed to help establish and maintain U.S. leadership in this program will support key DOE objectives by showing a path to meet Department of Energy Solid-State Lighting Manufacturing Roadmap cost targets, as well as meeting its efficiency targets by demonstrating the energy saving potential of our technology through the realization of greater than 76 lm/W OLED lighting panels by 2012.

Hack, Michael

2013-09-30T23:59:59.000Z

23

Preparing for a Water Emergency A tool for food processors, food manufacturers,  

E-Print Network [OSTI]

volume water users to be better prepared for water shortage and contamination emergencies Good business you become better prepared for a water shortage or water contamination situation. #12;PreparingPreparing for a Water Emergency A tool for food processors, food manufacturers, and other large

Keinan, Alon

24

Cedarburg Light and Water Utility- Commercial Energy Efficiency Rebate Program  

Broader source: Energy.gov [DOE]

Cedarburg Light and Water Utility provides incentives for commercial, industrial and agricultural customers to increase the energy efficiency of eligible facilities. Upon request, Cedarburg Light...

25

Multi-Applications Small Light Water Reactor - NERI Final Report  

SciTech Connect (OSTI)

The Multi-Application Small Light Water Reactor (MASLWR) project was conducted under the auspices of the Nuclear Energy Research Initiative (NERI) of the U.S. Department of Energy (DOE). The primary project objectives were to develop the conceptual design for a safe and economic small, natural circulation light water reactor, to address the economic and safety attributes of the concept, and to demonstrate the technical feasibility by testing in an integral test facility. This report presents the results of the project. After an initial exploratory and evolutionary process, as documented in the October 2000 report, the project focused on developing a modular reactor design that consists of a self-contained assembly with a reactor vessel, steam generators, and containment. These modular units would be manufactured at a single centralized facility, transported by rail, road, and/or ship, and installed as a series of self-contained units. This approach also allows for staged construction of an NPP and ''pull and replace'' refueling and maintenance during each five-year refueling cycle.

S. Michale Modro; James E. Fisher; Kevan D. Weaver; Jose N. Reyes, Jr.; John T. Groome; Pierre Babka; Thomas M. Carlson

2003-12-01T23:59:59.000Z

26

Zircaloy performance in light water reactors  

SciTech Connect (OSTI)

Zircaloy has been successfully used as the primary light water reactor (LWR) core structural material since its introduction in the early days of the US naval nuclear program. Its unique combination of low neutron absorption cross section, fabricability, mechanical strength, and corrosion resistance in water and steam near 300{degrees}C has resulted in remarkable reliability of operation of pressurized and boiling water reactor (PWR, BWR) fuel through the years. At present time, BWRs use Zircaloy-2 and PWRs use Zircaloy-4 for fuel cladding. In BWRs, both Zircaloy-2 and -4 have been successfully used for spacer grids and channels, and in PWRs Zircaloy-4 is used for spacer grids and control rod guide tubes. Performance of fuel rods has been excellent thus far. The current trend for utilities worldwide is to expect both higher fuel reliability in the future. Fuel suppliers have already achieved extended exposures in lead use assemblies, and have demonstrated excellent performance in all areas; therefore unsuspected problems are not likely to arise. However, as exposure and expectations continue to increase, Zircaloy is being taken toward the limits of its known capabilities. This paper reviews Zircaloy performance capabilities in areas related to environmentally affected microstructure, mechanical properties, corrosion resistance, and dimensional stability. The effects of radiation and reactor environment on each property is illustrated with data, micrographs, and analysis.

Adamson, R.B.; Cheng, B.C.; Kruger, R.M. [GE Nuclear Energy, Pleasanton, CA (United States)

1992-12-31T23:59:59.000Z

27

Light water reactor lower head failure analysis  

SciTech Connect (OSTI)

This document presents the results from a US Nuclear Regulatory Commission-sponsored research program to investigate the mode and timing of vessel lower head failure. Major objectives of the analysis were to identify plausible failure mechanisms and to develop a method for determining which failure mode would occur first in different light water reactor designs and accident conditions. Failure mechanisms, such as tube ejection, tube rupture, global vessel failure, and localized vessel creep rupture, were studied. Newly developed models and existing models were applied to predict which failure mechanism would occur first in various severe accident scenarios. So that a broader range of conditions could be considered simultaneously, calculations relied heavily on models with closed-form or simplified numerical solution techniques. Finite element techniques-were employed for analytical model verification and examining more detailed phenomena. High-temperature creep and tensile data were obtained for predicting vessel and penetration structural response.

Rempe, J.L.; Chavez, S.A.; Thinnes, G.L. [EG and G Idaho, Inc., Idaho Falls, ID (United States)] [and others

1993-10-01T23:59:59.000Z

28

Water cooled metal optics for the Advanced Light Source  

SciTech Connect (OSTI)

The program for providing water cooled metal optics for the Advanced Light Source at Berkeley is reviewed with respect to fabrication and metrology of the surfaces. Materials choices, surface figure and smoothness specifications, and metrology systems for measuring the plated metal surfaces are discussed. Results from prototype mirrors and grating blanks will be presented, which show exceptionally low microroughness and mid-period error. We will briefly describe out improved version of the Long Trace Profiler, and its importance to out metrology program. We have completely redesigned the mechanical, optical and computational parts of the profiler system with the cooperation of Peter Takacs of Brookhaven, Continental Optical, and Baker Manufacturing. Most important is that one of our profilers is in use at the vendor to allow testing during fabrication. Metrology from the first water cooled mirror for an ALS beamline is presented as an example. The preplating processing and grinding and polishing were done by Tucson Optical. We will show significantly better surface microroughness on electroless nickel, over large areas, than has been reported previously.

McKinney, W.R.; Irick, S.C. [Lawrence Berkeley Lab., CA (United States); Lunt, D.L.J. [Tucson Optical Research Corp., AZ (United States)

1991-10-28T23:59:59.000Z

29

austenitic light water: Topics by E-print Network  

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

First, a solid SiC-coated ... Hejzlar, P. 26 Overview of light waterhydrogen-base low energy nuclear reactions CiteSeer Summary: This paper reviews light water and hydrogen-based...

30

Water Cooling of High Power Light Emitting Diode Henrik Srensen  

E-Print Network [OSTI]

Water Cooling of High Power Light Emitting Diode Henrik Sørensen Department of Energy Technology and product lifetime. The high power Light Emitting Diodes (LED) belongs to the group of electronics

Berning, Torsten

31

Environmentally assisted cracking in light water reactors  

SciTech Connect (OSTI)

This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally assisted cracking (EAC) in light water reactors (LWRs) from April 1995 to December 1995. Topics that have been investigated include fatigue of carbon and low-alloy steel used in reactor piping and pressure vessels, EAC of Alloy 600 and 690, and irradiation-assisted stress corrosion cracking (IASCC) of Type 304 SS. Fatigue tests were conducted on ferritic steels in water that contained various concentrations of dissolved oxygen (DO) to determine whether a slow strain rate applied during different portions of a tensile-loading cycle are equally effective in decreasing fatigue life. Crack-growth-rate tests were conducted on compact-tension specimens from several heats of Alloys 600 and 690 in simulated LWR environments. Effects of fluoride-ion contamination on susceptibility to intergranular cracking of high- and commercial- purity Type 304 SS specimens from control-tensile tests at 288 degrees Centigrade. Microchemical changes in the specimens were studied by Auger electron spectroscopy and scanning electron microscopy to determine whether trace impurity elements may contribute to IASCC of these materials.

Chopra, O.K.; Chung, H.M.; Gruber, E.E. [and others

1996-07-01T23:59:59.000Z

32

Duquesne Light Company- Residential Solar Water Heating Program  

Broader source: Energy.gov [DOE]

Duquesne Light provides rebates to its residential customers for purchasing and installing qualifying solar water heating systems. Eligible systems may receive a flat rebate of $286 per qualifying...

33

Light Water Reactor Sustainability Newsletter Kathryn McCarthy  

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

Technical Integration Office T he Light Water Reactor Sustainability (LWRS) Pro- gram Integrated Program Plan was released on January 31, 2012; it can be downloaded at https:...

34

Light Water Reactor Sustainability Newsletter Rebecca Smith-Kevern  

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

Rebecca Smith-Kevern Director, Office of Light Water Reactor Technologies. I am often asked why the Federal Government should fund a program that supports the continued operation...

35

Light Water Reactor Sustainability Program - Non-Destructive...  

Energy Savers [EERE]

for Determining Remaining Useful Life of Aging Cables in Nuclear Power Plants Light Water Reactor Sustainability Program - Non-Destructive Evaluation R&D Roadmap for...

36

Light Water Reactor Sustainability Newsletter By Rich Reister  

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

the safety, and extend the life of current reactors. The Light Water Re- actor Sustainability (LWRS) program is NE's principal means of achieving this objective. We have...

37

Light Water Reactor Sustainability Newsletter Thomas M. Rosseel  

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

Laboratory (ORNL), through the Department of Energy's (DOE) Light Water Reactor Sustainability (LWRS) Program, is coordinating and contracting with Zion Solutions, LLC (a...

38

Light Water Reactor Sustainability Newsletter By John Gaertner  

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

Year 2011 LWRS Program funding is very clear: "Regarding the Light Water Reactor Sustainability program, (Congress) expects a high cost share from industry." Cost sharing is...

39

City Water Light and Power- Residential Energy Efficiency Rebate Programs  

Broader source: Energy.gov [DOE]

City Water Light and Power (CWLP) offers rebates to Springfield residential customers for increasing the energy efficiency of participating homes. Rebates are available for geothermal heat pumps,...

40

City Water Light and Power- Commercial Energy Efficiency Rebate Programs  

Broader source: Energy.gov [DOE]

City Water Light and Power (CWLP) offers rebates to help commercial customers increase the energy efficiency of participating facilities. Energy efficient air-to-air, geothermal and water-loop...

Note: This page contains sample records for the topic "lighting manufacturing water" 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

Development of Advanced Manufacturing Methods for Warm White LEDs for General Lighting  

SciTech Connect (OSTI)

GE Lighting Solutions will develop precise and efficient manufacturing techniques for the “remote phosphor” platform of warm-white LED products. In volume, this will be demonstrated to drive significant materials, labor and capital productivity to achieve a maximum possible 53% reduction in overall cost. In addition, the typical total color variation for these white LEDs in production will be well within the ANSI bins and as low as a 4-step MacAdam ellipse centered on the black body curve. Achievement of both of these objectives will be demonstrated while meeting a performance target of > 75 lm/W for a warm-white LED and a reliability target of <30% lumen drop / <2-step MacAdam ellipse shift, estimated over 50,000 hrs.

Deshpande, Anirudha; Kolodin, Boris; Jacob, Cherian; Chowdhury, Ashfaqul; Kuenzler, Glenn; Sater, Karen; Aesram, Danny; Glaettli, Steven; Gallagher, Brian; Langer, Paul; Setlur, Anant; Beers, Bill

2012-03-31T23:59:59.000Z

42

Upcoming Funding Opportunity for Water Power Manufacturing | Department of  

Energy Savers [EERE]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of Inspector GeneralDepartment of EnergyofProject is on Track|Solar Decathlon |Energy Water Power

43

Safety of light water reactor fuel with silicon carbide cladding  

E-Print Network [OSTI]

Structural aspects of the performance of light water reactor (LWR) fuel rod with triplex silicon carbide (SiC) cladding - an emerging option to replace the zirconium alloy cladding - are assessed. Its behavior under accident ...

Lee, Youho

2013-01-01T23:59:59.000Z

44

Columbia Water and Light- Residential HVAC Rebate Program  

Broader source: Energy.gov [DOE]

Columbia Water and Light (CWL) provides an HVAC incentive for residential customers that are replacing an older heating and cooling system. Customers should submit the mechanical permit from a...

45

Columbia Water and Light- Residential Super Saver Loans  

Broader source: Energy.gov [DOE]

The Columbia Water and Light (CWL) Home Performance Super Saver Loan allows Columbia residents to finance energy improvements to homes with affordable, low interest loans with five to ten year...

46

Columbia Water and Light- Commercial Super Saver Loans  

Broader source: Energy.gov [DOE]

Columbia Water and Light (CWL) provides Commercial Super Saver Loans, which allow C&I rate customers to replace a furnace along with a new central air conditioner or heat pump with an...

47

Light Water Reactor Sustainability Newsletter Kathryn A. McCarthy  

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

S ome of the Light Water Reactor Sustainability (LWRS) Program managers have changed; therefore, I would like to provide a brief introduction to all of the LWRS program managers:...

48

Photovoltaic device with increased light absorption and method for its manufacture  

DOE Patents [OSTI]

A photovoltaic cell having a light-directing optical element integrally formed in an encapsulant layer thereof. The optical element redirects light to increase the internal absorption of light incident on the photovoltaic device.

Glatfelter, Troy (Royal Oak, MI); Vogeli, Craig (New Baltimore, MI); Call, Jon (Royal Oak, MI); Hammond, Ginger (Imlay City, MI)

1993-07-20T23:59:59.000Z

49

Reduced heat flow in light water (H2O) due to heavy water (D2O)  

E-Print Network [OSTI]

The flow of heat, from top to bottom, in a column of light water can be decreased by over 1000% with the addition of heavy water. A column of light water cools from 25 C to 0 C in 11 hours, however, with the addition of heavy water it takes more than 100 hours. There is a concentration dependence where the cooling time increases as the concentration of added (D2O) increases, with a near maximum being reached with as little as 2% of (D2O) added. This phenomenon will not occur if the water is mixed after the heavy water is added.

William R. Gorman; James D. Brownridge

2008-09-04T23:59:59.000Z

50

Standard practice for evaluation of surveillance capsules from light-water moderated nuclear power reactor vessels  

E-Print Network [OSTI]

Standard practice for evaluation of surveillance capsules from light-water moderated nuclear power reactor vessels

American Society for Testing and Materials. Philadelphia

2010-01-01T23:59:59.000Z

51

Near-infrared light scattering by particles in coastal waters  

E-Print Network [OSTI]

Near-infrared light scattering by particles in coastal waters David Doxaran* , Marcel Babin extend over the near-infrared spectral region to up to 870 nm. The measurements were conducted in three in the near-infrared very closely matched a - spectral dependence, which is expected when the particle size

Babin, Marcel

52

Next Generation Print-based Manufacturing for Photovoltaics and Solid State Lighting  

SciTech Connect (OSTI)

For the grand challenge of reducing our energy and carbon footprint, the development of renewable energy and energy efficient technologies offer a potential solution. Energy technologies can reduce our dependence on foreign oil as well as the energy consumed by the petroleum industry, the leading consumer of energy by a U.S. industry sector. Nonetheless, the manufacturing processes utilized to manufacture equipment for alternative energy technologies often involve energy-intensive processes. This undermines some of the advantages to moving to 'green' technologies in the first place. Our answer to the Industrial Technology Program's (ITP) Grand Challenge FOA was to develop a transformational low cost manufacturing process for plastic-based photovoltaics that will lower by over 50% both energy consumption and greenhouse emissions and offer a return-of-investment of over 20%. We demonstrated a Luminescent Solar Concentrator fabricated on a plastic acrylic substrate (i.e. no glass) that increases the power output of the PV cell by 2.2x with a 2% power efficiency as well as an LSC with a 7% power efficiency that increased the power output from the PV cells by 35%. S large area 20-inch x 60-inch building-integrated photovoltaic window was fabricated using contract manufacturing with a 4% power efficiency which improved the power output of the PV cell by over 50%. In addition, accelerated lifetimes of the luminescent material demonstrate lifetimes of 20-years.

Sue A. Carter

2012-09-07T23:59:59.000Z

53

2012 Solid-State Lighting Manufacturing R&D Workshop Presentations...  

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

Frank Cerio, Veeco Instruments Advanced Epi Tools for Gallium Nitride Light Emitting Diode Devices Vivek Agrawal, Applied Materials Driving Down HB-LED Costs:...

54

MANUFACTURING Manufacturing and Biomanufacturing  

E-Print Network [OSTI]

process improvements to manufacturing. In addition, the critical national need area of Manufacturing hasMANUFACTURING Manufacturing and Biomanufacturing: Materials Advances and Critical Processes NATIONAL NEED The proposed topics within "Manufacturing and Biomanufacturing: Materials Advances

Magee, Joseph W.

55

The Third Annual DOE Solid-State Lighting Manufacturing R&D Workshop |  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustion |Energy Usage »of EnergyThe Energy DepartmentCategoryAdvanced Manufacturing

56

Multi-Application Small Light Water Reactor Final Report  

SciTech Connect (OSTI)

The Multi-Application Small Light Water Reactor (MASLWR) project was conducted under the auspices of the Nuclear Energy Research Initiative (NERI) of the U.S. Department of Energy (DOE). The primary project objectives were to develop the conceptual design for a safe and economic small, natural circulation light water reactor, to address the economic and safety attributes of the concept, and to demonstrate the technical feasibility by testing in an integral test facility. This report presents the results of the project. After an initial exploratory and evolutionary process, as documented in the October 2000 report, the project focused on developing a modular reactor design that consists of a self-contained assembly with a reactor vessel, steam generators, and containment. These modular units would be manufactured at a single centralized facility, transported by rail, road, and/or ship, and installed as a series of self-contained units. This approach also allows for staged construction of an NPP and ''pull and replace'' refueling and maintenance during each five-year refueling cycle. Development of the baseline design concept has been sufficiently completed to determine that it complies with the safety requirements and criteria, and satisfies the major goals already noted. The more significant features of the baseline single-unit design concept include: (1) Thermal Power--150 MWt; (2) Net Electrical Output--35 MWe; (3) Steam Generator Type--Vertical, helical tubes; (4) Fuel UO{sub 2}, 8% enriched; (5) Refueling Intervals--5 years; (6) Life-Cycle--60 years. The economic performance was assessed by designing a power plant with an electric generation capacity in the range of current and advanced evolutionary systems. This approach allows for direct comparison of economic performance and forms a basis for further evaluation, economic and technical, of the proposed design and for the design evolution towards a more cost competitive concept. Applications such as cogeneration, water desalination or district heating were not addressed directly in the economic analyses since these depend more on local conditions, demand and economy and can not be easily generalized. Current economic performance experience and available cost data were used. The preliminary cost estimate, based on a concept that could be deployed in less than a decade, is: (1) Net Electrical Output--1050 MWe; (2) Net Station Efficiency--23%; (3) Number of Power Units--30; (4) Nominal Plant Capacity Factor--95%; (5) Total capital cost--$1241/kWe; and (6) Total busbar cost--3.4 cents/kWh. The project includes a testing program that has been conducted at Oregon State University (OSU). The test facility is a 1/3-height and 1/254.7 volume scaled design that will operate at full system pressure and temperature, and will be capable of operation at 600 kW. The design and construction of the facility have been completed. Testing is scheduled to begin in October 2002. The MASLWR conceptual design is simple, safe, and economical. It operates at NSSS parameters much lower than for a typical PWR plant, and has a much simplified power generation system. The individual reactor modules can be operated as on/off units, thereby limiting operational transients to startup and shutdown. In addition, a plant can be built in increments that match demand increases. The ''pull and replace'' concept offers automation of refueling and maintenance activities. Performing refueling in a single location improves proliferation resistance and eliminates the threat of diversion. Design certification based on testing is simplified because of the relatively low cost of a full-scale prototype facility. The overall conclusion is that while the efficiency of the power generation unit is much lower (23% versus 30%), the reduction in capital cost due to simplification of design more than makes up for the increased cost of nuclear fuel. The design concept complies with the safety requirements and criteria. It also satisfies the goals for modularity, standard plant design, certification before construction, c

Modro, S.M.; Fisher, J.E.; Weaver, K.D.; Reyes, J.N.; Groome, J.T.; Babka, P.; Carlson, T.M.

2003-12-01T23:59:59.000Z

57

Calculation of heat capacities of light and heavy water by path-integral molecular dynamics  

E-Print Network [OSTI]

Calculation of heat capacities of light and heavy water by path-integral molecular dynamics-integral molecular dynamics has been used to calculate the constant-volume heat capacities of light and heavy water

Nielsen, Steven O.

58

Assessment of innovative fuel designs for high performance light water reactors  

E-Print Network [OSTI]

To increase the power density and maximum allowable fuel burnup in light water reactors, new fuel rod designs are investigated. Such fuel is desirable for improving the economic performance light water reactors loaded with ...

Carpenter, David Michael

2006-01-01T23:59:59.000Z

59

Light Water Reactor Sustainability (LWRS) Program | Department of Energy  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGYWomen OwnedofDepartment ofJared Temanson -of Energy 1procedures,Light Water Reactor

60

Fuel Summary Report: Shippingport Light Water Breeder Reactor - Rev. 2  

SciTech Connect (OSTI)

The Shippingport Light Water Breeder Reactor (LWBR) was developed by Bettis Atomic Power Laboratory to demonstrate the potential of a water-cooled, thorium oxide fuel cycle breeder reactor. The LWBR core operated from 1977-82 without major incident. The fuel and fuel components suffered minimal damage during operation, and the reactor testing was deemed successful. Extensive destructive and nondestructive postirradiation examinations confirmed that the fuel was in good condition with minimal amounts of cladding deformities and fuel pellet cracks. Fuel was placed in wet storage upon arrival at the Expended Core Facility, then dried and sent to the Idaho Nuclear Technology and Engineering Center for underground dry storage. It is likely that the fuel remains in good condition at its current underground dry storage location at the Idaho Nuclear Technology and Engineering Center. Reports show no indication of damage to the core associated with shipping, loading, or storage.

Olson, Gail Lynn; Mc Cardell, Richard Keith; Illum, Douglas Brent

2002-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "lighting manufacturing water" 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

Method of burning lightly loaded coal-water slurries  

DOE Patents [OSTI]

In a preferred arrangement of the method of the invention, a lightly loaded coal-water slurry, containing in the range of approximately 40% to 52% + 2% by weight coal, is atomized to strip water from coal particles in the mixture. Primary combustor air is forced around the atomized spray in a combustion chamber of a combustor to swirl the air in a helical path through the combustion chamber. A flame is established within the combustion chamber to ignite the stripped coal particles, and flame temperature regulating means are provided for maintaining the flame temperature within a desired predetermined range of temperatures that is effective to produce dry, essentially slag-free ash from the combustion process.

Krishna, C.R.

1984-07-27T23:59:59.000Z

62

Reduced heat flow in light water (H2O) due to heavy water (D2O) William R. Gormana)  

E-Print Network [OSTI]

Reduced heat flow in light water (H2O) due to heavy water (D2O) William R. Gormana) and James D by over 1000% with the addition of heavy water. A column of light water cools from 25°C to 0°C in 11 hours, however, with the addition of heavy water it takes more than 100 hours. There is a concentration

Suzuki, Masatsugu

63

Accident Performance of Light Water Reactor Cladding Materials  

SciTech Connect (OSTI)

During a loss of coolant accident as experienced at Fukushima, inadequate cooling of the reactor core forces component temperatures ever higher where they must withstand aggressive chemical environments. Conventional zirconium cladding alloys will readily oxidize in the presence of water vapor at elevated temperatures, rapidly degrading and likely failing. A cladding breach removes the critical barrier between actinides and fission products and the coolant, greatly increasing the probability of the release of radioactivity in the event of a containment failure. These factors have driven renewed international interest in both study and improvement of the materials used in commercial light water reactors. Characterization of a candidate cladding alloy or oxidation mitigation technique requires understanding of both the oxidation kinetics and hydrogen production as a function of temperature and atmosphere conditions. Researchers in the MST division supported by the DOE-NE Fuel Cycle Research and Development program are working to evaluate and quantify these parameters across a wide range of proposed cladding materials. The primary instrument employed is a simultaneous thermal analyzer (STA) equipped with a specialized water vapor furnace capable of maintaining temperatures above 1200 C in a range of atmospheres and water vapor contents. The STA utilizes thermogravimetric analysis and a coupled mass spectrometer to measure in situ oxidation and hydrogen production of candidate materials. This capability is unprecedented in study of materials under consideration for reactor cladding use, and is currently being expanded to investigate proposed coating techniques as well as the effect of coating defects on corrosion resistance.

Nelson, Andrew T. [Los Alamos National Laboratory

2012-07-24T23:59:59.000Z

64

Issues affecting advanced passive light-water reactor safety analysis  

SciTech Connect (OSTI)

Next generation commercial reactor designs emphasize enhanced safety through improved safety system reliability and performance by means of system simplification and reliance on immutable natural forces for system operation. Simulating the performance of these safety systems will be central to analytical safety evaluation of advanced passive reactor designs. Yet the characteristically small driving forces of these safety systems pose challenging computational problems to current thermal-hydraulic systems analysis codes. Additionally, the safety systems generally interact closely with one another, requiring accurate, integrated simulation of the nuclear steam supply system, engineered safeguards and containment. Furthermore, numerical safety analysis of these advanced passive reactor designs wig necessitate simulation of long-duration, slowly-developing transients compared with current reactor designs. The composite effects of small computational inaccuracies on induced system interactions and perturbations over long periods may well lead to predicted results which are significantly different than would otherwise be expected or might actually occur. Comparisons between the engineered safety features of competing US advanced light water reactor designs and analogous present day reactor designs are examined relative to the adequacy of existing thermal-hydraulic safety codes in predicting the mechanisms of passive safety. Areas where existing codes might require modification, extension or assessment relative to passive safety designs are identified. Conclusions concerning the applicability of these codes to advanced passive light water reactor safety analysis are presented.

Beelman, R.J.; Fletcher, C.D.; Modro, S.M.

1992-01-01T23:59:59.000Z

65

Issues affecting advanced passive light-water reactor safety analysis  

SciTech Connect (OSTI)

Next generation commercial reactor designs emphasize enhanced safety through improved safety system reliability and performance by means of system simplification and reliance on immutable natural forces for system operation. Simulating the performance of these safety systems will be central to analytical safety evaluation of advanced passive reactor designs. Yet the characteristically small driving forces of these safety systems pose challenging computational problems to current thermal-hydraulic systems analysis codes. Additionally, the safety systems generally interact closely with one another, requiring accurate, integrated simulation of the nuclear steam supply system, engineered safeguards and containment. Furthermore, numerical safety analysis of these advanced passive reactor designs wig necessitate simulation of long-duration, slowly-developing transients compared with current reactor designs. The composite effects of small computational inaccuracies on induced system interactions and perturbations over long periods may well lead to predicted results which are significantly different than would otherwise be expected or might actually occur. Comparisons between the engineered safety features of competing US advanced light water reactor designs and analogous present day reactor designs are examined relative to the adequacy of existing thermal-hydraulic safety codes in predicting the mechanisms of passive safety. Areas where existing codes might require modification, extension or assessment relative to passive safety designs are identified. Conclusions concerning the applicability of these codes to advanced passive light water reactor safety analysis are presented.

Beelman, R.J.; Fletcher, C.D.; Modro, S.M.

1992-08-01T23:59:59.000Z

66

Design and optimization of a light-emitting diode projection micro-stereolithography three-dimensional manufacturing system  

E-Print Network [OSTI]

The rapid manufacture of complex three-dimensional micro-scale components has eluded researchers for decades. Several additive manufacturing options have been limited by either speed or the ability to fabricate true ...

Lee, Howon

67

The Consortium for Advanced Simulation of Light Water Reactors  

SciTech Connect (OSTI)

The Consortium for Advanced Simulation of Light Water Reactors (CASL) is a DOE Energy Innovation Hub for modeling and simulation of nuclear reactors. It brings together an exceptionally capable team from national labs, industry and academia that will apply existing modeling and simulation capabilities and develop advanced capabilities to create a usable environment for predictive simulation of light water reactors (LWRs). This environment, designated as the Virtual Environment for Reactor Applications (VERA), will incorporate science-based models, state-of-the-art numerical methods, modern computational science and engineering practices, and uncertainty quantification (UQ) and validation against data from operating pressurized water reactors (PWRs). It will couple state-of-the-art fuel performance, neutronics, thermal-hydraulics (T-H), and structural models with existing tools for systems and safety analysis and will be designed for implementation on both today's leadership-class computers and the advanced architecture platforms now under development by the DOE. CASL focuses on a set of challenge problems such as CRUD induced power shift and localized corrosion, grid-to-rod fretting fuel failures, pellet clad interaction, fuel assembly distortion, etc. that encompass the key phenomena limiting the performance of PWRs. It is expected that much of the capability developed will be applicable to other types of reactors. CASL's mission is to develop and apply modeling and simulation capabilities to address three critical areas of performance for nuclear power plants: (1) reduce capital and operating costs per unit energy by enabling power uprates and plant lifetime extension, (2) reduce nuclear waste volume generated by enabling higher fuel burnup, and (3) enhance nuclear safety by enabling high-fidelity predictive capability for component performance.

Ronaldo Szilard; Hongbin Zhang; Doug Kothe; Paul Turinsky

2011-10-01T23:59:59.000Z

68

Fuel Summary Report: Shippingport Light Water Breeder Reactor  

SciTech Connect (OSTI)

The Shippingport Light Water Breeder Reactor (LWBR) was a small water cooled, U-233/Th-232 cycle breeder reactor developed by the Pittsburgh Naval Reactors to improve utilization of the nation's nuclear fuel resources in light water reactors. The LWBR was operated at Shippingport Atomic Power Station (APS), which was a Department of Energy (DOE) (formerly Atomic Energy Commission)-owned reactor plant. Shippingport APS was the first large-scale, central-station nuclear power plant in the United States and the first plant of such size in the world operated solely to produce electric power. The Shippingport LWBR was operated successfully from 1977 to 1982 at the APS. During the five years of operation, the LWBR generated more than 29,000 effective full power hours (EFPH) of energy. After final shutdown, the 39 core modules of the LWBR were shipped to the Expended Core Facility (ECF) at Naval Reactors Facility at the Idaho National Engineering and Environmental Laboratory (INEEL). At ECF, 12 of the 39 modules were dismantled and about 1000 of more than 17,000 rods were removed from the modules of proof-of-breeding and fuel performance testing. Some of the removed rods were kept at ECF, some were sent to Argonne National Laboratory-West (ANL-W) in Idaho and some to ANL-East in Chicago for a variety of physical, chemical and radiological examinations. All rods and rod sections remaining after the experiments were shipped back to ECF, where modules and loose rods were repackaged in liners for dry storage. In a series of shipments, the liners were transported from ECF to Idaho Nuclear Technology Engineering Center (INTEC), formerly the Idaho Chemical Processing Plant (ICPP). The 47 liners containing the fully-rodded and partially-derodded core modules, the loose rods, and the rod scraps, are now stored in underground dry wells at CPP-749.

Illum, D.B.; Olson, G.L.; McCardell, R.K.

1999-01-01T23:59:59.000Z

69

Electrocoagulation: A Technology for Water Recycle and Wastewater Treatment in Semiconductor Manufacturing  

E-Print Network [OSTI]

Manufacturing Devin Whipple James C. Baygents & James Farrell, Associate Professors Department of Chemical of treating wastewater streams in the semiconductor manufacturing industry. Electrocoagulation involves in particular has the possibility of immediate application at one of Intel's plants. In addition, these both

Fay, Noah

70

Commercial Light Water Reactor Tritium Extraction Facility Geotechnical Summary Report  

SciTech Connect (OSTI)

A geotechnical investigation program has been completed for the Circulating Light Water Reactor - Tritium Extraction Facility (CLWR-TEF) at the Savannah River Site (SRS). The program consisted of reviewing previous geotechnical and geologic data and reports, performing subsurface field exploration, field and laboratory testing and geologic and engineering analyses. The purpose of this investigation was to characterize the subsurface conditions for the CLWR-TEF in terms of subsurface stratigraphy and engineering properties for design and to perform selected engineering analyses. The objectives of the evaluation were to establish site-specific geologic conditions, obtain representative engineering properties of the subsurface and potential fill materials, evaluate the lateral and vertical extent of any soft zones encountered, and perform engineering analyses for slope stability, bearing capacity and settlement, and liquefaction potential. In addition, provide general recommendations for construction and earthwork.

Lewis, M.R.

2000-01-11T23:59:59.000Z

71

Materials Inventory Database for the Light Water Reactor Sustainability Program  

SciTech Connect (OSTI)

Scientific research involves the purchasing, processing, characterization, and fabrication of many sample materials. The history of such materials can become complicated over their lifetime – materials might be cut into pieces or moved to various storage locations, for example. A database with built-in functions to track these kinds of processes facilitates well-organized research. The Material Inventory Database Accounting System (MIDAS) is an easy-to-use tracking and reference system for such items. The Light Water Reactor Sustainability Program (LWRS), which seeks to advance the long-term reliability and productivity of existing nuclear reactors in the United States through multiple research pathways, proposed MIDAS as an efficient way to organize and track all items used in its research. The database software ensures traceability of all items used in research using built-in functions which can emulate actions on tracked items – fabrication, processing, splitting, and more – by performing operations on the data. MIDAS can recover and display the complete history of any item as a simple report. To ensure the database functions suitably for the organization of research, it was developed alongside a specific experiment to test accident tolerant nuclear fuel cladding under the LWRS Advanced Light Water Reactor Nuclear Fuels Pathway. MIDAS kept track of materials used in this experiment from receipt at the laboratory through all processes, test conduct and, ultimately, post-test analysis. By the end of this process, the database proved to be right tool for this program. The database software will help LWRS more efficiently conduct research experiments, from simple characterization tests to in-reactor experiments. Furthermore, MIDAS is a universal tool that any other research team could use to organize their material inventory.

Kazi Ahmed; Shannon M. Bragg-Sitton

2013-08-01T23:59:59.000Z

72

SSL Manufacturing Roadmap  

Broader source: Energy.gov [DOE]

Report detailing DOE Solid-State Lighting Program activities to accelerate manufacturing improvements that reduce costs and enhance the quality of SSL products.

73

Posted 10/18/11 MANUFACTURING ENGINEER  

E-Print Network [OSTI]

manufacturing processes in our Metal Fabrication and Assembly departments. Additional responsibilities includePosted 10/18/11 MANUFACTURING ENGINEER Kenall Manufacturing Gurnee, IL Kenall, a leading manufacturer of advanced lighting solutions for specialized environments, has exceptional opportunities

Heller, Barbara

74

Model for inventory management in valve manufacturing cell at Waters Corporation  

E-Print Network [OSTI]

This thesis addresses the challenges of improving the on-time delivery performance of a high-volume critical part type in a high-product-mix manufacturing facility of valves. Preliminary analysis on the push-type production ...

Yao, Bingxin

2013-01-01T23:59:59.000Z

75

Light Water Reactor Sustainability Constellation Pilot Project FY13 Summary Report  

SciTech Connect (OSTI)

Summary report for Light Water Reactor Sustainability (LWRS) activities related to the R. E. Ginna and Nine Mile Point Unit 1 for FY13.

R. Johansen

2013-09-01T23:59:59.000Z

76

Lansing Board of Water and Light- Hometown Energy Savers Commercial Rebates  

Broader source: Energy.gov [DOE]

Franklin Energy Services and the Lansing Board of Water and Light (LBWL) partner together to offer the Hometown Energy Savers® Commercial and Industrial Energy Efficiency Rebate Program. Eligible...

77

Light Water Reactor Sustainability Constellation Pilot Project FY12 Summary Report  

SciTech Connect (OSTI)

Summary report for Light Water Reactor Sustainability (LWRS) activities related to the R. E. Ginna and Nine Mile Point Unit 1 for FY12.

R. Johansen

2012-09-01T23:59:59.000Z

78

Light-water-reactor safety research program. Quarterly progress report, July to September 1981  

SciTech Connect (OSTI)

Information is presented concerning environmentally assisted cracking in light water reactors; transient fuel response and fission-product release; and clad properties for code verification.

Not Available

1982-02-01T23:59:59.000Z

79

McMinnville Water and Light- Residential Energy Efficiency Rebate Program  

Broader source: Energy.gov [DOE]

McMinnville Water and Light (MWL) offers rebates on energy efficient homes, appliances and equipment to their residential customers. Rebates are valid on refrigerators, freezers, clothes washer,...

80

Physics methods for calculating light water reactor increased performances  

SciTech Connect (OSTI)

The intensive use of light water reactors (LWRs) has induced modification of their characteristics and performances in order to improve fissile material utilization and to increase their availability and flexibility under operation. From the conceptual point of view, adequate methods must be used to calculate core characteristics, taking into account present design requirements, e.g., use of burnable poison, plutonium recycling, etc. From the operational point of view, nuclear plants that have been producing a large percentage of electricity in some countries must adapt their planning to the need of the electrical network and operate on a load-follow basis. Consequently, plant behavior must be predicted and accurately followed in order to improve the plant's capability within safety limits. The Belgonucleaire code system has been developed and extensively validated. It is an accurate, flexible, easily usable, fast-running tool for solving the problems related to LWR technology development. The methods and validation of the two computer codes LWR-WIMS and MICROLUX, which are the main components of the physics calculation system, are explained.

Vandenberg, C.; Charlier, A.

1988-11-01T23:59:59.000Z

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


81

Technologies for Upgrading Light Water Reactor Outlet Temperature  

SciTech Connect (OSTI)

Nuclear energy could potentially be utilized in hybrid energy systems to produce synthetic fuels and feedstocks from indigenous carbon sources such as coal and biomass. First generation nuclear hybrid energy system (NHES) technology will most likely be based on conventional light water reactors (LWRs). However, these LWRs provide thermal energy at temperatures of approximately 300°C, while the desired temperatures for many chemical processes are much higher. In order to realize the benefits of nuclear hybrid energy systems with the current LWR reactor fleets, selection and development of a complimentary temperature upgrading technology is necessary. This paper provides an initial assessment of technologies that may be well suited toward LWR outlet temperature upgrading for powering elevated temperature industrial and chemical processes during periods of off-peak power demand. Chemical heat transformers (CHTs) are a technology with the potential to meet LWR temperature upgrading requirements for NHESs. CHTs utilize chemical heat of reaction to change the temperature at which selected heat sources supply or consume thermal energy. CHTs could directly utilize LWR heat output without intermediate mechanical or electrical power conversion operations and the associated thermodynamic losses. CHT thermal characteristics are determined by selection of the chemical working pair and operating conditions. This paper discusses the chemical working pairs applicable to LWR outlet temperature upgrading and the CHT operating conditions required for providing process heat in NHES applications.

Daniel S. Wendt; Piyush Sabharwall; Vivek Utgikar

2013-07-01T23:59:59.000Z

82

Survey of Worldwide Light Water Reactor Experience with Mixed Uranium-Plutonium Oxide Fuel  

SciTech Connect (OSTI)

The US and the Former Soviet Union (FSU) have recently declared quantities of weapons materials, including weapons-grade (WG) plutonium, excess to strategic requirements. One of the leading candidates for the disposition of excess WG plutonium is irradiation in light water reactors (LWRs) as mixed uranium-plutonium oxide (MOX) fuel. A description of the MOX fuel fabrication techniques in worldwide use is presented. A comprehensive examination of the domestic MOX experience in US reactors obtained during the 1960s, 1970s, and early 1980s is also presented. This experience is described by manufacturer and is also categorized by the reactor facility that irradiated the MOX fuel. A limited summary of the international experience with MOX fuels is also presented. A review of MOX fuel and its performance is conducted in view of the special considerations associated with the disposition of WG plutonium. Based on the available information, it appears that adoption of foreign commercial MOX technology from one of the successful MOX fuel vendors will minimize the technical risks to the overall mission. The conclusion is made that the existing MOX fuel experience base suggests that disposition of excess weapons plutonium through irradiation in LWRs is a technically attractive option.

Cowell, B.S.; Fisher, S.E.

1999-02-01T23:59:59.000Z

83

Chemical and light-stable isotope characteristics of waters from...  

Open Energy Info (EERE)

water; (2) there is a single deep hot water, and the range of chloride concentrations is produced by the water passing through a zone of highly soluble materials (most likely in...

84

Light Water Reactor Sustainability Program Integrated Program Plan  

SciTech Connect (OSTI)

Nuclear power has safely, reliably, and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. Domestic demand for electrical energy is expected to experience a 31% growth from 2009 to 2035. At the same time, most of the currently operating nuclear power plants will begin reaching the end of their initial 20-year extension to their original 40-year operating license for a total of 60 years of operation. Figure E-1 shows projected nuclear energy contribution to the domestic generating capacity. If current operating nuclear power plants do not operate beyond 60 years, the total fraction of generated electrical energy from nuclear power will begin to decline—even with the expected addition of new nuclear generating capacity. The oldest commercial plants in the United States reached their 40th anniversary in 2009. The U.S. Department of Energy Office of Nuclear Energy’s Research and Development Roadmap (Nuclear Energy Roadmap) organizes its activities around four objectives that ensure nuclear energy remains a compelling and viable energy option for the United States. The four objectives are as follows: (1) develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the life of the current reactors; (2) develop improvements in the affordability of new reactors to enable nuclear energy to help meet the Administration’s energy security and climate change goals; (3) develop sustainable nuclear fuel cycles; and (4) understand and minimize the risks of nuclear proliferation and terrorism. The Light Water Reactor Sustainability (LWRS) Program is the primary programmatic activity that addresses Objective 1. This document summarizes the LWRS Program’s plans.

McCarthy, Kathryn A. [INL; Busby, Jeremy [ORNL; Hallbert, Bruce [INL; Bragg-Sitton, Shannon [INL; Smith, Curtis [INL; Barnard, Cathy [INL

2014-04-01T23:59:59.000Z

85

Light Water Reactor Sustainability Program Integrated Program Plan  

SciTech Connect (OSTI)

Nuclear power has safely, reliably, and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. Domestic demand for electrical energy is expected to experience a 31% growth from 2009 to 2035. At the same time, most of the currently operating nuclear power plants will begin reaching the end of their initial 20-year extension to their original 40-year operating license for a total of 60 years of operation. Figure E-1 shows projected nuclear energy contribution to the domestic generating capacity. If current operating nuclear power plants do not operate beyond 60 years, the total fraction of generated electrical energy from nuclear power will begin to decline - even with the expected addition of new nuclear generating capacity. The oldest commercial plants in the United States reached their 40th anniversary in 2009. The U.S. Department of Energy Office of Nuclear Energy's Research and Development Roadmap (Nuclear Energy Roadmap) organizes its activities around four objectives that ensure nuclear energy remains a compelling and viable energy option for the United States. The four objectives are as follows: (1) develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the life of the current reactors; (2) develop improvements in the affordability of new reactors to enable nuclear energy to help meet the Administration's energy security and climate change goals; (3) develop sustainable nuclear fuel cycles; and (4) understand and minimize the risks of nuclear proliferation and terrorism. The Light Water Reactor Sustainability (LWRS) Program is the primary programmatic activity that addresses Objective 1. This document summarizes the LWRS Program's plans.

George Griffith; Robert Youngblood; Jeremy Busby; Bruce Hallbert; Cathy Barnard; Kathryn McCarthy

2012-01-01T23:59:59.000Z

86

Light Water Reactor Sustainability Program Integrated Program Plan  

SciTech Connect (OSTI)

Nuclear power has safely, reliably, and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. Domestic demand for electrical energy is expected to experience a 31% growth from 2009 to 2035. At the same time, most of the currently operating nuclear power plants will begin reaching the end of their initial 20-year extension to their original 40-year operating license for a total of 60 years of operation. Figure E-1 shows projected nuclear energy contribution to the domestic generating capacity. If current operating nuclear power plants do not operate beyond 60 years, the total fraction of generated electrical energy from nuclear power will begin to decline—even with the expected addition of new nuclear generating capacity. The oldest commercial plants in the United States reached their 40th anniversary in 2009. The U.S. Department of Energy Office of Nuclear Energy’s Research and Development Roadmap (Nuclear Energy Roadmap) organizes its activities around four objectives that ensure nuclear energy remains a compelling and viable energy option for the United States. The four objectives are as follows: (1) develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the life of the current reactors; (2) develop improvements in the affordability of new reactors to enable nuclear energy to help meet the Administration’s energy security and climate change goals; (3) develop sustainable nuclear fuel cycles; and (4) understand and minimize the risks of nuclear proliferation and terrorism. The Light Water Reactor Sustainability (LWRS) Program is the primary programmatic activity that addresses Objective 1. This document summarizes the LWRS Program’s plans.

Kathryn McCarthy; Jeremy Busby; Bruce Hallbert; Shannon Bragg-Sitton; Curtis Smith; Cathy Barnard

2013-04-01T23:59:59.000Z

87

High Efficiency Integrated Space Conditioning, Water Heating and Air Distribution System for HUD-Code Manufactured Housing  

SciTech Connect (OSTI)

Recognizing the need for new space conditioning and water heating systems for manufactured housing, DeLima Associates assembled a team to develop a space conditioning system that would enhance comfort conditions while also reducing energy usage at the systems level. The product, Comboflair® was defined as a result of a needs analysis of project sponsors and industry stakeholders. An integrated system would be developed that would combine a packaged airconditioning system with a small-duct, high-velocity air distribution system. In its basic configuration, the source for space heating would be a gas water heater. The complete system would be installed at the manufactured home factory and would require no site installation work at the homesite as is now required with conventional split-system air conditioners. Several prototypes were fabricated and tested before a field test unit was completed in October 2005. The Comboflair® system, complete with ductwork, was installed in a 1,984 square feet, double-wide manufactured home built by Palm Harbor Homes in Austin, TX. After the home was transported and installed at a Palm Harbor dealer lot in Austin, TX, a data acquisition system was installed for remote data collection. Over 60 parameters were continuously monitored and measurements were transmitted to a remote site every 15 minutes for performance analysis. The Comboflair® system was field tested from February 2006 until April 2007. The cooling system performed in accordance with the design specifications. The heating system initially could not provide the needed capacity at peak heating conditions until the water heater was replaced with a higher capacity standard water heater. All system comfort goals were then met. As a result of field testing, we have identified improvements to be made to specific components for incorporation into production models. The Comboflair® system will be manufactured by Unico, Inc. at their new production facility in St. Louis, MO. The product will be initially launched in the hot-humid climates of the southern U.S.

Henry DeLima; Joe Akin; Joseph Pietsch

2008-09-14T23:59:59.000Z

88

Ceramic filter manufacturing in Northern Ghana : water storage and quality control  

E-Print Network [OSTI]

In 2009, Pure Home Water (PHW), a Ghana based non-profit organization working to provide affordable and safe drinking water to people in the Northern Region of Ghana, began the construction of a ceramic pot filter (CPF) ...

Kleiman, Shanti Lisa

2011-01-01T23:59:59.000Z

89

Cross section generation strategy for high conversion light water reactors  

E-Print Network [OSTI]

High conversion water reactors (HCWR), such as the Resource-renewable Boiling Water Reactor (RBWR), are being designed with axial heterogeneity of alternating fissile and blanket zones to achieve a conversion ratio of ...

Herman, Bryan R. (Bryan Robert)

2011-01-01T23:59:59.000Z

90

Sustained Recycle in Light Water and Sodium-Cooled Reactors  

SciTech Connect (OSTI)

From a physics standpoint, it is feasible to sustain recycle of used fuel in either thermal or fast reactors. This paper examines multi-recycle potential performance by considering three recycling approaches and calculating several fuel cycle parameters, including heat, gamma, and neutron emission of fresh fuel; radiotoxicity of waste; and uranium utilization. The first recycle approach is homogeneous mixed oxide (MOX) fuel assemblies in a light water reactor (LWR). The transuranic portion of the MOX was varied among Pu, NpPu, NpPuAm, or all-TRU. (All-TRU means all isotopes through Cf-252.) The Pu case was allowed to go to 10% Pu in fresh fuel, but when the minor actinides were included, the transuranic enrichment was kept below 8% to satisfy the expected void reactivity constraint. The uranium portion of the MOX was enriched uranium. That enrichment was increased (to as much as 6.5%) to keep the fuel critical for a typical LWR irradiation. The second approach uses heterogeneous inert matrix fuel (IMF) assemblies in an LWR - a mix of IMF and traditional UOX pins. The uranium-free IMF fuel pins were Pu, NpPu, NpPuAm, or all-TRU. The UOX pins were limited to 4.95% U-235 enrichment. The number of IMF pins was set so that the amount of TRU in discharged fuel from recycle N (from both IMF and UOX pins) was made into the new IMF pins for recycle N+1. Up to 60 of the 264 pins in a fuel assembly were IMF. The assembly-average TRU content was 1-6%. The third approach uses fast reactor oxide fuel in a sodium-cooled fast reactor with transuranic conversion ratio of 0.50 and 1.00. The transuranic conversion ratio is the production of transuranics divided by destruction of transuranics. The FR at CR=0.50 is similar to the CR for the MOX case. The fast reactor cases had a transuranic content of 33-38%, higher than IMF or MOX.

Steven J. Piet; Samuel E. Bays; Michael A. Pope; Gilles J. Youinou

2010-11-01T23:59:59.000Z

91

advanced light water: Topics by E-print Network  

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

SM top properties such as the cross-section has been suggested to give a handle for this stealth stop' scenario. We present an estimate of the potential impact a light stop may...

92

Engineering Research Center for Environmentally Benign Semiconductor Manufacturing Water Use and Reuse in  

E-Print Network [OSTI]

Phase 4 Water Usage in the US Fabs #12;Engineering Research Center for Environmentally Benign, and energy usage as we move to nano-scale · Solution: Development of new ESH-friendly nano in Water and Energy Usage #12;Engineering Research Center for Environmentally Benign Semiconductor

Cushing, Jim. M.

93

The impact of passive safety systems on desirability of advanced light water reactors  

E-Print Network [OSTI]

This work investigates whether the advanced light water reactor designs with passive safety systems are more desirable than advanced reactor designs with active safety systems from the point of view of uncertainty in the ...

Eul, Ryan C

2006-01-01T23:59:59.000Z

94

Memphis Light, Gas and Water (Electric)- Commercial Efficiency Advice and Incentives Program  

Broader source: Energy.gov [DOE]

Memphis Light, Gas and Water (MLGW), in partnership with the Tennessee Valley Authority (TVA), offers a variety of energy efficient incentives to non-residential customers. The program provides...

95

E-Print Network 3.0 - advanced light-water nuclear Sample Search...  

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

by Explorit Topic List Advanced Search Sample search results for: advanced light-water nuclear Page: << < 1 2 3 4 5 > >> 1 1 Managed by UT-Battelle for the U.S. Department...

96

INL/EXT-14-33257 Light Water Reactor Sustainability Program  

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

57 Light Water Reactor Sustainability Program 3D J-Integral Capability in Grizzly September 2014 DOE Office of Nuclear Energy DISCLAIMER This information was prepared as an account...

97

Assessment of light water reactor power plant cost and ultra-acceleration depreciation financing  

E-Print Network [OSTI]

Although in many regions of the U.S. the least expensive electricity is generated from light-water reactor (LWR) plants, the fixed (capital plus operation and maintenance) cost has increased to the level where the cost ...

El-Magboub, Sadek Abdulhafid.

98

McMinnville Water and Light- Commercial Energy Efficiency Rebate Programs  

Broader source: Energy.gov [DOE]

McMinnville Water and Light Company offers a variety of rebates for commercial and industrial customers to make energy efficient improvements to eligible facilities. MW&L offers rebates in...

99

EIS-0288: Production of Tritium in a Commercial Light Water Reactor  

Broader source: Energy.gov [DOE]

This Environmental Impact Statement for the Production of Tritium in a Commercial Light Water Reactor (CLWR EIS) evaluates the environmental impacts associated with producing tritium at one or more...

100

Visible Light Water Splitting Using Dye-Sensitized Oxide Semiconductors  

E-Print Network [OSTI]

- ical energy in the form of fuels. Hydrogen is a key solar fuel because it can be used directly. This Account describes our approach to two problems in solar water splitting: the organization of molecules in photochemistry.1,2 Efficient photocatalytic water-splitting systems could have practical value for solar energy

Note: This page contains sample records for the topic "lighting manufacturing water" 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

Fatigue and environmentally assisted cracking in light water reactors  

SciTech Connect (OSTI)

Fatigue and stress corrosion cracking (SCC) for low-alloy steel used in piping and in steam generator and reactor pressure vessels have been investigated. Fatigue data were obtained on medium-sulfur-content A533-Gr B and A106-Gr B steels in high-purity (HP) deoxygenated water, in simulated pressurized water reactor water, and in air. Analytical studies focused on the behavior of carbon steels in boiling water reactor (BWR) environments. Crack-growth rates of composite fracture-mechanics specimens of A533-Gr B/Inconel-182/Inconel-600 (plated with nickel) and homogeneous specimens of A533-Gr B steel were determined under small-amplitude cyclic loading in HP water with {approx}300 pbb dissolved oxygen. Radiation-induced segregation and irradiation-assisted SCC of Type 304 SS after accumulation of relatively high fluence also have been investigated. Microchemical and microstructural changes in HP and commercial-purity Type 304 SS specimens from control-blade absorber tubes used in two operating BWRs were studied by Auger electron spectroscopy and scanning electron microscopy, and slow-strain-rate tensile tests were conducted on tubular specimens in air and in simulated BWR water at 289{degrees}C.

Kassner, T.F.; Ruther, W.E.; Chung, H.M.; Hicks, P.D.; Hins, A.G.; Park, J.Y.; Shack, W.J.

1992-03-01T23:59:59.000Z

102

Low cost manufacturing of light trapping features on multi-crystalline silicon solar cells : jet etching method and cost analysis  

E-Print Network [OSTI]

An experimental study was conducted in order to determine low cost methods to improve the light trapping ability of multi-crystalline solar cells. We focused our work on improving current wet etching methods to achieve the ...

Berrada Sounni, Amine

2010-01-01T23:59:59.000Z

103

Materials science division light-water-reactor safety research program. Quarterly progress report, October - December 1981  

SciTech Connect (OSTI)

This progress report summarizes the Argonne National Laboratory work performed during October, November, and December 1981 on water-reactor-safety problems. The research and development areas covered are environmentally assisted cracking in light water reactors, transient fuel response and fission-product release, and clad properties for code verification.

Not Available

1982-05-01T23:59:59.000Z

104

Light-water-reactor safety research program. Quarterly progress report, April-June 1981  

SciTech Connect (OSTI)

This progress report summarizes the Argonne National Laboratory work performed during April, May, and June 1981 on water-reactor-safety problems. The research and development areas covered are transient fuel response and fission-product release and environmentally assisted cracking in light water reactors.

Not Available

1981-01-01T23:59:59.000Z

105

Impact of Pilot Light Modeling on the Predicted Annual Performance of Residential Gas Water Heaters: Preprint  

SciTech Connect (OSTI)

Modeling residential water heaters with dynamic simulation models can provide accurate estimates of their annual energy consumption, if the units? characteristics and use conditions are known. Most gas storage water heaters (GSWHs) include a standing pilot light. It is generally assumed that the pilot light energy will help make up standby losses and have no impact on the predicted annual energy consumption. However, that is not always the case. The gas input rate and conversion efficiency of a pilot light for a GSWH were determined from laboratory data. The data were used in simulations of a typical GSWH with and without a pilot light, for two cases: 1) the GSWH is used alone; and 2) the GSWH is the second tank in a solar water heating (SWH) system. The sensitivity of wasted pilot light energy to annual hot water use, climate, and installation location was examined. The GSWH used alone in unconditioned space in a hot climate had a slight increase in energy consumption. The GSWH with a pilot light used as a backup to an SWH used up to 80% more auxiliary energy than one without in hot, sunny locations, from increased tank losses.

Maguire, J.; Burch, J.

2013-08-01T23:59:59.000Z

106

Superior Water, Light and Power Co | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of InspectorConcentrating SolarElectric Coop, Inc Place: MissouriPrograms |IllinoisCPA CDC1 LLCSunergieWater,

107

Albany Water Gas & Light Comm | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of Inspector GeneralDepartmentAUDIT REPORTOpenWende NewSowitecAWSAgri-Energy LLCAir(EC-LEDS) | Open EnergyWater

108

Moose Lake Water & Light Comm | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of InspectorConcentrating Solar Powerstories onFocus Area EnergyMohawk MunicipalMontvale, New Jersey:Water &

109

Two Rivers Water & Light | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia:FAQ < RAPID Jump to:Seadov Pty LtdSteen,LtdInformationTulsa,Tuscarawas County,Florida:Creeks,Water &

110

Light-water-reactor safety materials engineering research programs. Quarterly progress report, January-March 1985. Volume 1  

SciTech Connect (OSTI)

This progress report summarizes work performed by the Materials Science and Technology Division of Argonne National Laboratory during January, February, and March 1985 on water reactor safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light-Water Reactors and Long-Term Embrittlement of Cast Duplex Stainless Steels in Light-Water-Reactor Systems. 42 refs.

Not Available

1986-03-01T23:59:59.000Z

111

Light-water-reactor safety materials engineering research programs. Volume 3. Quarterly progress report, October-December 1984  

SciTech Connect (OSTI)

This progress report summarizes work performed by the Materials Science and Technology Division of Argonne National Laboratory during October, November, and December 1984 on water reactor safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light-Water Reactors and Long-Term Embrittlement of Cast Duplex Stainless Steels in Light-Water-Reactor Systems.

Not Available

1985-10-01T23:59:59.000Z

112

Environmentally assisted cracking of light-water reactor materials  

SciTech Connect (OSTI)

Environmentally assisted cracking (EAC) of lightwater reactor (LWR) materials has affected nuclear reactors from the very introduction of the technology. Corrosion problems have afflicted steam generators from the very introduction of pressurized water reactor (PWR) technology. Shippingport, the first commercial PWR operated in the United States, developed leaking cracks in two Type 304 stainless steel (SS) steam generator tubes as early as 1957, after only 150 h of operation. Stress corrosion cracks were observed in the heat-affected zones of welds in austenitic SS piping and associated components in boiling-water reactors (BRWs) as early as 1965. The degradation of steam generator tubing in PWRs and the stress corrosion cracking (SCC) of austenitic SS piping in BWRs have been the most visible and most expensive examples of EAC in LWRs, and the repair and replacement of steam generators and recirculation piping has cost hundreds of millions of dollars. However, other problems associated with the effects of the environment on reactor structures and components am important concerns in operating plants and for extended reactor lifetimes. Cast duplex austenitic-ferritic SSs are used extensively in the nuclear industry to fabricate pump casings and valve bodies for LWRs and primary coolant piping in many PWRs. Embrittlement of the ferrite phase in cast duplex SS may occur after 10 to 20 years at reactor operating temperatures, which could influence the mechanical response and integrity of pressure boundary components during high strain-rate loading (e.g., seismic events). The problem is of most concern in PWRs where slightly higher temperatures are typical and cast SS piping is widely used.

Chopra, O.K.; Chung, H.M.; Kassner, T.F.; Shack, W.J.

1996-02-01T23:59:59.000Z

113

Materials Science Division light-water-reactor safety research program. Quarterly progress report, January-March 1982  

SciTech Connect (OSTI)

Information is presented concerning environmentally assisted cracking in light water reactors; transient fuel response and fission product release; and clad properties for code verification.

Shack, W.J.; Rest, J.; Kassner, T.F.

1982-10-01T23:59:59.000Z

114

A comparison of the heat transfer capabilities of two manufacturing methods for high heat flux water-cooled devices  

SciTech Connect (OSTI)

An experimental program was undertaken to compare the heat transfer characteristics of water-cooled copper devices manufactured via conventional drilled passage construction and via a technique whereby molten copper is cast over a network of preformed cooling tubes. Two similar test blocks were constructed; one using the drilled passage technique, the other via casting copper over Monel pipe. Each test block was mounted in a vacuum system and heated uniformly on the top surface using a swept electron beam. From the measured absorbed powers and resultant temperatures, an overall heat transfer coefficient was calculated. The maximum heat transfer coefficient calculated for the case of the drilled passage test block was 2534 Btu/hr/ft/sup 2///sup 0/F. This corresponded to an absorbed power density of 320 w/cm/sup 2/ and resulted in a maximum recorded copper temperature of 346/sup 0/C. Corresponding figures for the cast test block were 363 Btu/hr/ft/sup 2///sup 0/F, 91 w/cm/sup 2/, and 453/sup 0/C.

McKoon, R.H.

1986-10-01T23:59:59.000Z

115

Light Water Reactor Sustainability Constellation Pilot Project FY11 Summary Report  

SciTech Connect (OSTI)

Summary report for Fiscal Year 2011 activities associated with the Constellation Pilot Project. The project is a joint effor between Constellation Nuclear Energy Group (CENG), EPRI, and the DOE Light Water Reactor Sustainability Program. The project utilizes two CENG reactor stations: R.E. Ginna and Nine Point Unit 1. Included in the report are activities associate with reactor internals and concrete containments.

R. Johansen

2011-09-01T23:59:59.000Z

116

Light Water Reactor Safety Research Program. Semiannual report, April-September 1982  

SciTech Connect (OSTI)

This report documents progress made in Light Water Reactor Safety research conducted by Division 6441 in the period from April 1982 to September 1982. The programs conducted under investigation include Core Concrete Interactions, Core Melt-Coolant Interactions, Containment Emergency Sump Performance, the Hydrogen Program, and Combustible Gas in Containment Program. 50 references.

Berman, M.

1983-10-01T23:59:59.000Z

117

Light water reactor safety research program. Volume 12: quarterly report, Apr-Jun 79  

SciTech Connect (OSTI)

This report summarizes the progress of the Light Water Reactor Safety Research Program during the 2nd quarter of 1979. Specifically, the report summarizes progress in five major areas of research. They are: (1) the molten core/concrete interactions study; (2) steam explosion research phenomena; (3) statistical LOCA analysis; (4) UHI model development; (5) two-phase jet loads.

Berman, M.

1980-05-01T23:59:59.000Z

118

The use of reduced-moderation light water reactors for transuranic isotope burning in thorium fuel  

E-Print Network [OSTI]

Light water reactors (LWRs) are the world’s dominant nuclear reactor system. Uranium (U)-fuelled LWRs produce long-lived transuranic (TRU) isotopes. TRUs can be recycled in LWRs or fast reactors. The thermal neutron spectrum in LWRs is less suitable...

Lindley, Benjamin A.

2015-02-03T23:59:59.000Z

119

Materials Degradation in Light Water Reactors: Life After 60,???  

SciTech Connect (OSTI)

Nuclear reactors present a very harsh environment for components service. Components within a reactor core must tolerate high temperature water, stress, vibration, and an intense neutron field. Degradation of materials in this environment can lead to reduced performance, and in some cases, sudden failure. A recent EPRI-led study interviewed 47 US nuclear utility executives to gauge perspectives on long-term operation of nuclear reactors. Nearly 90% indicated that extensions of reactor lifetimes to beyond 60 years were likely. When polled on the most challenging issues facing further life extension, two-thirds cited plant reliability as the key issue with materials aging and cable/piping as the top concerns for plant reliability. Materials degradation within a nuclear power plant is very complex. There are many different types of materials within the reactor itself: over 25 different metal alloys can be found with can be found within the primary and secondary systems, not to mention the concrete containment vessel, instrumentation and control, and other support facilities. When this diverse set of materials is placed in the complex and harsh environment coupled with load, degradation over an extended life is indeed quite complicated. To address this issue, the USNRC has developed a Progressive Materials Degradation Approach (NUREG/CR-6923). This approach is intended to develop a foundation for appropriate actions to keep materials degradation from adversely impacting component integrity and safety and identify materials and locations where degradation can reasonably be expected in the future. Clearly, materials degradation will impact reactor reliability, availability, and potentially, safe operation. Routine surveillance and component replacement can mitigate these factors, although failures still occur. With reactor life extensions to 60 years or beyond or power uprates, many components must tolerate the reactor environment for even longer times. This may increase susceptibility for most components and may introduce new degradation modes. While all components (except perhaps the reactor vessel) can be replaced, it may not be economically favorable. Therefore, understanding, controlling, and mitigating materials degradation processes are key priorities for reactor operation, power uprate considerations, and life extensions. This document is written to give an overview of some of the materials degradation issues that may be key for extend reactor service life. A detailed description of all the possible forms of degradation is beyond the scope of this short paper and has already been described in other documents (for example, the NUREG/CR-6923). The intent of this document is to present an overview of current materials issues in the existing reactor fleet and a brief analysis of the potential impact of extending life beyond 60 years. Discussion is presented in six distinct areas: (1) Reactor pressure vessel; (2) Reactor core and primary systems; (3) Reactor secondary systems; (4) Weldments; (5) Concrete; and (6) Modeling and simulations. Following each of these areas, some research thrust directions to help identify and mitigate lifetime extension issues are proposed. Note that while piping and cabling are important for extended service, these components are discussed in more depth in a separate paper. Further, the materials degradation issues associated with fuel cladding and fuel assemblies are not discussed in this section as these components are replaced periodically and will not influence the overall lifetime of the reactor.

Busby, Jeremy T [ORNL; Nanstad, Randy K [ORNL; Stoller, Roger E [ORNL; Feng, Zhili [ORNL; Naus, Dan J [ORNL

2008-04-01T23:59:59.000Z

120

Thermophysical properties of saturated light and heavy water for advanced neutron source applications  

SciTech Connect (OSTI)

The Advanced Neutron Source is an experimental facility being developed by Oak Ridge National Laboratory. As a new nuclear fission research reactor of unprecedented flux, the Advanced Neutron Source Reactor will provide the most intense steady-state beams of neutrons in the world. The high heat fluxes generated in the reactor [303 MW(t) with an average power density of 4.5 MW/L] will be accommodated by a flow of heavy water through the core at high velocities. In support of this experimental and analytical effort, a reliable, highly accurate, and uniform source of thermodynamic and transport property correlations for saturated light and heavy water were developed. In order to attain high accuracy in the correlations, the range of these correlations was limited to the proposed Advanced Neutron Source Reactor's nominal operating conditions. The temperature and corresponding saturation pressure ranges used for light water were 20--300[degrees]C and 0.0025--8.5 MPa, respectively, while those for heavy water were 50--250[degrees]C and 0.012--3.9 MPa. Deviations between the correlation predictions and data from the various sources did not exceed 1.0%. Light water vapor density was the only exception, with an error of 1.76%. The physical property package consists of analytical correlations, SAS codes, and FORTRAN subroutines incorporating these correlations, as well as an interactive, easy-to-use program entitled QuikProp.

Crabtree, A.; Siman-Tov, M.

1993-05-01T23:59:59.000Z

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


121

Thermophysical properties of saturated light and heavy water for Advanced Neutron Source applications  

SciTech Connect (OSTI)

The Advanced Neutron Source is an experimental facility being developed by Oak Ridge National Laboratory. As a new nuclear fission research reactor of unprecedented flux, the Advanced Neutron Source Reactor will provide the most intense steady-state beams of neutrons in the world. The high heat fluxes generated in the reactor [303 MW(t) with an average power density of 4.5 MW/L] will be accommodated by a flow of heavy water through the core at high velocities. In support of this experimental and analytical effort, a reliable, highly accurate, and uniform source of thermodynamic and transport property correlations for saturated light and heavy water were developed. In order to attain high accuracy in the correlations, the range of these correlations was limited to the proposed Advanced Neutron Source Reactor`s nominal operating conditions. The temperature and corresponding saturation pressure ranges used for light water were 20--300{degrees}C and 0.0025--8.5 MPa, respectively, while those for heavy water were 50--250{degrees}C and 0.012--3.9 MPa. Deviations between the correlation predictions and data from the various sources did not exceed 1.0%. Light water vapor density was the only exception, with an error of 1.76%. The physical property package consists of analytical correlations, SAS codes, and FORTRAN subroutines incorporating these correlations, as well as an interactive, easy-to-use program entitled QuikProp.

Crabtree, A.; Siman-Tov, M.

1993-05-01T23:59:59.000Z

122

Life cycle assessment of buildings technologies: High-efficiency commercial lighting and residential water heaters  

SciTech Connect (OSTI)

In this study the life cycle emissions and energy use are estimated for two types of energy technologies. The first technology evaluated is the sulfur lamp, a high-efficiency lighting system under development by the US Department of Energy (DOE) and Fusion Lighting, the inventor of the technology. The sulfur lamp is compared with conventional metal halide high-intensity discharge lighting systems. The second technology comparison is between standard-efficiency and high-efficiency gas and electric water heaters. In both cases the life cycle energy use and emissions are presented for the production of an equivalent level of service by each of the technologies. For both analyses, the energy use and emissions from the operation of the equipment are found to dominate the life cycle profile. The life cycle emissions for the water heating systems are much more complicated. The four systems compared include standard- and high-efficiency gas water heaters, standard electric resistance water heaters, and heat pump water heaters.

Freeman, S.L.

1997-01-01T23:59:59.000Z

123

Search for Free Decay of Negative Pions in Water and Light Materials  

E-Print Network [OSTI]

We report on a search for the free decay component of pi- stopped in water and light materials. A non-zero value of this would be an indication of anomalous nu_e contamination to the nu_e and nu_mu_bar production at stopped-pion neutrino facilities. No free decay component of pi- was observed in water, Beryllium, and Aluminum, for which upper limits were established at 8.2E-4, 3.2E-3, and 7.7E-3, respectively.

T. Numao; Yu. I. Davydov; J-M. Poutissou; T. C. Awes; V. Cianciolo; S. Berridge; W. Bugg; Yu. Efremenko; R. Gearhart; S. Ovchinnikov

2006-05-30T23:59:59.000Z

124

Meeting Summary Advanced Light Water Reactor Fuels Industry Meeting Washington DC October 27 - 28, 2011  

SciTech Connect (OSTI)

The Advanced LWR Fuel Working Group first met in November of 2010 with the objective of looking 20 years ahead to the role that advanced fuels could play in improving light water reactor technology, such as waste reduction and economics. When the group met again in March 2011, the Fukushima incident was still unfolding. After the March meeting, the focus of the program changed to determining what we could do in the near term to improve fuel accident tolerance. Any discussion of fuels with enhanced accident tolerance will likely need to consider an advanced light water reactor with enhanced accident tolerance, along with the fuel. The Advanced LWR Fuel Working Group met in Washington D.C. on October 72-18, 2011 to continue discussions on this important topic.

Not Listed

2011-11-01T23:59:59.000Z

125

Establishment of a Hub for the Light Water Reactor Sustainability Online Monitoring Community  

SciTech Connect (OSTI)

Implementation of online monitoring and prognostics in existing U.S. nuclear power plants will involve coordinating the efforts of national laboratories, utilities, universities, and private companies. Internet-based collaborative work environments provide necessary communication tools to facilitate interaction between geographically diverse participants. Available technologies were considered, and a collaborative workspace was established at INL as a hub for the light water reactor sustainability online monitoring community.

Nancy J. Lybeck; Magdy S. Tawfik; Binh T. Pham

2011-08-01T23:59:59.000Z

126

Fuel assembly for the production of tritium in light water reactors  

DOE Patents [OSTI]

A nuclear fuel assembly is described for producing tritium in a light water moderated reactor. The assembly consists of two intermeshing arrays of subassemblies. The first subassemblies comprise concentric annular elements of an outer containment tube, an annular target element, an annular fuel element, and an inner neutron spectrums shifting rod. The second subassemblies comprise an outer containment tube and an inner rod of either fuel, target, or neutron spectrum shifting neutral.

Cawley, William E. (Richland, WA); Trapp, Turner J. (Richland, WA)

1985-01-01T23:59:59.000Z

127

Fuel assembly for the production of tritium in light water reactors  

DOE Patents [OSTI]

A nuclear fuel assembly is described for producing tritium in a light water moderated reactor. The assembly consists of two intermeshing arrays of subassemblies. The first subassemblies comprise concentric annular elements of an outer containment tube, an annular target element, an annular fuel element, and an inner neutron spectrums shifting rod. The second subassemblies comprise an outer containment tube and an inner rod of either fuel, target, or neutron spectrum shifting neutral.

Cawley, W.E.; Trapp, T.J.

1983-06-10T23:59:59.000Z

128

Overview of the US Department of Energy Light Water Reactor Sustainability Program  

SciTech Connect (OSTI)

The US Department of Energy Light Water Reactor Sustainability Program is focused on the long-term operation of US commercial power plants. It encompasses two facets of long-term operation: (1) manage the aging of plant systems, structures, and components so that nuclear power plant lifetimes can be extended and the plants can continue to operate safely, efficiently, and economically; and (2) provide science-based solutions to the nuclear industry that support implementation of performance improvement technologies. An important aspect of the Light Water Reactor Sustainability Program is partnering with industry and the Nuclear Regulatory Commission to support and conduct the long-term research needed to inform major component refurbishment and replacement strategies, performance enhancements, plant license extensions, and age-related regulatory oversight decisions. The Department of Energy research, development, and demonstration role focuses on aging phenomena and issues that require long-term research and/or unique Department of Energy laboratory expertise and facilities and are applicable to all operating reactors. This paper gives an overview of the Department of Energy Light Water Reactor Sustainability Program, including vision, goals, and major deliverables.

K. A. McCarthy; D. L. Williams; R. Reister

2012-05-01T23:59:59.000Z

129

End-of-life destructive examination of light water breeder reactor fuel rods (LWBR Development Program)  

SciTech Connect (OSTI)

Destructive examination of 12 representative Light Water Breeder Reactor fuel rods was performed following successful operation in the Shippingport Atomic Power Station for 29,047 effective full power hours, about five years. Light Water Breeder Reactor fuel rods were unique in that the thorium oxide and uranium-233 oxide fuel was contained within Zircaloy-4 cladding. Destructive examinations included analysis of released fission gas; chemical analysis of the fuel to determine depletion, iodine, and cesium levels; chemical analysis of the cladding to determine hydrogen, iodine, and cesium levels; metallographic examination of the cladding, fuel, and other rod components to determine microstructural features and cladding corrosion features; and tensile testing of the irradiated cladding to determine mechanical strength. The examinations confirmed that Light Water Breeder Reactor fuel rod performance was excellent. No evidence of fuel rod failure was observed, and the fuel operating temperature was low (below 2580/sup 0/F at which an increased percentage of fission gas is released). 21 refs., 80 figs., 20 tabs.

Richardson, K.D.

1987-10-01T23:59:59.000Z

130

Gas-liquid-liquid equilibria in mixtures of water, light gases, and hydrocarbons  

SciTech Connect (OSTI)

Phase equilibrium in mixtures of water + light gases and water + heavy hydrocarbons has been investigated with the development of new local composition theory, new equations of state, and new experimental data. The preferential segregation and orientation of molecules due to different energies of molecular interaction has been simulated with square well molecules. Extensive simulation has been made for pure square well fluids and mixtures to find the local composition at wide ranges of states. A theory of local composition has been developed and an equation of state has been obtained for square well fluids. The new local composition theory has been embedded in several equations of state. The pressure of water is decoupled into a polar pressure and non-polar pressure according to the molecular model of water of Jorgensen et al. The polar pressure of water is combined with the BACK equation for the general description of polar fluids and their mixtures. Being derived from the steam table, the Augmented BACK equation is particularly suited for mixtures of water + non-polar substances such as the hydrocarbons. The hydrophobic character of the hydrocarbons had made their mixtures with water a special challenge. A new group contribution equation of state is developed to describe phase equilibrium and volumetric behavior of fluids while requiring only to know the molecular structure of the components. 15 refs., 1 fig.

Chao, K.C.

1990-01-01T23:59:59.000Z

131

Designing of a prototype heat-sealer to manufacture solar water sterilization pouches for use in developing nations  

E-Print Network [OSTI]

Water purification proves to be a difficult task in many developing nations. The SODIS (SOlar water DISinfection) process is a method which improves the microbiological quality of water making it safer for drinking and ...

Quinlan, Saundra S

2005-01-01T23:59:59.000Z

132

Feasibility Study of Supercritical Light Water Cooled Fast Reactors for Actinide Burning and Electric Power Production  

SciTech Connect (OSTI)

The use of supercritical temperature and pressure light water as the coolant in a direct-cycle nuclear reactor offers potential for considerable plant simplification and consequent capital and O&M cost reduction compared with current light water reactor (LWR) designs. Also, given the thermodynamic conditions of the coolant at the core outlet (i.e. temperature and pressure beyond the water critical point), very high thermal efficiencies of the power conversion cycle are possible (i.e. up to 46%). Because no change of phase occurs in the core, the need for steam separators and dryers as well as for BWR-type recirculation pumps is eliminated, which, for a given reactor power, results in a substantially shorter reactor vessel than the current BWRs. Furthermore, in a direct cycle the steam generators are not needed. If a tight fuel rod lattice is adopted, it is possible to significantly reduce the neutron moderation and attain fast neutron energy spectrum conditions. In this project a supercritical water reactor concept with a simple, blanket-free, pancake-shaped core will be developed. This type of core can make use of either fertile or fertile-free fuel and retain the hard spectrum to effectively burn plutonium and minor actinides from LWR spent fuel while efficiently generating electricity.

Mac Donald, Philip Elsworth; Buongiorno, Jacopo; Davis, Cliff Bybee; Weaver, Kevan Dean

2002-01-01T23:59:59.000Z

133

Northwest Energy Efficient Manufactured Housing Program: High Performance Manufactured Home Prototyping and Construction Development  

SciTech Connect (OSTI)

The Building America Partnership for Improved Residential Construction, the Bonneville Power Administration (BPA), and Northwest Energy Works (NEW), the current Northwest Energy Efficient Manufactured Housing Program (NEEM) administrator, have been collaborating to conduct research on new specifications that would improve on the energy requirements of a NEEM home. In its role as administrator, NEW administers the technical specs, performs research and engineering analysis, implements ongoing construction quality management procedures, and maintains a central database with home tracking. This project prototyped and assessed the performances of cost-effective high performance building assemblies and mechanical systems that are not commonly deployed in the manufacturing setting. The package of measures is able to reduce energy used for space conditioning, water heating and lighting by 50 percent over typical manufactured homes produced in the northwest.

Hewes, T.; Peeks, B.

2013-11-01T23:59:59.000Z

134

Technology Solutions for New Manufactured Homes: Idaho, Oregon, and Washington Manufactured Home Builders (Fact Sheet)  

SciTech Connect (OSTI)

The Building America Partnership for Improved Residential Construction, the Bonneville Power Administration (BPA), and Northwest Energy Works (NEW), the current Northwest Energy Efficient Manufactured Housing Program (NEEM) administrator, have been collaborating to conduct research on new specifications that would improve on the energy requirements of a NEEM home. In its role as administrator, NEW administers the technical specs, performs research and engineering analysis, implements ongoing construction quality management procedures, and maintains a central database with home tracking. This project prototyped and assessed the performances of cost-effective high performance building assemblies and mechanical systems that are not commonly deployed in the manufacturing setting. The package of measures is able to reduce energy used for space conditioning, water heating and lighting by 50 percent over typical manufactured homes produced in the northwest.

Not Available

2013-11-01T23:59:59.000Z

135

Core design study of a supercritical light water reactor with double row fuel rods  

SciTech Connect (OSTI)

An equilibrium core for supercritical light water reactor has been designed. A novel type of fuel assembly with dual rows of fuel rods between water rods is chosen and optimized to get more uniform assembly power distributions. Stainless steel is used for fuel rod cladding and structural material. Honeycomb structure filled with thermal isolation is introduced to reduce the usage of stainless steel and to keep moderator temperature below the pseudo critical temperature. Water flow scheme with ascending coolant flow in inner regions is carried out to achieve high outlet temperature. In order to enhance coolant outlet temperature, the radial power distributions needs to be as flat as possible through operation cycle. Fuel loading pattern and control rod pattern are optimized to flatten power distribution at inner regions. Axial fuel enrichment is divided into three parts to control axial power peak, which affects maximum cladding surface temperature. (authors)

Zhao, C.; Wu, H.; Cao, L.; Zheng, Y. [School of Nuclear Science and Technology, Xi'an Jiaotong Univ., No. 28, Xianning West Road, Xi'an, ShannXi, 710049 (China); Yang, J.; Zhang, Y. [China Nuclear Power Technology Research Inst., Yitian Road, ShenZhen, GuangDong, 518026 (China)

2012-07-01T23:59:59.000Z

136

Materials Science and Technology Division, light-water-reactor safety research program. Quarterly progress report, October-December 1982  

SciTech Connect (OSTI)

The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors, Transient Fuel Response and Fission Product Release, Clad Properties for Code Verification, and Long-Term Embrittlement of Cast Duplex Stainless Steels in LWR Systems.

Shack, W.J.; Rest, J.; Kassner, T.F.; Ayrault, G.; Chopra, O.K.; Chung, H.M.; Kupperman, D.S.; Maiya, P.S.; Nichols, F.A.; Park, J.Y.

1983-11-01T23:59:59.000Z

137

Conceptual design of a pressure tube light water reactor with variable moderator control  

SciTech Connect (OSTI)

This paper presents the development of innovative pressure tube light water reactor with variable moderator control. The core layout is derived from a CANDU line of reactors in general, and advanced ACR-1000 design in particular. It should be stressed however, that while some of the ACR-1000 mechanical design features are adopted, the core design basics of the reactor proposed here are completely different. First, the inter fuel channels spacing, surrounded by the calandria tank, contains a low pressure gas instead of heavy water moderator. Second, the fuel channel design features an additional/external tube (designated as moderator tube) connected to a separate moderator management system. The moderator management system is design to vary the moderator tube content from 'dry' (gas) to 'flooded' (light water filled). The dynamic variation of the moderator is a unique and very important feature of the proposed design. The moderator variation allows an implementation of the 'breed and burn' mode of operation. The 'breed and burn' mode of operation is implemented by keeping the moderator tube empty ('dry' filled with gas) during the breed part of the fuel depletion and subsequently introducing the moderator by 'flooding' the moderator tube for the 'burn' part. This paper assesses the conceptual feasibility of the proposed concept from a neutronics point of view. (authors)

Rachamin, R.; Fridman, E. [Reactor Safety Div., Inst. of Resource Ecology, Helmholtz-Zentrum Dresden-Rossendorf, POB 51 01 19, 01314 Dresden (Germany); Galperin, A. [Dept. of Nuclear Engineering, Ben-Gurion Univ. of the Negev, POB 653, Beer Sheva 84105 (Israel)

2012-07-01T23:59:59.000Z

138

Light Water Reactor Sustainability Program Status of Silicon Carbide Joining Technology Development  

SciTech Connect (OSTI)

Advanced, accident tolerant nuclear fuel systems are currently being investigated for potential application in currently operating light water reactors (LWR) or in reactors that have attained design certification. Evaluation of potential options for accident tolerant nuclear fuel systems point to the potential benefits of silicon carbide (SiC) relative to Zr-based alloys, including increased corrosion resistance, reduced oxidation and heat of oxidation, and reduced hydrogen generation under steam attack (off-normal conditions). If demonstrated to be applicable in the intended LWR environment, SiC could be used in nuclear fuel cladding or other in-core structural components. Achieving a SiC-SiC joint that resists corrosion with hot, flowing water, is stable under irradiation and retains hermeticity is a significant challenge. This report summarizes the current status of SiC-SiC joint development work supported by the Department of Energy Light Water Reactor Sustainability Program. Significant progress has been made toward SiC-SiC joint development for nuclear service, but additional development and testing work (including irradiation testing) is still required to present a candidate joint for use in nuclear fuel cladding.

Shannon M. Bragg-Sitton

2013-09-01T23:59:59.000Z

139

Environmentally assisted cracking in light water reactors. Semiannual report July 1996--December 1996  

SciTech Connect (OSTI)

This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally assisted cracking (EAC) in light water reactors from July 1996 to December 1996. Topics that have been investigated include (a) fatigue of carbon, low-alloy, and austenitic stainless steels (SSs) used in reactor piping and pressure vessels, (b) irradiation-assisted stress corrosion cracking of Type 304 SS, (c) EAC of Alloy 600, and (d) characterization of residual stresses in welds of boiling water reactor (BWR) core shrouds by numerical models. Fatigue tests were conducted on ferritic and austenitic SSs in water that contained various concentrations of dissolved oxygen to determine whether a slow strain rate applied during various portions of a tensile-loading cycle are equally effective in decreasing fatigue life. Slow-strain-rate-tensile tests were conducted in simulated BWR water at 288 C on SS specimens irradiated to a low fluence in the Halden reactor and the results were compared with similar data from a control-blade sheath and neutron-absorber tubes irradiated in BWRs to the same fluence level. Crack-growth-rate tests were conducted on compact-tension specimens from a low-carbon content heat of Alloy 600 in high-purity oxygenated water at 289 C. Residual stresses and stress intensity factors were calculated for BWR core shroud welds.

Chopra, O.K.; Chung, H.M.; Gavenda, D.J. [Argonne National Lab., IL (United States)] [and others

1997-10-01T23:59:59.000Z

140

Environmentally assisted cracking in light water reactors. Semiannual report, April 1994--September 1994, Volume 19  

SciTech Connect (OSTI)

This report summarizes work performed by Argonne National Laboratory (ANL) on fatigue and environmentally assisted cracking (EAC) in light water reactors from April to September 1994. Topics that have been investigated include (a) fatigue of carbon and low-alloy steel used in piping and reactor pressure vessels, (b) EAC of austenitic stainless steels (SSs) and Alloy 600, and (c) irradiation-assisted stress corrosion cracking (IASCC) of Type 304 SS. Fatigue tests have been conducted on A106-Gr B and A533-Gr B steels in oxygenated water to determine whether a slow strain rate applied during different portions of a tensile-loading cycle are equally effective in decreasing fatigue life. Crack growth data were obtained on fracture-mechanics specimens of SSs and Alloy 600 to investigate EAC in simulated boiling water reactor (BWR) and pressurized water reactor environments at 289{degrees}C. The data were compared with predictions from crack growth correlations developed at ANL for SSs in water and from rates in air from Section XI of the ASME Code. Microchemical changes in high- and commercial-purity Type 304 SS specimens from control-blade absorber tubes and a control-blade sheath from operating BWRs were studied by Auger electron spectroscopy and scanning electron microscopy to determine whether trace impurity elements may contribute to IASCC of these materials.

Chopra, O.K.; Chung, H.M.; Gavenda, D.J. [and others

1995-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "lighting manufacturing water" 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

Environmentally assisted cracking in Light Water Reactors: Semiannual report, April 1993--September 1993. Volume 17  

SciTech Connect (OSTI)

This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally assisted cracking (EAC) in light water reactors (LWRS) during the six months from April 1993 to September 1993. EAC and fatigue of piping, pressure vessels, and core components in LWRs are important concerns as extended reactor lifetimes are envisaged. Topics that have been investigated include (a) fatigue of low-alloy steel used in piping, steam generators, and reactor pressure vessels; (b) EAC of cast stainless steels (SSs); and (c) radiation-induced segregation and irradiation-assisted stress corrosion cracking of Type 304 SS after accumulation of relatively high fluence. Fatigue tests were conducted on medium-sulfur-content A106-Gr B piping and A533-Gr B pressure vessel steels in simulated PWR water and in air. Additional crack growth data were obtained on fracture-mechanics specimens of cast austenitic SSs in the as-received and thermally aged conditions in simulated boiling-water reactor (BWR) water at 289{degree}C. The data were compared with predictions based on crack growth correlations for wrought austenitic SS in oxygenated water developed at ANL and rates in air from Section 11 of the ASME Code. Microchemical and microstructural changes in high- and commercial-purity Type 304 SS specimens from control-blade absorber tubes and a control-blade sheath from operating BWRs were studied by Auger electron spectroscopy and scanning electron microscopy.

Chopra, O.K.; Chung, H.M.; Karlsen, T.; Kassner, T.F.; Michaud, W.F.; Ruther, W.E.; Sanecki, J.E.; Shack, W.J.; Soppet, W.K. [Argonne National Lab., IL (United States)

1994-06-01T23:59:59.000Z

142

Environmentally assisted cracking in light water reactors. Semiannual progress report, January 1996--June 1996  

SciTech Connect (OSTI)

This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally assisted cracking (EAC) in light water reactors from January 1996 to June 1996. Topics that have been investigated include (a) fatigue of carbon, low-alloy, and austenitic stainless steels (SSs) used in reactor piping and pressure vessels, (b) irradiation-assisted stress corrosion cracking of Type 304 SS, and (c) EAC of Alloys 600 and 690. Fatigue tests were conducted on ferritic and austenitic SSs in water that contained various concentrations of dissolved oxygen (DO) to determine whether a slow strain rate applied during various portions of a tensile-loading cycle are equally effective in decreasing fatigue life. Slow-strain-rate-tensile tests were conducted in simulated boiling water reactor (BWR) water at 288{degrees}C on SS specimens irradiated to a low fluence in the Halden reactor and the results were compared with similar data from a control-blade sheath and neutron-absorber tubes irradiated in BWRs to the same fluence level. Crack-growth-rate tests were conducted on compact-tension specimens from several heats of Alloys 600 and 690 in air and high-purity, low-DO water. 83 refs., 60 figs., 14 tabs.

Chopra, O.K.; Chung, H.M.; Gruber, E.E. [and others

1997-05-01T23:59:59.000Z

143

Manufacturing technologies  

SciTech Connect (OSTI)

The Manufacturing Technologies Center is an integral part of Sandia National Laboratories, a multiprogram engineering and science laboratory, operated for the Department of Energy (DOE) with major facilities at Albuquerque, New Mexico, and Livermore, California. Our Center is at the core of Sandia`s Advanced Manufacturing effort which spans the entire product realization process.

NONE

1995-09-01T23:59:59.000Z

144

Microencapsulated Fuel Technology for Commercial Light Water and Advanced Reactor Application  

SciTech Connect (OSTI)

The potential application of microencapsulated fuels to light water reactors (LWRs) has been explored. The specific fuel manifestation being put forward is for coated fuel particles embedded in silicon carbide or zirconium metal matrices. Detailed descriptions of these concepts are presented, along with a review of attributes, potential benefits, and issues with respect to their application in LWR environments, specifically from the standpoints of materials, neutronics, operations, and economics. Preliminary experiment and modeling results imply that with marginal redesign, significant gains in operational reliability and accident response margins could be potentially achieved by replacing conventional oxide-type LWR fuel with microencapsulated fuel forms.

Terrani, Kurt A [ORNL; Snead, Lance Lewis [ORNL; Gehin, Jess C [ORNL

2012-01-01T23:59:59.000Z

145

General features of direct-cycle, supercritical-pressure, light-water-cooled reactors  

SciTech Connect (OSTI)

The concept of direct-cycle, supercritical-pressure, light-water-cooled reactors is developed. Breeding is possible in the tight lattice core. The power output can be maximized in the fast converter reactor. The gross thermal efficiency of the high temperature reactor adopting Inconel as fuel cladding is expected to be 44.8%. The plant system is similar to the supercritical-fossil-fired power plant which adopts once-through type coolant circulation system. The volume and height of the containment are approximately half of the BWR. The basic safety principles follows those of LWRs. The reactor will solve the economic problems of LWR and LMFBR.

Oka, Y.; Koshizuka, S. [Univ. of Tokyo (Japan). Nuclear Engineering Research Lab.

1996-07-01T23:59:59.000Z

146

Light Water Reactor Safety Research Program. Semiannual report, October 1983-March 1984  

SciTech Connect (OSTI)

This report describes the investigations and analyses conducted at Sandia National Laboratories, Albuquerque, in support of the Light Water Reactor Safety Research Program from October 1983 through March 1984. The Fuel-Coolant Interactions Study investigates the mechanism of concrete erosion by molten core materials, the nature and rate of generation of evolved gases, and the effects of fission-product release. The Hydrogen Behavior and Mitigative and Preventive Schemes Programs investigate the HECTR code for modeling hydrogen deflagration, and the Grand Gulf Igniter System II is being reviewed. All activities are continuing. 53 figs., 11 tabs.

Berman, M.

1986-02-01T23:59:59.000Z

147

Shippingport operations with the Light Water Breeder Reactor core. (LWBR Development Program)  

SciTech Connect (OSTI)

This report describes the operation of the Shippingport Atomic Power Station during the LWBR (Light Water Breeder Reactor) Core lifetime. It also summarizes the plant-oriented operations during the period preceding LWBR startup, which include the defueling of The Pressurized Water Reactor Core 2 (PWR-2) and the installation of the LWBR Core, and the operations associated with the defueling of LWBR. The intent of this report is to examine LWBR experience in retrospect and present pertinent and significant aspects of LWBR operations that relate primarily to the nuclear portion of the Station. The nonnuclear portion of the Station is discussed only as it relates to overall plant operation or to unusual problems which result from the use of conventional equipment in radioactive environments. 30 refs., 69 figs., 27 tabs.

Budd, W.A. (ed.)

1986-03-01T23:59:59.000Z

148

Materials Science and Technology Division light-water-reactor safety research program: quarterly progress report, January-March 1983  

SciTech Connect (OSTI)

This progress report summarizes the Argonne National Laboratory work performed during January, February and March 1983 on water reactor safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors, Transient Fuel Response and Fission Product Release, Clad Properties for Code Verification, and Long-Term Embrittlement of Cast Duplex Stainless Steels in LWR Systems.

Not Available

1984-04-01T23:59:59.000Z

149

Materials Science Division light-water-reactor safety-research program. Quarterly progress report, April-June 1982. Volume 2  

SciTech Connect (OSTI)

This progress report summarizes the Argonne National Laboratory work performed during April, May, and June 1982 on water-reactor-safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors, Transient Fuel Response and Fission Product Release, and Clad Properties for Code Verification.

Shack, W.J.; Rest, J.; Kassner, T.F.; Chung, H.M.; Claytor, T.N.; Kupperman, D.S.; Maiya, P.S.; Nichols, F.A.; Park, J.Y.; Ruther, W.E.; Yaggee, F.L.

1983-05-01T23:59:59.000Z

150

Materials Science Division light-water-reactor safety research program. Quarterly progress report, July-September 1982  

SciTech Connect (OSTI)

This progress report summarizes the Argonne National Laboratory work performed during July, August, and September 1982 on water reactor safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors, Transient Fuel Response and Fission Product Release, Clad Properties for Code Verification, Posttest Fuel Examination of the ORNL Fission Product Release Tests, and Examination of TMI-2 Fuel Specimens.

Shack, W.J.; Rest, J.; Kassner, T.F.; Neimark, L.A.; Chung, H.M.; Claytor, T.N.; Kupperman, D.S.; Maiya, P.S.; Nichols, F.A.; Park, J.Y.

1983-08-01T23:59:59.000Z

151

Environmentally assisted cracking in light water reactors. Semiannual report, October 1993--March 1994. Volume 18  

SciTech Connect (OSTI)

This report summarizes work performed by Argonne National Laboratory (ANL) on fatigue and environmentally assisted cracking (EAC) in light water reactors (LWRs) during the six months from October 1993 to March 1994. EAC and fatigue of piping, pressure vessels, and core components in LWRs are important concerns in operating plants and as extended reactor lifetimes are envisaged. Topics that have been investigated include (a) fatigue of low-alloy steel used in piping, steam generators, and reactor pressure vessels, (b) EAC of wrought and cast austenitic stainless steels (SSs), and (c) radiation-induced segregation and irradiation-assisted stress corrosion cracking (IASCC) of Type 304 SS after accumulation of relatively high fluence. Fatigue tests have been conducted on A302-Gr B low-alloy steel to verify whether the current predictions of modest decreases of fatigue life in simulated pressurized water reactor water are valid for high-sulfur heats that show environmentally enhanced fatigue crack growth rates. Additional crack growth data were obtained on fracture-mechanics specimens of austenitic SSs to investigate threshold stress intensity factors for EAC in high-purity oxygenated water at 289{degrees}C. The data were compared with predictions based on crack growth correlations for wrought austenitic SS in oxygenated water developed at ANL and rates in air from Section XI of the ASME Code. Microchemical and microstructural changes in high- and commercial-purity Type 304 SS specimens from control-blade absorber tubes and a control-blade sheath from operating boiling water reactors were studied by Auger electron spectroscopy and scanning electron microscopy to determine whether trace impurity elements, which are not specified in the ASTM specifications, may contribute to IASCC of solution-annealed materials.

Chung, H.M.; Chopra, O.K.; Erck, R.A.; Kassner, T.F.; Michaud, W.F.; Ruther, W.E.; Sanecki, J.E.; Shack, W.J.; Soppet, W.K. [Argonne National Lab., IL (United States)

1995-03-01T23:59:59.000Z

152

Depolarized light scattering and dielectric response of a peptide dissolved in water  

SciTech Connect (OSTI)

The density and orientational relaxation of bulk water can be separately studied by depolarized light scattering (DLS) and dielectric spectroscopy (DS), respectively. Here, we ask the question of what are the leading collective modes responsible for polarization anisotropy relaxation (DLS) and dipole moment relaxation (DS) of solutions involving mostly hydrophobic solute-water interfaces. We study, by atomistic molecular dynamics simulations, the dynamics and structure of hydration water interfacing N-Acetyl-leucine-methylamide dipeptide. The DLS response of the solution is consistent with three relaxation processes: bulk water, rotations of single solutes, and collective dipole-induced-dipole polarizability of the solutes, with the time-scale of 130–200 ps. No separate DLS response of the hydration shell has been identified by our simulations. Density fluctuations of the hydration layer, which largely contribute to the response, do not produce a dynamical process distinct from bulk water. We find that the structural perturbation of the orientational distribution of hydration waters by the dipeptide solute is quite significant and propagates ?3?5 hydration layers into the bulk. This perturbation is still below that produced by hydrated globular proteins. Despite this structural perturbation, there is little change in the orientational dynamics of the hydration layers, compared to the bulk, as probed by both single-particle orientational dynamics and collective dynamics of the dipole moment of the shells. There is a clear distinction between the perturbation of the interfacial structure by the solute-solvent interaction potential and the perturbation of the interfacial dynamics by the corresponding forces.

Martin, Daniel R. [Department of Physics, Arizona State University, PO Box 871604, Tempe, Arizona 85287-1604 (United States)] [Department of Physics, Arizona State University, PO Box 871604, Tempe, Arizona 85287-1604 (United States); Fioretto, Daniele [Dipartimento di Fisica, Universita di Perugia, via Pascoli, 06123 Perugia (Italy)] [Dipartimento di Fisica, Universita di Perugia, via Pascoli, 06123 Perugia (Italy); Matyushov, Dmitry V., E-mail: dmitrym@asu.edu [Department of Physics and Department of Chemistry and Biochemistry, Arizona State University, PO Box 871604, Tempe, Arizona 85287-1604 (United States)

2014-01-21T23:59:59.000Z

153

Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels  

E-Print Network [OSTI]

1.1 This practice covers procedures for designing a surveillance program for monitoring the radiation-induced changes in the mechanical properties of ferritic materials in light-water moderated nuclear power reactor vessels. This practice includes the minimum requirements for the design of a surveillance program, selection of vessel material to be included, and the initial schedule for evaluation of materials. 1.2 This practice was developed for all light-water moderated nuclear power reactor vessels for which the predicted maximum fast neutron fluence (E > 1 MeV) at the end of license (EOL) exceeds 1 × 1021 neutrons/m2 (1 × 1017 n/cm2) at the inside surface of the reactor vessel. 1.3 This practice applies only to the planning and design of surveillance programs for reactor vessels designed and built after the effective date of this practice. Previous versions of Practice E185 apply to earlier reactor vessels. 1.4 This practice does not provide specific procedures for monitoring the radiation induced cha...

American Society for Testing and Materials. Philadelphia

2010-01-01T23:59:59.000Z

154

Nondestructive examination (NDE) reliability for inservice inspection of light waters reactors  

SciTech Connect (OSTI)

Evaluation and Improvement of NDE Reliability for Inservice Inspection of Light Water Reactors (NDE Reliability) Program at the Pacific Northwest Laboratory was established by the Nuclear Regulatory Commission to determine the reliability of current inservice inspection (ISI) techniques and to develop recommendations that will ensure a suitably high inspection reliability. The objectives of this program include determining the reliability of ISI performed on the primary systems of commercial light-water reactors (LWRs); using probabilistic fracture mechanics analysis to determine the impact of NDE unreliability on system safety; and evaluating reliability improvements that can be achieved with improved and advanced technology. A final objective is to formulate recommended revisions to ASME Code and Regulatory requirements, based on material properties, service conditions, and NDE uncertainties. The program scope is limited to ISI of the primary systems including the piping, vessel, and other inspected components. This is a progress report covering the programmatic work from April 1988 through September 1988. 33 refs., 70 figs., 12 tabs.

Doctor, S.R.; Deffenbaugh, J.D.; Good, M.S.; Green, E.R.; Heasler, P.G.; Simonen, F.A.; Spanner, J.C.; Taylor, T.T. (Pacific Northwest Lab., Richland, WA (USA))

1989-11-01T23:59:59.000Z

155

Manufacturing technology  

SciTech Connect (OSTI)

The specific goals of the Manufacturing Technology thrust area are to develop an understanding of fundamental fabrication processes, to construct general purpose process models that will have wide applicability, to document our findings and models in journals, to transfer technology to LLNL programs, industry, and colleagues, and to develop continuing relationships with industrial and academic communities to advance our collective understanding of fabrication processes. Advances in four projects are described here, namely Design of a Precision Saw for Manufacturing, Deposition of Boron Nitride Films via PVD, Manufacturing and Coating by Kinetic Energy Metallization, and Magnet Design and Application.

Blaedel, K.L.

1997-02-01T23:59:59.000Z

156

Artisan Manufacturing: Order (2010-CW-0712)  

Broader source: Energy.gov [DOE]

DOE ordered Artisan Manufacturing Company, Inc., to pay a $5,000 civil penalty after finding Artisan Manufacturing had failed to certify that certain models of faucets comply with the applicable water conservation standard.

157

e! Science News Semiconductor manufacturing technique holds  

E-Print Network [OSTI]

arsenide chips manufactured in multilayer stacks: light sensors, high-speed transistors and solar cellse! Science News Semiconductor manufacturing technique holds promise for solar energy Published semiconductor manufacturing method pioneered at the University of Illinois, the future of solar energy just got

Rogers, John A.

158

Induction Lighting: An Old Lighting Technology Made New Again...  

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

around the same time that his rival, Thomas Edison, was working to improve the incandescent light bulb. In the early 1990s, several major lighting manufacturers introduced...

159

Efficiency Maine Residential Lighting Program  

Broader source: Energy.gov [DOE]

Efficiency Maine's Residential Lighting Program works directly with retailers and manufacturers to encourage residential customers to purchase energy-efficient lighting. Rebate amounts average $1...

160

Nuclide Composition Benchmark Data Set for Verifying Burnup Codes on Spent Light Water Reactor Fuels  

SciTech Connect (OSTI)

To establish a nuclide composition benchmark data set for the verification of burnup codes, destructive analyses of light water reactor spent-fuel samples, which were cut out from several heights of spent-fuel rods, were carried out at the analytical laboratory at the Japan Atomic Energy Research Institute. The 16 samples from three kinds of pressurized water reactor (PWR) fuel rods and the 18 samples from two boiling water reactor (BWR) fuel rods were examined. Their initial {sup 235}U enrichments and burnups were from 2.6 to 4.1% and from 4 to 50 GWd/t, respectively. One PWR fuel rod and one BWR fuel rod contained gadolinia as a burnable poison. The measurements for more than 40 nuclides of uranium, transuranium, and fission product elements were performed by destructive analysis using mass spectrometry, and alpha-ray and gamma-ray spectrometry. Burnup for each sample was determined by the {sup 148}Nd method. The analytical methods and the results as well as the related irradiation condition data are compiled as a complete benchmark data set.

Nakahara, Yoshinori; Suyama, Kenya; Inagawa, Jun; Nagaishi, Ryuji; Kurosawa, Setsumi; Kohno, Nobuaki; Onuki, Mamoru; Mochizuki, Hiroki [Japan Atomic Energy Research Institute (Japan)

2002-02-15T23:59:59.000Z

Note: This page contains sample records for the topic "lighting manufacturing water" 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

Additive Manufacturing: Implications on Research and Manufacturing  

E-Print Network [OSTI]

Additive Manufacturing: Implications on Research and Manufacturing With recent developments, etc.), additive manufacturing (AM) has the potential to become a transformative technology in innovation-based manufacturing. Agencies such as the Department of Defense, the National Science Foundation

Crawford, T. Daniel

162

Environmentally assisted cracking in light water reactors annual report January - December 2005.  

SciTech Connect (OSTI)

This report summarizes work performed from January to December 2005 by Argonne National Laboratory on fatigue and environmentally assisted cracking in light water reactors (LWRs). Existing statistical models for estimating the fatigue life of carbon and low-alloy steels and austenitic stainless steels (SSs) as a function of material, loading, and environmental conditions were updated. Also, the ASME Code fatigue adjustment factors of 2 on stress and 20 on life were critically reviewed to assess the possible conservatism in the current choice of the margins. An approach, based on an environmental fatigue correction factor, for incorporating the effects of LWR environments into ASME Section III fatigue evaluations is discussed. The susceptibility of austenitic stainless steels and their welds to irradiation-assisted stress corrosion cracking (IASCC) is being evaluated as a function of the fluence level, water chemistry, material chemistry, and fabrication history. For this task, crack growth rate (CGR) tests and slow strain rate tensile (SSRT) tests are being conducted on various austenitic SSs irradiated in the Halden boiling water reactor. The SSRT tests are currently focused on investigating the effects of the grain boundary engineering process on the IASCC of the austenitic SSs. The CGR tests were conducted on Type 316 SSs irradiated to 0.45-3.0 dpa, and on sensitized Type 304 SS and SS weld heat-affected-zone material irradiated to 2.16 dpa. The CGR tests on materials irradiated to 2.16 dpa were followed by a fracture toughness test in a water environment. The effects of material composition, irradiation, and water chemistry on growth rates are discussed. The susceptibility of austenitic SS core internals to IASCC and void swelling is also being evaluated for pressurized water reactors. Both SSRT tests and microstructural examinations are being conducted on specimens irradiated in the BOR-60 reactor in Russia to doses up to 20 dpa. Crack growth rate data, obtained in the pressurized water reactor environment, are presented on Ni-alloy welds prepared in the laboratory or obtained from the nozzle-to-pipe weld of the V. C. Summer reactor. The experimental CGRs under cyclic and constant load are compared with the existing CGR data for Ni-alloy welds to determine the relative susceptibility of these materials to environmentally enhanced cracking under a variety of loading conditions.

Alexandreanu, B.; Chen, Y.; Chopra, O. K.; Chung, H. M.; Gruber, E. E.; Shack, W. J.; Soppet, W. K.

2007-08-31T23:59:59.000Z

163

Bolt Manufacture: Process Selection  

E-Print Network [OSTI]

file · Selective Laser Sintering (SLS) 3 D P i ti· 3-D Printing · Light Engineered Net Shaping (LENS Processes and Systems Prof. J.S. Colton © GIT 2009 20 #12;3D Printing Process (Soligen) ME 6222: Manufacturing Processes and Systems Prof. J.S. Colton © GIT 2009 21 #12;3D Printing Head (Soligen)3D Printing

Colton, Jonathan S.

164

Direct Water Splitting under Visible Light with a Nanostructured Photoanode and GaInP2 Photocathode  

SciTech Connect (OSTI)

Thin films of hematite nanorod and GaInP2 were used for direct water splitting under visible light. In open circuit conditions, the potential of hematite shifted cathodically and that of GaInP2 anodically, which generated an open circuit voltage between the two electrodes. In short circuit condition, the combination of the two photoelectrodes can split water under visible light illumination, though with a very low current of {micro}A/cm2 level even at 1 W/cm2 light. By means of chopped light, we found that hematite nanorod has a low photocurrent, which is responsible for the low short circuit current of the 2-electrode combination. The low photoresponse of hematite nanorods is due to the recombination of photo- generated charges, low holes mobility, and short diffusion length.

Wang, H.; Deutsch, T.; Turner, J.

2008-01-01T23:59:59.000Z

165

Light Water Breeder Reactor fuel rod design and performance characteristics (LWBR Development Program)  

SciTech Connect (OSTI)

Light Water Breeder Reactor (LWBR) fuel rods were designed to provide a reliable fuel system utilizing thorium/uranium-233 mixed-oxide fuel while simultaneously minimizing structural material to enhance fuel breeding. The fuel system was designed to be capable of operating successfully under both load follow and base load conditions. The breeding objective required thin-walled, low hafnium content Zircaloy cladding, tightly spaced fuel rods with a minimum number of support grid levels, and movable fuel rod bundles to supplant control rods. Specific fuel rod design considerations and their effects on performance capability are described. Successful completion of power operations to over 160 percent of design lifetime including over 200 daily load follow cycles has proven the performance capability of the fuel system. 68 refs., 19 figs., 44 tabs.

Campbell, W.R.; Giovengo, J.F.

1987-10-01T23:59:59.000Z

166

Chemical aspects of pellet-cladding interaction in light water reactor fuel elements  

SciTech Connect (OSTI)

In contrast to the extensive literature on the mechanical aspects of pellet-cladding interaction (PCI) in light water reactor fuel elements, the chemical features of this phenomenon are so poorly understood that there is still disagreement concerning the chemical agent responsible. Since the earliest work by Rosenbaum, Davies and Pon, laboratory and in-reactor experiments designed to elucidate the mechanism of PCI fuel rod failures have concentrated almost exclusively on iodine. The assumption that this is the reponsible chemical agent is contained in models of PCI which have been constructed for incorporation into fuel performance codes. The evidence implicating iodine is circumstantial, being based primarily upon the volatility and significant fission yield of this element and on the microstructural similarity of the failed Zircaloy specimens exposed to iodine in laboratory stress corrosion cracking (SCC) tests to cladding failures by PCI.

Olander, D.R.

1982-01-01T23:59:59.000Z

167

Categorization of failed and damaged spent LWR (light-water reactor) fuel currently in storage  

SciTech Connect (OSTI)

The results of a study that was jointly sponsored by the US Department of Energy and the Electric Power Research Institute are described in this report. The purpose of the study was to (1) estimate the number of failed fuel assemblies and damaged fuel assemblies (i.e., ones that have sustained mechanical or chemical damage but with fuel rod cladding that is not breached) in storage, (2) categorize those fuel assemblies, and (3) prepare this report as an authoritative, illustrated source of information on such fuel. Among the more than 45,975 spent light-water reactor fuel assemblies currently in storage in the United States, it appears that there are nearly 5000 failed or damaged fuel assemblies. 78 refs., 23 figs., 19 tabs.

Bailey, W.J.

1987-11-01T23:59:59.000Z

168

REACTOR PRESSURE VESSEL ISSUES FOR THE LIGHT-WATER REACTOR SUSTAINABILITY PROGRAM  

SciTech Connect (OSTI)

The Light Water Reactor Sustainability Program Plan is a collaborative program between the U.S. Department of Energy and the private sector directed at extending the life of the present generation of nuclear power plants to enable operation to at least 80 years. The reactor pressure vessel (RPV) is one of the primary components requiring significant research to enable such long-term operation. There are significant issues that need to be addressed to reduce the uncertainties in regulatory application, such as, 1) high neutron fluence/long irradiation times, and flux effects, 2) material variability, 3) high-nickel materials, 4)specimen size effects and the fracture toughness master curve, etc. The first issue is the highest priority to obtain the data and mechanistic understanding to enable accurate, reliable embrittlement predictions at high fluences. This paper discusses the major issues associated with long-time operation of existing RPVs and the LWRSP plans to address those issues.

Nanstad, Randy K [ORNL; Odette, George Robert [UCSB

2010-01-01T23:59:59.000Z

169

Advanced dry head-end reprocessing of light water reactor spent nuclear fuel  

SciTech Connect (OSTI)

A method for reprocessing spent nuclear fuel from a light water reactor includes the step of reacting spent nuclear fuel in a voloxidation vessel with an oxidizing gas having nitrogen dioxide and oxygen for a period sufficient to generate a solid oxidation product of the spent nuclear fuel. The reacting step includes the step of reacting, in a first zone of the voloxidation vessel, spent nuclear fuel with the oxidizing gas at a temperature ranging from 200-450.degree. C. to form an oxidized reaction product, and regenerating nitrogen dioxide, in a second zone of the voloxidation vessel, by reacting oxidizing gas comprising nitrogen monoxide and oxygen at a temperature ranging from 0-80.degree. C. The first zone and the second zone can be separate. A voloxidation system is also disclosed.

Collins, Emory D.; Delcul, Guillermo D.; Hunt, Rodney D.; Johnson, Jared A.; Spencer, Barry B.

2014-06-10T23:59:59.000Z

170

Advanced dry head-end reprocessing of light water reactor spent nuclear fuel  

DOE Patents [OSTI]

A method for reprocessing spent nuclear fuel from a light water reactor includes the step of reacting spent nuclear fuel in a voloxidation vessel with an oxidizing gas having nitrogen dioxide and oxygen for a period sufficient to generate a solid oxidation product of the spent nuclear fuel. The reacting step includes the step of reacting, in a first zone of the voloxidation vessel, spent nuclear fuel with the oxidizing gas at a temperature ranging from 200-450.degree. C. to form an oxidized reaction product, and regenerating nitrogen dioxide, in a second zone of the voloxidation vessel, by reacting oxidizing gas comprising nitrogen monoxide and oxygen at a temperature ranging from 0-80.degree. C. The first zone and the second zone can be separate. A voloxidation system is also disclosed.

Collins, Emory D; Delcul, Guillermo D; Hunt, Rodney D; Johnson, Jared A; Spencer, Barry B

2013-11-05T23:59:59.000Z

171

Light water reactor safety research program, quarterly report, July-September 1980. Volume 3  

SciTech Connect (OSTI)

The report covers research performed during July-September 1980 for the NRC Light Water Reactor Safety Research Program comprised of: (1) The Molten Fuel Concrete Interactions (MFCI) study of experimental and analytical investigations of the chemical and physical phenomena associated with interactions between molten core materials and concrete; (2) Steam Explosion Phenomena program to assess the probability and consequences of steam explosions during postulated meltdown accidents in LWRs; (3) Separate Effects Tests for TRAP Code Development investigating vapor pressures of fission-product species at elevated temperatures, chemical compound formation and reaction rates; (4) Containment Emergency Sump Performance (CESP) program to investigate the reliability of ECCS sumps; (5) Hydrogen Program designed to quantify the threat posed by hydrogen released during LWR accidents; and (6) Combustible Gas in Containment Program to study the generation of H2 from the corrosion of zinc and other materials located within LWR containment buildings.

Berman, M.

1981-04-01T23:59:59.000Z

172

Light water reactor safety research program. Quarterly report Jan-Mar 80  

SciTech Connect (OSTI)

The Molten Fuel Concrete Interactions (MFCI) study is comprised of experimental and analytical investigations of the chemical and physical phenomena associated with interactions between molten core materials and concrete. Such interactions are possible during hypothetical fuel-melt accidents in light water reactors (LWRs) when molten fuel and steel from the reactor core penetrate the pressure vessel and cascade onto the concrete substructure. The purpose of the MFCI study is to develop an understanding of these interactions suitable for risk assessment. Emphasis is placed on identifying and investigating the dominant interaction phenomena occurring between prototypic materials. The table of contents is the following: Molten fuel concrete interactions study; Steam explosion phenomena; Separate effects tests for TRAP code development; and Containment emergency sump performance.

Berman, M.

1980-09-01T23:59:59.000Z

173

Light-water-reactor safety research program. Quarterly progress report, July-September 1980  

SciTech Connect (OSTI)

A physically realistic description of fuel swelling and fission-gas release is needed to aid in predicting the behavior of fuel rods and fission gases under certain hypothetical light-water-reactor (LWR) accident conditions. To satisfy this need, a comprehensive computer-base model, the Steady-State and Transient Gas-Release and Swelling Subroutine (GRASS-SST), its faster-running version, FASTGRASS, and correlations based on analyses performed with GRASS-SST, PARAGRASS, are being developed at Argonne National Laboratory (ANL). This model is being incorporated into the Fuel-Rod Analysis Program (FRAP) code being developed by EG and G Idaho, Inc., at the Idaho National Engineering Laboratory (INEL). The analytical effort is supported by a data base and correlations developed from characterization of irradiated LWR fuel and from out-of-reactor transient heating tests of irradiated commercial and experimental LWR fuel under a range of thermal conditions. 7 refs., 2 figs.

Massey, W.E.; Till, C.E.

1981-02-01T23:59:59.000Z

174

Sensitivity Analysis of Reprocessing Cooling Times on Light Water Reactor and Sodium Fast Reactor Fuel Cycles  

SciTech Connect (OSTI)

The purpose of this study is to quantify the effects of variations of the Light Water Reactor (LWR) Spent Nuclear Fuel (SNF) and fast reactor reprocessing cooling time on a Sodium Fast Reactor (SFR) assuming a single-tier fuel cycle scenario. The results from this study show the effects of different cooling times on the SFR’s transuranic (TRU) conversion ratio (CR) and transuranic fuel enrichment. Also, the decay heat, gamma heat and neutron emission of the SFR’s fresh fuel charge were evaluated. A 1000 MWth commercial-scale SFR design was selected as the baseline in this study. Both metal and oxide CR=0.50 SFR designs are investigated.

R. M. Ferrer; S. Bays; M. Pope

2008-04-01T23:59:59.000Z

175

Standard Guide for In-Service Annealing of Light-Water Moderated Nuclear Reactor Vessels  

E-Print Network [OSTI]

1.1 This guide covers the general procedures to be considered for conducting an in-service thermal anneal of a light-water moderated nuclear reactor vessel and demonstrating the effectiveness of the procedure. The purpose of this in-service annealing (heat treatment) is to improve the mechanical properties, especially fracture toughness, of the reactor vessel materials previously degraded by neutron embrittlement. The improvement in mechanical properties generally is assessed using Charpy V-notch impact test results, or alternatively, fracture toughness test results or inferred toughness property changes from tensile, hardness, indentation, or other miniature specimen testing (1). 1.2 This guide is designed to accommodate the variable response of reactor-vessel materials in post-irradiation annealing at various temperatures and different time periods. Certain inherent limiting factors must be considered in developing an annealing procedure. These factors include system-design limitations; physical constrain...

American Society for Testing and Materials. Philadelphia

2003-01-01T23:59:59.000Z

176

Vibrational spectra of light and heavy water with application to neutron cross section calculations  

SciTech Connect (OSTI)

The design of nuclear reactors and neutron moderators require a good representation of the interaction of low energy (E < 1 eV) neutrons with hydrogen and deuterium containing materials. These models are based on the dynamics of the material, represented by its vibrational spectrum. In this paper, we show calculations of the frequency spectrum for light and heavy water at room temperature using two flexible point charge potentials: SPC-MPG and TIP4P/2005f. The results are compared with experimental measurements, with emphasis on inelastic neutron scattering data. Finally, the resulting spectra are applied to calculation of neutron scattering cross sections for these materials, which were found to be a significant improvement over library data.

Damian, J. I. Marquez; Granada, J. R. [Neutron Physics Department and Instituto Balseiro, Centro Atomico Bariloche, CNEA (Argentina); Malaspina, D. C. [Department of Biomedical Engineering and Chemistry of Life Processes Institute, Northwestern University, 2145 Sheridan Road, Evanston, Illinois 60208 (United States)

2013-07-14T23:59:59.000Z

177

Accuracy Based Generation of Thermodynamic Properties for Light Water in RELAP5-3D  

SciTech Connect (OSTI)

RELAP5-3D interpolates to obtain thermodynamic properties for use in its internal calculations. The accuracy of the interpolation was determined for the original steam tables currently used by the code. This accuracy evaluation showed that the original steam tables are generally detailed enough to allow reasonably accurate interpolations in most areas needed for typical analyses of nuclear reactors cooled by light water. However, there were some regions in which the original steam tables were judged to not provide acceptable accurate results. Revised steam tables were created that used a finer thermodynamic mesh between 4 and 21 MPa and 530 and 640 K. The revised steam tables solved most of the problems observed with the original steam tables. The accuracies of the original and revised steam tables were compared throughout the thermodynamic grid.

Cliff B. Davis

2010-09-01T23:59:59.000Z

178

Advanced Proliferation Resistant, Lower Cost, Uranium-Thorium Dioxide Fuels for Light Water Reactors (Progress report for work through June 2002, 12th quarterly report)  

SciTech Connect (OSTI)

The overall objective of this NERI project is to evaluate the potential advantages and disadvantages of an optimized thorium-uranium dioxide (ThO2/UO2) fuel design for light water reactors (LWRs). The project is led by the Idaho National Engineering and Environmental Laboratory (INEEL), with the collaboration of three universities, the University of Florida, Massachusetts Institute of Technology (MIT), and Purdue University; Argonne National Laboratory; and all of the Pressurized Water Reactor (PWR) fuel vendors in the United States (Framatome, Siemens, and Westinghouse). In addition, a number of researchers at the Korean Atomic Energy Research Institute and Professor Kwangheon Park at Kyunghee University are active collaborators with Korean Ministry of Science and Technology funding. The project has been organized into five tasks: · Task 1 consists of fuel cycle neutronics and economics analysis to determine the economic viability of various ThO2/UO2 fuel designs in PWRs, · Task 2 will determine whether or not ThO2/UO2 fuel can be manufactured economically, · Task 3 will evaluate the behavior of ThO2/UO2 fuel during normal, off-normal, and accident conditions and compare the results with the results of previous UO2 fuel evaluations and U.S. Nuclear Regulatory Commission (NRC) licensing standards, · Task 4 will determine the long-term stability of ThO2/UO2 high-level waste, and · Task 5 consists of the Korean work on core design, fuel performance analysis, and xenon diffusivity measurements.

Mac Donald, Philip Elsworth

2002-09-01T23:59:59.000Z

179

Final report for the Light Water Breeder Reactor proof-of-breeding analytical support project  

SciTech Connect (OSTI)

The technology of breeding /sup 233/U from /sup 232/Th in a light water reactor is being developed and evaluated by the Westinghouse Bettis Atomic Power Laboratory (BAPL) through operation and examination of the Shippingport Light Water Breeder Reactor (LWBR). Bettis is determining the end-of-life (EOL) inventory of fissile uranium in the LWBR core by nondestructive assay of a statistical sample comprising approximately 500 EOL fuel rods. This determination is being made with an irradiated-fuel assay gauge based on neutron interrogation and detection of delayed neutrons from each rod. The EOL fissile inventory will be compared with the beginning-of-life fissile loading of the LWBR to determine the extent of breeding. In support of the BAPL proof-of-breeding (POB) effort, Argonne National Laboratory (ANL) carried out destructive physical, chemical, and radiometric analyses on 17 EOL LWBR fuel rods that were previously assayed with the nondestructive gauge. The ANL work included measurements on the intact rods; shearing of the rods into pre-designated contiguous segments; separate dissolution of each of the more than 150 segments; and analysis of the dissolver solutions to determine each segment's uranium content, uranium isotopic composition, and loading of selected fission products. This report describes the facilities in which this work was carried out, details operations involved in processing each rod, and presents a comprehensive discussion of uncertainties associated with each result of the ANL measurements. Most operations were carried out remotely in shielded cells. Automated equipment and procedures, controlled by a computer system, provided error-free data acquisition and processing, as well as full replication of operations with each rod. Despite difficulties that arose during processing of a few rod segments, the ANL destructive-assay results satisfied the demanding needs of the parent LWBR-POB program.

Graczyk, D.G.; Hoh, J.C.; Martino, F.J.; Nelson, R.E.; Osudar, J.; Levitz, N.M.

1987-05-01T23:59:59.000Z

180

Environmentally assisted cracking in light water reactors - annual report, January-December 2001.  

SciTech Connect (OSTI)

This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally assisted cracking (EAC) in light water reactors (LWRs) from January to December 2001. Topics that have been investigated include (a) environmental effects on fatigue S-N behavior of austenitic stainless steels (SSs), (b) irradiation-assisted stress corrosion cracking (IASCC) of austenitic SSs, and (c) EAC of Alloy 600. The effects of key material and loading variables, such as strain amplitude, strain rate, temperature, dissolved oxygen (DO) level in water, and material heat treatment, on the fatigue lives of wrought and cast austenitic SSs in air and LWR environments have been evaluated. The mechanism of fatigue crack initiation in austenitic SSs in LWR environments has also been examined. The results indicate that the presence of a surface oxide film or difference in the characteristics of the oxide film has no effect on fatigue crack initiation in austenitic SSs in LWR environments. Slow-strain-rate tensile tests and post-test fractographic analyses were conducted on several model SS alloys irradiated to {approx}2 x 10{sup 21} n {center_dot} cm{sup -2} (E > 1 MeV) ({approx}3 dpa) in He at 289 C in the Halden reactor. The results were used to determine the influence of alloying and impurity elements on the susceptibility of these steels to IASCC. Corrosion fatigue tests were conducted on nonirradiated austenitic SSs in high-purity water at 289 C to establish the test procedure and conditions that will be used for the tests on irradiated materials. A comprehensive irradiation experiment was initiated to obtain many tensile and disk specimens irradiated under simulated pressurized water reactor conditions at {approx}325 C to 5, 10, 20, and 40 dpa. Crack growth tests were completed on 30% cold-worked Alloy 600 in high-purity water under various environmental and loading conditions. The results are compared with data obtained earlier on several heats of Alloy 600 tested in high-DO water under several heat treatment conditions.

Chopra, O. K.; Chung, H. M.; Clark, R. W.; Gruber, E. E; Hiller, R. W.; Shack, W. J.; Soppet, W. K.; Strain, R. V.; Energy Technology

2003-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "lighting manufacturing water" 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

Removal of pollutant compounds from water supplies using ozone, ultraviolet light, and a counter, current packed column. Master's thesis  

SciTech Connect (OSTI)

Many water pollutants are determined to be carcinogenic and often appear in very low concentrations and still pose a health risk. Conventional water treatment processes cannot remove these contaminants and there is a great demand for the development of alternative removal technologies. The use of ozone and ultraviolet light in a counter current packed column could prove to be an effective treatment process to remove these contaminants.

Kelly, E.L.

1991-01-01T23:59:59.000Z

182

Fuel Cell Manufacturing: American Energy and Manufacturing Competitive...  

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

Fuel Cell Manufacturing: American Energy and Manufacturing Competitiveness Summit Fuel Cell Manufacturing: American Energy and Manufacturing Competitiveness Summit Presentation on...

183

Stress corrosion cracking and crack tip characterization of Alloy X-750 in light water reactor environments  

E-Print Network [OSTI]

Stress corrosion cracking (SCC) susceptibility of Inconel Alloy X-750 in the HTH condition has been evaluated in high purity water at 93 and 288°C under Boiling Water Reactor Normal Water Chemistry (NWC) and Hydrogen Water ...

Gibbs, Jonathan Paul

2011-01-01T23:59:59.000Z

184

Stress Corrosion Cracking and Crack Tip Characterization of Alloy X-750 in Light Water Reactor Environments  

E-Print Network [OSTI]

Stress corrosion cracking (SCC) susceptibility of Inconel Alloy X-750 in the HTH condition has been evaluated in high purity water at 93 and 288°C under Boiling Water Reactor Normal Water Chemistry (NWC) and Hydrogen Water ...

Gibbs, Jonathan Paul

185

309NUCLEAR ENGINEERING AND TECHNOLOGY, VOL.37 NO.4, AUGUST 2005 A NEW BOOK: "LIGHT-WATER REACTOR MATERIALS"  

E-Print Network [OSTI]

309NUCLEAR ENGINEERING AND TECHNOLOGY, VOL.37 NO.4, AUGUST 2005 A NEW BOOK: "LIGHT-WATER REACTOR review; it is a book preview. Thirty years ago, "Fundamental Aspects of Nuclear Reactor Fuel Elements of nuclear fuels among other topics pertinent to the materials in the ensemble of the nuclear reactor

Motta, Arthur T.

186

EIS-0071: Memphis Light, Gas and Water Division Industrial Fuels Gas Demonstration Plant, Memphis, Shelby County, Tennessee  

Broader source: Energy.gov [DOE]

The U.S. Department of Energy developed this EIS to assesses the potential environmental impacts associated with the construction and operation of a 3,155-ton-per-day capacity facility, which will demonstrate the technical operability, economic viability, and environmental acceptability of the Memphis Division of Light, Gas and Water coal gasification plant at Memphis, Tennessee.

187

EIS-0288-S1: Production of Tritium in a Commercial Light Water Reactor (CLWR) Tritium Readiness Supplemental Environmental Impact Statement  

Broader source: Energy.gov [DOE]

This Supplemental EIS updates the environmental analyses in DOE’s 1999 EIS for the Production of Tritium in a Commercial Light Water Reactor (CLWR EIS). The CLWR EIS addressed the production of tritium in Tennessee Valley Authority reactors in Tennessee using tritium-producing burnable absorber rods.

188

Ferritic Alloys as Accident Tolerant Fuel Cladding Material for Light Water Reactors  

SciTech Connect (OSTI)

The objective of the GE project is to demonstrate that advanced steels such as iron-chromium-aluminum (FeCrAl) alloys could be used as accident tolerant fuel cladding material in commercial light water reactors. The GE project does not include fuel development. Current findings support the concept that a FeCrAl alloy could be used for the cladding of commercial nuclear fuel. The use of this alloy will benefit the public since it is going to make the power generating light water reactors safer. In the Phase 1A of this cost shared project, GE (GRC + GNF) teamed with the University of Michigan, Los Alamos National Laboratory, Brookhaven National Laboratory, Idaho National Laboratory, and Oak Ridge National Laboratory to study the environmental and mechanical behavior of more than eight candidate cladding material both under normal operation conditions of commercial nuclear reactors and under accident conditions in superheated steam (loss of coolant condition). The main findings are as follows: (1) Under normal operation conditions the candidate alloys (e.g. APMT, Alloy 33) showed excellent resistance to general corrosion, shadow corrosion and to environmentally assisted cracking. APMT also showed resistance to proton irradiation up to 5 dpa. (2) Under accident conditions the selected candidate materials showed several orders of magnitude improvement in the reaction with superheated steam as compared with the current zirconium based alloys. (3) Tube fabrication feasibility studies of FeCrAl alloys are underway. The aim is to obtain a wall thickness that is below 400 µm. (4) A strategy is outlined for the regulatory path approval and for the insertion of a lead fuel assembly in a commercial reactor by 2022. (5) The GE team worked closely with INL to have four rodlets tested in the ATR. GE provided the raw stock for the alloys, the fuel for the rodlets and the cost for fabrication/welding of the rodlets. INL fabricated the rodlets and the caps and welded them to provide hermetic seal. The replacement of a zirconium alloy using a ferritic material containing chromium and aluminum appears to be the most near term implementation for accident tolerant nuclear fuels.

Rebak, Raul B. [General Electric] (ORCID:0000000280704475)

2014-12-30T23:59:59.000Z

189

Adaptation of gas tagging for failed fuel identification in light water reactors  

SciTech Connect (OSTI)

This paper discusses experience with noble gas tagging and its adaptation to commercial reactors. It reviews the recent incidence of fuel failures in light water reactors, and methods used to identify failures, and concludes that the on-line technique of gas tagging could significantly augment present flux tilting, sipping and ultrasonic testing of assemblies. The paper describes calculations on tag gas stability in-reactor, and tag injection tests that were carried out collaboratively with Commonwealth Edison Company in the Byron-2 pressurized water reactor (P%a) and with Duke Power Company and Babcock and Wilcox Fuel Company in the Oconee-2 PWM. The tests gave information on: (a) noble gas concentration dynamics as the tag gases were dissolved in and eventually removed from subsystems of the RCS; and (b) the suitability of candidate Ar, Ne, Kr and Xe isotopes for tagging PWR fuel. It was found that the activity of Xe{sup 125} (the activation product of the tag isotope Xe{sup 124}) acted as a ``tag of a tag`` and tracked gas through the reactor; measured activities are being used to model gas movement in the RCS. Several interference molecules (trace contaminants normally present at sub-ppM concentrations in RCS samples) and entrained air in the RCS were found to affect mass spectrometer sensitivity for tag isotopes. In all instances the contaminants could be differentiated from the tag isotopes by operating the mass spectrometer at high resolution (2500). Similarly, it was possible to distinguish all the candidate tag gases against a high background of air. The test results suggested, however, that for routine analysis a high resolution static mass spectrometer will be preferable to the dynamic instrument used for the present analyses.

Lambert, J.D.B.; Gross, K.C.; Depiante, E.V. [Argonne National Lab., IL (United States); Callis, E.L. [Los Alamos National Lab., NM (United States); Egebrecht, P.M. [Commonwealth Edison Company, Downers Grove, IL (United States)

1996-03-01T23:59:59.000Z

190

Radioactive Fission Product Release from Defective Light Water Reactor Fuel Elements  

SciTech Connect (OSTI)

Results are provided of the experimental investigation of radioactive fission product (RFP) release, i.e., krypton, xenon, and iodine radionuclides from fuel elements with initial defects during long-term (3 to 5 yr) irradiation under low linear power (5 to 12 kW/m) and during special experiments in the VK-50 vessel-type boiling water reactor.The calculation model for the RFP release from the fuel-to-cladding gap of the defective fuel element into coolant was developed. It takes into account the convective transport in the fuel-to-cladding gap and RFP sorption on the internal cladding surface and is in good agreement with the available experimental data. An approximate analytical solution of the transport equation is given. The calculation dependencies of the RFP release coefficients on the main parameters such as defect size, fuel-to-cladding gap, temperature of the internal cladding surface, and radioactive decay constant were analyzed.It is shown that the change of the RFP release from the fuel elements with the initial defects during long-term irradiation is, mainly, caused by fuel swelling followed by reduction of the fuel-to-cladding gap and the fuel temperature. The calculation model for the RFP release from defective fuel elements applicable to light water reactors (LWRs) was developed. It takes into account the change of the defective fuel element parameters during long-term irradiation. The calculation error according to the program does not exceed 30% over all the linear power change range of the LWR fuel elements (from 5 to 26 kW/m)

Konyashov, Vadim V.; Krasnov, Alexander M. [State Scientific Centre of Russian Federation-Research Institute of Atomic Reactors (Russian Federation)

2002-04-15T23:59:59.000Z

191

Manufacturing Success Stories  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: AlternativeEnvironment, SafetyWater ConservationDepartmentEnergy Manufacturing Energy6

192

Feasibility Study of Supercritical Light Water Cooled Reactors for Electrical Power Production, 5th Quarterly Report, October - December 2002  

SciTech Connect (OSTI)

The overall objective of this project is to evaluate the feasibility of supercritical light water cooled reactors for electric power production. The use of light water at supercritical pressures as the coolant in a nuclear reactor offers the potential for considerable plant simplification and consequent capital and O&M cost reduction compared with current light water reactor (LWR) designs. Also, given the thermodynamic conditions of the coolant at the core outlet (i.e. temperature and pressure beyond the water critical point), very high thermal efficiencies for the power conversion cycle are possible (i.e. up to about 45%). Because no change of phase occurs in the core, the need for steam separators and dryers as well as for BWR-type re-circulation pumps is eliminated, which, for a given reactor power, results in a substantially shorter reactor vessel and smaller containment building than the current BWRs. Furthermore, in a direct cycle the steam generators are not needed. If no additional moderator is added to the fuel rod lattice, it is possible to attain fast neutron energy spectrum conditions in a supercritical water-cooled reactor (SCWR). This type of core can make use of either fertile or fertile-free fuel and retain a hard spectrum to effectively burn plutonium and minor actinides from LWR spent fuel while efficiently generating electricity. One can also add moderation and design a thermal spectrum SCWR that can also burn actinides. The project is organized into three tasks:

Philip MacDonald; Jacopo Buongiorno; Cliff Davis; J. Stephen Herring; Kevan Weaver; Ron Latanision; Bryce Mitton; Gary Was; Luca Oriani; Mario Carelli; Dmitry Paramonov; Lawrence Conway

2003-01-01T23:59:59.000Z

193

Green Manufacturing  

SciTech Connect (OSTI)

Green Manufacturing Initiative (GMI): The initiative provides a conduit between the university and industry to facilitate cooperative research programs of mutual interest to support green (sustainable) goals and efforts. In addition to the operational savings that greener practices can bring, emerging market demands and governmental regulations are making the move to sustainable manufacturing a necessity for success. The funding supports collaborative activities among universities such as the University of Michigan, Michigan State University and Purdue University and among 40 companies to enhance economic and workforce development and provide the potential of technology transfer. WMU participants in the GMI activities included 20 faculty, over 25 students and many staff from across the College of Engineering and Applied Sciences; the College of Arts and Sciences' departments of Chemistry, Physics, Biology and Geology; the College of Business; the Environmental Research Institute; and the Environmental Studies Program. Many outside organizations also contribute to the GMI's success, including Southwest Michigan First; The Right Place of Grand Rapids, MI; Michigan Department of Environmental Quality; the Michigan Department of Energy, Labor and Economic Growth; and the Michigan Manufacturers Technical Center.

Patten, John

2013-12-31T23:59:59.000Z

194

Feasibility Study of Supercritical Light Water Cooled Fast Reactors for Actinide Burning and Electric Power Production, 3rd Quarterly Report  

SciTech Connect (OSTI)

The use of light water at supercritical pressures as the coolant in a nuclear reactor offers the potential for considerable plant simplification and consequent capital and O&M cost reduction compared with current light water reactor (LWR) designs. Also, given the thermodynamic conditions of the coolant at the core outlet (i.e. temperature and pressure beyond the water critical point), very high thermal efficiencies of the power conversion cycle are possible (i.e. up to about 45%). Because no change of phase occurs in the core, the need for steam separators and dryers as well as for BWR-type re-circulation pumps is eliminated, which, for a given reactor power, results in a substantially shorter reactor vessel and smaller containment building than the current BWRs. Furthermore, in a direct cycle the steam generators are not needed.

Mac Donald, Philip Elsworth

2002-06-01T23:59:59.000Z

195

Accident source terms for Light-Water Nuclear Power Plants. Final report  

SciTech Connect (OSTI)

In 1962 tile US Atomic Energy Commission published TID-14844, ``Calculation of Distance Factors for Power and Test Reactors`` which specified a release of fission products from the core to the reactor containment for a postulated accident involving ``substantial meltdown of the core``. This ``source term``, tile basis for tile NRC`s Regulatory Guides 1.3 and 1.4, has been used to determine compliance with tile NRC`s reactor site criteria, 10 CFR Part 100, and to evaluate other important plant performance requirements. During the past 30 years substantial additional information on fission product releases has been developed based on significant severe accident research. This document utilizes this research by providing more realistic estimates of the ``source term`` release into containment, in terms of timing, nuclide types, quantities and chemical form, given a severe core-melt accident. This revised ``source term`` is to be applied to the design of future light water reactors (LWRs). Current LWR licensees may voluntarily propose applications based upon it.

Soffer, L.; Burson, S.B.; Ferrell, C.M.; Lee, R.Y.; Ridgely, J.N.

1995-02-01T23:59:59.000Z

196

Analysis of assembly serial number usage in domestic light-water reactors  

SciTech Connect (OSTI)

Domestic light-water reactor (LWR) fuel assemblies are identified by a serial number that is placed on each assembly. These serial numbers are used as identifiers throughout the life of the fuel. The uniqueness of assembly serial numbers is important in determining their effectiveness as unambiguous identifiers. The purpose of this study is to determine what serial numbering schemes are used, the effectiveness of these schemes, and to quantify how many duplicate serial numbers occur on domestic LWR fuel assemblies. The serial numbering scheme adopted by the American National Standards Institute (ANSI) ensures uniqueness of assembly serial numbers. The latest numbering scheme adopted by General Electric (GE), was also found to be unique. Analysis of 70,971 fuel assembly serial numbers from permanently discharged fuel identified 11,948 serial number duplicates. Three duplicate serial numbers were found when analysis focused on duplication within the individual fuel inventory at each reactor site, but these were traced back to data entry errors and will be corrected by the Energy Information Administration (EIA). There were also three instances where the serial numbers used to identify assemblies used for hot cell studies differed from the serial numbers reported to the EIA. It is recommended that fuel fabricators and utilities adhere to the ANSI serial numbering scheme to ensure serial number uniqueness. In addition, organizations collecting serial number information, should request that all known serial numbers physically attached or associated with each assembly be reported and identified by the corresponding number scheme. 10 refs., 5 tabs.

Reich, W.J. (Oak Ridge National Lab., TN (USA)); Moore, R.S. (Automated Sciences Group, Inc., Oak Ridge, TN (USA))

1991-05-01T23:59:59.000Z

197

Assessment of the use of extended burnup fuel in light water power reactors  

SciTech Connect (OSTI)

This study has been conducted by Pacific Northwest Laboratory for the US Nuclear Regulatory Commission to review the environmental and economic impacts associated with the use of extended burnup nuclear fuel in light water power reactors. It has been proposed that current batch average burnup levels of 33 GWd/t uranium be increased to above 50 GWd/t. The environmental effects of extending fuel burnup during normal operations and during accident events and the economic effects of cost changes on the fuel cycle are discussed in this report. The physical effects of extended burnup on the fuel and the fuel assembly are also presented as a basis for the environmental and economic assessments. Environmentally, this burnup increase would have no significant impact over that of normal burnup. Economically, the increased burnup would have favorable effects, consisting primarily of a reduction: (1) total fuel requirements; (2) reactor downtime for fuel replacement; (3) the number of fuel shipments to and from reactor sites; and (4) repository storage requirements. 61 refs., 4 figs., 27 tabs.

Baker, D.A.; Bailey, W.J.; Beyer, C.E.; Bold, F.C.; Tawil, J.J.

1988-02-01T23:59:59.000Z

198

Safeguards and security requirements for weapons plutonium disposition in light water reactors  

SciTech Connect (OSTI)

This paper explores the issues surrounding the safeguarding of the plutonium disposition process in support of the United States nuclear weapons dismantlement program. It focuses on the disposition of the plutonium by burning mixed oxide fuel in light water reactors (LWR) and addresses physical protection, material control and accountability, personnel security and international safeguards. The S and S system needs to meet the requirements of the DOE Orders, NRC Regulations and international safeguards agreements. Experience has shown that incorporating S and S measures into early facility designs and integrating them into operations provides S and S that is more effective, more economical, and less intrusive. The plutonium disposition safeguards requirements with which the US has the least experience are the implementation of international safeguards on plutonium metal; the large scale commercialization of the mixed oxide fuel fabrication; and the transportation to and loading in the LWRs of fresh mixed oxide fuel. It is in these areas where the effort needs to be concentrated if the US is to develop safeguards and security systems that are effective and efficient.

Thomas, L.L.; Strait, R.S. [Lawrence Livermore National Lab., CA (United States). Fission Energy and Systems Safety Program

1994-10-01T23:59:59.000Z

199

Insights for aging management of light water reactor components: Metal containments. Volume 5  

SciTech Connect (OSTI)

This report evaluates the available technical information and field experience related to management of aging damage to light water reactor metal containments. A generic aging management approach is suggested for the effective and comprehensive aging management of metal containments to ensure their safe operation. The major concern is corrosion of the embedded portion of the containment vessel and detection of this damage. The electromagnetic acoustic transducer and half-cell potential measurement are potential techniques to detect corrosion damage in the embedded portion of the containment vessel. Other corrosion-related concerns include inspection of corrosion damage on the inaccessible side of BWR Mark I and Mark II containment vessels and corrosion of the BWR Mark I torus and emergency core cooling system piping that penetrates the torus, and transgranular stress corrosion cracking of the penetration bellows. Fatigue-related concerns include reduction in the fatigue life (a) of a vessel caused by roughness of the corroded vessel surface and (b) of bellows because of any physical damage. Maintenance of surface coatings and sealant at the metal-concrete interface is the best protection against corrosion of the vessel.

Shah, V.N.; Sinha, U.P. [EG and G Idaho, Inc., Idaho Falls, ID (United States); Smith, S.K. [Ogden Environmental and Energy Services, Southfield, MI (United States)

1994-03-01T23:59:59.000Z

200

Modeling of the performance of weapons MOX fuel in light water reactors  

SciTech Connect (OSTI)

Both the Russian Federation and the US are pursing mixed uranium-plutonium oxide (MOX) fuel in light water reactors (LWRs) for the disposition of excess plutonium from disassembled nuclear warheads. Fuel performance models are used which describe the behavior of MOX fuel during irradiation under typical power reactor conditions. The objective of this project is to perform the analysis of the thermal, mechanical, and chemical behavior of weapons MOX fuel pins under LWR conditions. If fuel performance analysis indicates potential questions, it then becomes imperative to assess the fuel pin design and the proposed operating strategies to reduce the probability of clad failure and the associated release of radioactive fission products into the primary coolant system. Applying the updated code to anticipated fuel and reactor designs, which would be used for weapons MOX fuel in the US, and analyzing the performance of the WWER-100 fuel for Russian weapons plutonium disposition are addressed in this report. The COMETHE code was found to do an excellent job in predicting fuel central temperatures. Also, despite minor predicted differences in thermo-mechanical behavior of MOX and UO{sub 2} fuels, the preliminary estimate indicated that, during normal reactor operations, these deviations remained within limits foreseen by fuel pin design.

Alvis, J.; Bellanger, P.; Medvedev, P.G.; Peddicord, K.L. [Texas A and M Univ., College Station, TX (United States). Nuclear Engineering Dept.; Gellene, G.I. [Texas Tech Univ., Lubbock, TX (United States). Dept. of Chemistry and Biochemistry

1999-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "lighting manufacturing water" 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

Qualification Requirements of Guided Ultrasonic Waves for Inspection of Piping in Light Water Reactors  

SciTech Connect (OSTI)

Guided ultrasonic waves (GUW) are being increasingly used for both NDT and monitoring of piping. GUW offers advantages over many conventional NDE technologies due to the ability to inspect large volumes of piping components without significant removal of thermal insulation or protective layers. In addition, regions rendered inaccessible to more conventional NDE technologies may be more accessible using GUW techniques. For these reasons, utilities are increasingly considering the use of GUWs for performing the inspection of piping components in nuclear power plants. GUW is a rapidly evolving technology and its usage for inspection of nuclear power plant components requires refinement and qualification to ensure it is able to achieve consistent and acceptable levels of performance. This paper will discuss potential requirements for qualification of GUW techniques for the inspection of piping components in light water reactors (LWRs). The Nuclear Regulatory Commission has adopted ASME Boiler and Pressure Vessel Code requirements in Sections V, III, and XI for nondestructive examination methods, fabrication inspections, and pre-service and in-service inspections. A Section V working group has been formed to place the methodology of GUW into the ASME Boiler and Pressure Vessel Code but no requirements for technique, equipment, or personnel exist in the Code at this time.

Meyer, Ryan M.; Ramuhalli, Pradeep; Doctor, Steven R.; Bond, Leonard J.

2013-08-01T23:59:59.000Z

202

Advanced Fuels Campaign Light Water Reactor Accident Tolerant Fuel Performance Metrics Executive Summary  

SciTech Connect (OSTI)

Research and development (R&D) activities on advanced, higher performance Light Water Reactor (LWR) fuels have been ongoing for the last few years. Following the unfortunate March 2011 events at the Fukushima Nuclear Power Plant in Japan, the R&D shifted toward enhancing the accident tolerance of LWRs. Qualitative attributes for fuels with enhanced accident tolerance, such as improved reaction kinetics with steam resulting in slower hydrogen generation rate, provide guidance for the design and development of fuels and cladding with enhanced accident tolerance. A common set of technical metrics should be established to aid in the optimization and down selection of candidate designs on a more quantitative basis. “Metrics” describe a set of technical bases by which multiple concepts can be fairly evaluated against a common baseline and against one another. This report describes a proposed technical evaluation methodology that can be applied to evaluate the ability of each concept to meet performance and safety goals relative to the current UO2 – zirconium alloy system and relative to one another. The resultant ranked evaluation can then inform concept down-selection, such that the most promising accident tolerant fuel design option(s) can continue to be developed toward qualification.

Shannon Bragg-Sitton

2014-02-01T23:59:59.000Z

203

Environmentally assisted cracking in light water reactors. Semiannual report, July 1998-December 1998.  

SciTech Connect (OSTI)

This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally assisted cracking (EAC) in light water reactors from July 1998 to December 1998. Topics that have been investigated include (a) environmental effects on fatigue S-N behavior of primary pressure boundary materials, (b) irradiation-assisted stress corrosion cracking of austenitic stainless steels (SSs), and (c) EAC of Alloys 600 and 690. Fatigue tests have been conducted to determine the crack initiation and crack growth characteristics of austenitic SSs in LWR environments. Procedures are presented for incorporating the effects of reactor coolant environments on the fatigue life of pressure vessel and piping steels. Slow-strain-rate tensile tests and posttest fractographic analyses were conducted on several model SS alloys irradiated to {approx}0.3 and 0.9 x 10{sup 21} n {center_dot} cm{sup -2} (E > 1 MeV) in helium at 289 C in the Halden reactor. The results have been used to determine the influence of alloying and impurity elements on the susceptibility of these steels to irradiation-assisted stress corrosion cracking. Fracture toughness J-R curve tests were also conducted on two heats of Type 304 SS that were irradiated to {approx}0.3 x 10{sup 21} n {center_dot} cm{sup -2} in the Halden reactor. Crack-growth-rate tests have been conducted on compact-tension specimens of Alloys 600 and 690 under constant load to evaluate the resistance of these alloys to stress corrosion cracking in LWR environments.

Chopra, O. K.; Chung, H. M.; Gruber, E. E.; Kassner, T. F.; Ruther, W. E.; Shack, W. J.; Smith, J. L.; Soppet, W. K.; Strain; R. V. (Energy Technology); ( APS-USR)

1999-10-01T23:59:59.000Z

204

Light Water Reactor Sustainability Research and Development Program Plan -- Fiscal Year 2009–2013  

SciTech Connect (OSTI)

Nuclear power has reliably and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. By the year 2030, domestic demand for electrical energy is expected to grow to levels of 16 to 36% higher than 2007 levels. At the same time, most currently operating nuclear power plants will begin reaching the end of their 60-year operating licenses. If current operating nuclear power plants do not operate beyond 60 years, the total fraction of generated electrical energy from nuclear power will begin to decline—even with the expected addition of new nuclear generating capacity. The oldest commercial plants in the United States reached their 40th anniversary this year. U.S. regulators have begun considering extended operations of nuclear power plants and the research needed to support long-term operations. The Light Water Reactor Sustainability (LWRS) Research and Development (R&D) Program, developed and sponsored by the Department of Energy, is performed in close collaboration with industry R&D programs. The purpose of the LWRS R&D Program is to provide technical foundations for licensing and managing long-term, safe and economical operation of the current operating nuclear power plants. The LWRS R&D Program vision is captured in the following statements: Existing operating nuclear power plants will continue to safely provide clean and economic electricity well beyond their first license- extension period, significantly contributing to reduction of United States and global carbon emissions, enhancement of national energy security, and protection of the environment. There is a comprehensive technical basis for licensing and managing the long-term, safe, economical operation of nuclear power plants. Sustaining the existing operating U.S. fleet also will improve its international engagement and leadership on nuclear safety and security issues.

Idaho National Laboratory

2009-12-01T23:59:59.000Z

205

Light Water Reactor Sustainability Program A Reference Plan for Control Room Modernization: Planning and Analysis Phase  

SciTech Connect (OSTI)

The U.S. Department of Energy’s Light Water Reactor Sustainability (LWRS) program is collaborating with a U.S. nuclear utility to bring about a systematic fleet-wide control room modernization. To facilitate this upgrade, a new distributed control system (DCS) is being introduced into the control rooms of these plants. The DCS will upgrade the legacy plant process computer and emergency response facility information system. In addition, the DCS will replace an existing analog turbine control system with a display-based system. With technology upgrades comes the opportunity to improve the overall human-system interaction between the operators and the control room. To optimize operator performance, the LWRS Control Room Modernization research team followed a human-centered approach published by the U.S. Nuclear Regulatory Commission. NUREG-0711, Rev. 3, Human Factors Engineering Program Review Model (O’Hara et al., 2012), prescribes four phases for human factors engineering. This report provides examples of the first phase, Planning and Analysis. The three elements of Planning and Analysis in NUREG-0711 that are most crucial to initiating control room upgrades are: • Operating Experience Review: Identifies opportunities for improvement in the existing system and provides lessons learned from implemented systems. • Function Analysis and Allocation: Identifies which functions at the plant may be optimally handled by the DCS vs. the operators. • Task Analysis: Identifies how tasks might be optimized for the operators. Each of these elements is covered in a separate chapter. Examples are drawn from workshops with reactor operators that were conducted at the LWRS Human System Simulation Laboratory HSSL and at the respective plants. The findings in this report represent generalized accounts of more detailed proprietary reports produced for the utility for each plant. The goal of this LWRS report is to disseminate the technique and provide examples sufficient to serve as a template for other utilities’ projects for control room modernization.

Jacques Hugo; Ronald Boring; Lew Hanes; Kenneth Thomas

2013-09-01T23:59:59.000Z

206

Advanced Fuel Cycle Economic Analysis of Symbiotic Light-Water Reactor and Fast Burner Reactor Systems  

SciTech Connect (OSTI)

The Advanced Fuel Cycle Economic Analysis of Symbiotic Light-Water Reactor and Fast Burner Reactor Systems, prepared to support the U.S. Advanced Fuel Cycle Initiative (AFCI) systems analysis, provides a technology-oriented baseline system cost comparison between the open fuel cycle and closed fuel cycle systems. The intent is to understand their overall cost trends, cost sensitivities, and trade-offs. This analysis also improves the AFCI Program’s understanding of the cost drivers that will determine nuclear power’s cost competitiveness vis-a-vis other baseload generation systems. The common reactor-related costs consist of capital, operating, and decontamination and decommissioning costs. Fuel cycle costs include front-end (pre-irradiation) and back-end (post-iradiation) costs, as well as costs specifically associated with fuel recycling. This analysis reveals that there are large cost uncertainties associated with all the fuel cycle strategies, and that overall systems (reactor plus fuel cycle) using a closed fuel cycle are about 10% more expensive in terms of electricity generation cost than open cycle systems. The study concludes that further U.S. and joint international-based design studies are needed to reduce the cost uncertainties with respect to fast reactor, fuel separation and fabrication, and waste disposition. The results of this work can help provide insight to the cost-related factors and conditions needed to keep nuclear energy (including closed fuel cycles) economically competitive in the U.S. and worldwide. These results may be updated over time based on new cost information, revised assumptions, and feedback received from additional reviews.

D. E. Shropshire

2009-01-01T23:59:59.000Z

207

Advanced Fuels Campaign Light Water Reactor Accident Tolerant Fuel Performance Metrics  

SciTech Connect (OSTI)

The safe, reliable and economic operation of the nation’s nuclear power reactor fleet has always been a top priority for the United States’ nuclear industry. As a result, continual improvement of technology, including advanced materials and nuclear fuels, remains central to industry’s success. Decades of research combined with continual operation have produced steady advancements in technology and yielded an extensive base of data, experience, and knowledge on light water reactor (LWR) fuel performance under both normal and accident conditions. In 2011, following the Great East Japan Earthquake, resulting tsunami, and subsequent damage to the Fukushima Daiichi nuclear power plant complex, enhancing the accident tolerance of LWRs became a topic of serious discussion. As a result of direction from the U.S. Congress, the U.S. Department of Energy Office of Nuclear Energy (DOE-NE) initiated an Accident Tolerant Fuel (ATF) Development program. The complex multiphysics behavior of LWR nuclear fuel makes defining specific material or design improvements difficult; as such, establishing qualitative attributes is critical to guide the design and development of fuels and cladding with enhanced accident tolerance. This report summarizes a common set of technical evaluation metrics to aid in the optimization and down selection of candidate designs. As used herein, “metrics” describe a set of technical bases by which multiple concepts can be fairly evaluated against a common baseline and against one another. Furthermore, this report describes a proposed technical evaluation methodology that can be applied to assess the ability of each concept to meet performance and safety goals relative to the current UO2 – zirconium alloy system and relative to one another. The resultant ranked evaluation can then inform concept down-selection, such that the most promising accident tolerant fuel design option(s) can continue to be developed for lead test rod or lead test assembly insertion into a commercial reactor within the desired timeframe (by 2022).

Brad Merrill; Melissa Teague; Robert Youngblood; Larry Ott; Kevin Robb; Michael Todosow; Chris Stanek; Mitchell Farmer; Michael Billone; Robert Montgomery; Nicholas Brown; Shannon Bragg-Sitton

2014-02-01T23:59:59.000Z

208

Nuclear Systems Enhanced Performance Program, Maintenance Cycle Extension in Advanced Light Water Reactor Design  

SciTech Connect (OSTI)

A renewed interest in new nuclear power generation in the US has spurred interest in developing advanced reactors with features which will address the public's concerns regarding nuclear generation. However, it is economic performance which will dictate whether any new orders for these plants will materialize. Economic performance is, to a great extent, improved by maximizing the time that the plant is on-line generating electricity relative to the time spent off-line conducting maintenance and refueling. Indeed, the strategy for the advanced light water reactor plant IRIS (International Reactor, Innovative and Secure) is to utilize an eight year operating cycle. This report describes a formalized strategy to address, during the design phase, the maintenance-related barriers to an extended operating cycle. The top-level objective of this investigation was to develop a methodology for injecting component and system maintainability issues into the reactor plant design process to overcome these barriers. A primary goal was to demonstrate the applicability and utility of the methodology in the context of the IRIS design. The first step in meeting the top-level objective was to determine the types of operating cycle length barriers that the IRIS design team is likely to face. Evaluation of previously identified regulatory and investment protection surveillance program barriers preventing a candidate operating PWR from achieving an extended (48 month) cycle was conducted in the context of the IRIS design. From this analysis, 54 known IRIS operating cycle length barriers were identified. The resolution methodology was applied to each of these barriers to generate design solution alternatives for consideration in the IRIS design. The methodology developed has been demonstrated to narrow the design space to feasible design solutions which enable a desired operating cycle length, yet is general enough to have broad applicability. Feedback from the IRIS design team indicates that the proposed solutions to the investigated operating cycle length barriers are both feasible and consistent with sound design practice.

Professor Neill Todreas

2001-10-01T23:59:59.000Z

209

MWCNT/WO{sub 3} nanocomposite photoanode for visible light induced water splitting  

SciTech Connect (OSTI)

The Multi-walled carbon nanotube (MWCNT)/WO{sub 3} nanocomposite thin films with different MWCNT’s weight percentages were prepared by sol–gel method as visible light induced photoanode in water splitting reaction. Weight percentage of MWCNT in the all nanocomposite thin films was confirmed by TGA/DSC analysis. According to XPS analysis, oxygenated groups at the surface of the MWCNT and stoichiometric formation of WO{sub 3} thin films were determined, while the crystalline structure of the nanocomposite samples was studied by XRD indicating (0 0 2) peak of MWCNT in the monoclinic phase of WO{sub 3}. The influence of different weight percentage (wt%) of MWCNT on WO{sub 3} photoactivity showed that the electron conductivity, charge transfer and electron life time had improved as compared with the pure WO{sub 3}. Based on linear sweep voltammetry and chronoamperometry measurements, the (1 wt%) MWCNT/WO{sub 3} nanocomposite thin films photoanode has a maximum photocurrent density of ?4.5 A/m{sup 2} and electron life time of about 57 s. - Graphical abstract: Photocurrent density versus time at constant potential (0.7 V) for the WO{sub 3} films containing different MWCNT weight percentages annealed at 400 °C under 1000 Wm{sup ?2} visible photo-illumination. Display Omitted - Highlights: • MWCNT/ WO{sub 3} nanocomposite thin films were synthesized using sol–gel derived method. • TGA/DSC confirmed the weight percentage of MWCNT in the all nanocomposite thin films. • XPS analysis revealed that WO{sub 3} was attached on the oxygenated group of MWCNT surface. • The Highest Photoelectrochemical activity is achieved for (1 wt%)MWCNT/WO{sub 3} thin film.

Yousefzadeh, Samira [Physics Department, Sharif University of Technology, P.O. Box 11155-9161, Tehran (Iran, Islamic Republic of); Reyhani, Ali [Physics Department, Faculty of Science, Imam Khomeini International University, P.O. Box 34149-16818, Qazvin (Iran, Islamic Republic of); Naseri, Naimeh [Physics Department, Sharif University of Technology, P.O. Box 11155-9161, Tehran (Iran, Islamic Republic of); Moshfegh, Alireza Z., E-mail: moshfegh@sharif.edu [Physics Department, Sharif University of Technology, P.O. Box 11155-9161, Tehran (Iran, Islamic Republic of); Institute for Nanoscience and Nanotechnology, Sharif University of Technology, P.O. Box 14588-89694, Tehran (Iran, Islamic Republic of)

2013-08-15T23:59:59.000Z

210

Nondestructive Examination (NDE) Reliability for Inservice Inspection of Light Water Reactors. Semiannual report, October 1990--March 1991: Volume 13  

SciTech Connect (OSTI)

The Evaluation and Improvement of NDE Reliability for Inservice Inspection of Light Water Reactors (NDE Reliability) Program at the Pacific Northwest Laboratory was established by the Nuclear Regulatory Commission to determine the reliability of current inservice inspection (ISI) techniques and to develop recommendations that will ensure a suitably high inspection reliability. The objectives of this program include determining the reliability of ISI performed on the primary systems of commercial light-water reactors (LWRs); using probabilistic fracture mechanics analysis to determine the impact of NDE unreliability on system safety; and evaluating reliability improvements that can be achieved with improved and advanced technology. A final objective is to formulate recommended revisions to the Regulatory and ASME Code requirements, based on material properties, service conditions, and NDE uncertainties.

Doctor, S.R.; Good, M.S.; Heasler, P.G.; Hockey, R.L.; Simonen, F.A.; Spanner, J.C.; Taylor, T.T.; Vo, T.V. [Pacific Northwest Lab., Richland, WA (United States)

1992-07-01T23:59:59.000Z

211

LIGHT WATER REACTOR SUSTAINABILITY PROGRAM ADVANCED INSTRUMENTATION, INFORMATION, AND CONTROL SYSTEMS TECHNOLOGIES TECHNICAL PROGRAM PLAN FOR 2013  

SciTech Connect (OSTI)

Reliable instrumentation, information, and control (II&C) systems technologies are essential to ensuring safe and efficient operation of the U.S. light water reactor (LWR) fleet. These technologies affect every aspect of nuclear power plant (NPP) and balance-of-plant operations. In 1997, the National Research Council conducted a study concerning the challenges involved in modernization of digital instrumentation and control systems in NPPs. Their findings identified the need for new II&C technology integration.

Hallbert, Bruce; Thomas, Ken

2014-07-01T23:59:59.000Z

212

Utilizing Daylighting Controls in a Manufacturing Facility  

E-Print Network [OSTI]

Utilizing Daylighting Controls in a Manufacturing Facility Som S. Shrestha Dr. Gregory M. Maxwell PhD Candidate Associate Professor som@iastate.edu gmaxwell@iastate.edu Iowa State University Ames, IA ABSTRACT Opportunities exist... to reduce artificial lighting in manufacturing facilities which have skylights and/or fenestration that provide sufficient quantities of daylight to the work space. Using photometric sensors to measure the illuminance in the space, artificial lights can...

Shrestha, S. S.; Maxwell, G. M.

213

Distribution of trace elements in waters and sediments of the Seversky Donets  

E-Print Network [OSTI]

are affected by the extensive multiple water uses (iron ore-mining processes, heavy and light manufacturing, power, industrial and drinking water supply infrastructures, agriculture, aquaculture) and urban inputsDistribution of trace elements in waters and sediments of the Seversky Donets transboundary

Paris-Sud XI, Université de

214

Environmentally assisted cracking in light water reactors : semiannual report, July 2000 - December 2000.  

SciTech Connect (OSTI)

This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally assisted cracking (EAC) in light water reactors (LWRs) from July 2000 to December 2000. Topics that have been investigated include (a) environmental effects on fatigue S-N behavior of primary pressure boundary materials, (b) irradiation-assisted stress corrosion cracking (IASCC) of austenitic stainless steels (SSs), and (c) EAC of Alloys 600 and 690. The fatigue strain-vs.-life data are summarized for the effects of various material, loading, and environmental parameters on the fatigue lives of carbon and low-alloy steels and austenitic SSs. Effects of the reactor coolant environment on the mechanism of fatigue crack initiation are discussed. Two methods for incorporating the effects of LWR coolant environments into the ASME Code fatigue evaluations are presented. Slow-strain-rate tensile tests and posttest fractographic analyses were conducted on several model SS alloys irradiated to {approx}0.9 x 10{sup 21} n {center_dot} cm{sup -2} (E > 1 MeV) in He at 289 C in the Halden reactor. The results were used to determine the influence of alloying and impurity elements on the susceptibility of these steels to IASCC. A fracture toughness J-R curve test was conducted on a commercial heat of Type 304 SS that was irradiated to {approx}2.0 x 10{sup 21} n {center_dot} cm{sup -2} in the Halden reactor. The results were compared with the data obtained earlier on steels irradiated to 0.3 and 0.9 x 10{sup 21} n {center_dot} cm{sup -2} (E > 1 MeV) (0.45 and 1.35 dpa). Neutron irradiation at 288 C was found to decrease the fracture toughness of austenitic SSs. Tests were conducted on compact-tension specimens of Alloy 600 under cyclic loading to evaluate the enhancement of crack growth rates in LWR environments. Then, the existing fatigue crack growth data on Alloys 600 and 690 were analyzed to establish the effects of temperature, load ratio, frequency, and stress intensity range on crack growth rates in air.

Chopra, O. K.; Chung, H. M.; Gruber, E. E.; Shack, W. J.; Soppet, W. K.; Strain, R. V.; Energy Technology

2002-04-01T23:59:59.000Z

215

The infusion of intelligence that transforms the way industries conceptualize, design and operate the manufacturing enterprise.  

E-Print Network [OSTI]

Intelligence & Collaborative Manufacturing Green Light Analyze - to put into production Make ­ right the manufacturing enterprise. Smart Manufacturing as a Real-Time Networked Information Enterprise Jim Davis UCLA://smartmanufacturingcoalition.org http://smartmanufacturing.com #12;What is Smart Manufacturing? Smart Manufacturing enables all

Grossmann, Ignacio E.

216

Research and Development of High Temperature Light Water Cooled Reactor Operating at Supercritical-Pressure in Japan  

SciTech Connect (OSTI)

This paper summarizes the status and future plans of research and development of the high temperature light water cooled reactor operating at supercritical-pressure in Japan. It includes; the concept development; material for the fuel cladding; water chemistry under supercritical pressure; thermal hydraulics of supercritical fluid; and the conceptual design of core and plant system. Elements of concept development of the once-through coolant cycle reactor are described, which consists of fuel, core, reactor and plant system, stability and safety. Material studies include corrosion tests with supercritical water loops and simulated irradiation tests using a high-energy transmission electron microscope. Possibilities of oxide dispersion strengthening steels for the cladding material are studied. The water chemistry research includes radiolysis and kinetics of supercritical pressure water, influence of radiolysis and radiation damage on corrosion and behavior on the interface between water and material. The thermal hydraulic research includes heat transfer tests of single tube, single rod and three-rod bundles with a supercritical Freon loop and numerical simulations. The conceptual designs include core design with a three-dimensional core simulator and sub-channel analysis, and balance of plant. (authors)

Yoshiaki Oka [Nuclear Engineering Research Laboratory, The University of Tokyo, 7-3-1, Hongo, Bunkyo-ku, Tokyo, 112-0006 (Japan); Katsumi Yamada [Isogo Nuclear Engineering Center, Toshiba Corporation, 8, Shinsugita-cho, Isogo-ku, Yokohama, 235-8523 (Japan)

2004-07-01T23:59:59.000Z

217

E-Print Network 3.0 - abb-ce light water Sample Search Results  

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

Supplier Beginning in 1999... , community water supply systems must provide an annual report describ- ing the quality of their drinking Source: Fernndez-Juricic, Esteban -...

218

Materials Science and Technology Division Light-Water-Reactor Safety Research Program. Volume 4. Quarterly progress report, October-December 1983  

SciTech Connect (OSTI)

The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors, Transient Fuel Response and Fission Product Release, Clad Properties for Code Verification, and Long-Term Embrittlement of Cast Duplex Stainless Steels in LWR Systems.

Not Available

1984-08-01T23:59:59.000Z

219

Advanced Manufacturing | Department of Energy  

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

Better Buildings, Better Plants Clean Energy Manufacturing Initiative Combined Heat and Power Innovative Manufacturing Initiative National Network for Manufacturing Innovation...

220

Manufacturing Battle Creek  

E-Print Network [OSTI]

Computer simulation Facilities design Finite element analysis Green manufacturing Industrial materialsManufacturing Research Center Kalamazoo Battle Creek The College of Engineering and Applied Sciences The Supporting manufacturing industries by providing opportunities for collaboration with faculty

de Doncker, Elise

Note: This page contains sample records for the topic "lighting manufacturing water" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
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We encourage you to perform a real-time search of NLEBeta
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221

Light Water Reactor Sustainability Program Grizzly Year-End Progress Report  

SciTech Connect (OSTI)

The Grizzly software application is being developed under the Light Water Reactor Sustainability (LWRS) program to address aging and material degradation issues that could potentially become an obstacle to life extension of nuclear power plants beyond 60 years of operation. Grizzly is based on INL’s MOOSE multiphysics simulation environment, and can simultaneously solve a variety of tightly coupled physics equations, and is thus a very powerful and flexible tool with a wide range of potential applications. Grizzly, the development of which was begun during fiscal year (FY) 2012, is intended to address degradation in a variety of critical structures. The reactor pressure vessel (RPV) was chosen for an initial application of this software. Because it fulfills the critical roles of housing the reactor core and providing a barrier to the release of coolant, the RPV is clearly one of the most safety-critical components of a nuclear power plant. In addition, because of its cost, size and location in the plant, replacement of this component would be prohibitively expensive, so failure of the RPV to meet acceptance criteria would likely result in the shutting down of a nuclear power plant. The current practice used to perform engineering evaluations of the susceptibility of RPVs to fracture is to use the ASME Master Fracture Toughness Curve (ASME Code Case N-631 Section III). This is used in conjunction with empirically based models that describe the evolution of this curve due to embrittlement in terms of a transition temperature shift. These models are based on an extensive database of surveillance coupons that have been irradiated in operating nuclear power plants, but this data is limited to the lifetime of the current reactor fleet. This is an important limitation when considering life extension beyond 60 years. The currently available data cannot be extrapolated with confidence further out in time because there is a potential for additional damage mechanisms (i.e. late blooming phases) to become active later in life beyond the current operational experience. To develop a tool that can eventually serve a role in decision-making, it is clear that research and development must be perfomed at multiple scales. At the engineering scale, a multiphysics analysis code that can capture the thermomechanical response of the RPV under accident conditions, including detailed fracture mechanics evaluations of flaws with arbitrary geometry and orientation, is needed to assess whether the fracture toughness, as defined by the master curve, including the effects of embrittlement, is exceeded. At the atomistic scale, the fundamental mechanisms of degradation need to be understood, including the effects of that degradation on the relevant material properties. In addition, there is a need to better understand the mechanisms leading to the transition from ductile to brittle fracture through improved continuum mechanics modeling at the fracture coupon scale. Work is currently being conducted at all of these levels with the goal of creating a usable engineering tool informed by lower length-scale modeling. This report summarizes progress made in these efforts during FY 2013.

Benjamin Spencer; Yongfeng Zhang; Pritam Chakraborty; S. Bulent Biner; Marie Backman; Brian Wirth; Stephen Novascone; Jason Hales

2013-09-01T23:59:59.000Z

222

LED Manufacturing Process Modifications Will Boost Quality and  

E-Print Network [OSTI]

2012 The Issue Highly energyefficient LightEmitting Diode (LED) lighting products have made great process that will enable LED manufacturers to produce higher quality, energyefficient products at lower

223

Visible Light-Driven Water Oxidation by Ir oxide Clusters Coupledto Single Cr Centers in Mesoporous Silica  

SciTech Connect (OSTI)

Visible light-induced water oxidation has been demonstrated at an Ir oxide nanocluster coupled to a single Cr{sup VI} site on the pore surface of MCM-41 mesoporous silica. The photocatalytic unit was assembled by the reaction of surface Cr=O groups with Ir(acac){sub 3} precursor followed by calcination at 300 C and bond formation monitored by FT-Raman and FT-IR spectroscopy. High-resolution Z-contrast electron micrographs of the calcined material combined with energy-dispersive X-ray spot analysis confirmed the occlusion of Ir oxide nanoparticles inside the mesopores. Oxygen evolution of an aqueous suspension of the Ir{sub x}O{sub y}-CrMCM-41 upon visible light irradiation of the Cr{sup VI}-O ligand-to-metal charge-transfer absorption was monitored mass-spectrometrically. Comparison of the product yields for samples with low Cr content (Cr/Si {le} 0.02) and high Cr content (Cr/Si = 0.05) indicates that only isolated Cr centers are capable of extracting electrons from Ir oxide clusters, while di- or polychromate species are not. Water oxidation at a multielectron-transfer catalyst coupled to a single metal center has not been demonstrated before. The ability to drive water oxidation with a single metal center as electron pump offers opportunities for coupling the oxygen-evolving photocatalytic unit to reducing sites in the nanoporous scaffold.

Nakamura, Ryuhei; Frei, Heinz

2006-07-10T23:59:59.000Z

224

Environmentally assisted cracking in light-water reactors: Semi-annual report, January--June 1997. Volume 24  

SciTech Connect (OSTI)

This report summarizes work performed by Argonne National Laboratory on fatigue and environmentally assisted cracking (EAC) in light water reactors from January 1997 to June 1997. Topics that have been investigated include (a) fatigue of carbon, low-alloy, and austenitic stainless steels (SSs) used in reactor piping and pressure vessels, (b) irradiation-assisted stress corrosion cracking of Types 304 and 304L SS, and (c) EAC of Alloys 600 and 690. Fatigue tests were conducted on ferritic and austenitic SSs in water that contained various concentrations of dissolved oxygen (DO) to determine whether a slow strain rate applied during various portions of a tensile-loading cycle is equally effective in decreasing fatigue life. Slow-strain-rate-tensile tests were conducted in simulated boiling water reactor (BWR) water at 288 C on SS specimens irradiated to a low fluence in the Halden reactor and the results were compared with similar data from a control-blade sheath and neutron-absorber tubes irradiated in BWRs to the same fluence level. Crack-growth-rate tests were conducted on compact-tension specimens from several heats of Alloys 600 and 690 in low-DO, simulated pressurized water reactor environments.

Chopra, O.K.; Chung, H.M.; Gruber, E.E. [Argonne National Lab., IL (United States)] [and others

1998-04-01T23:59:59.000Z

225

Metrics for Sustainable Manufacturing  

E-Print Network [OSTI]

a system or process in maintaining a sustainable level of afor manufacturing processes to achieve truly sustainablesustainable phase of the automobile manufacturing process

Reich-Weiser, Corinne; Vijayaraghavan, Athulan; Dornfeld, David

2008-01-01T23:59:59.000Z

226

Silicon carbide performance as cladding for advanced uranium and thorium fuels for light water reactors  

E-Print Network [OSTI]

There has been an ongoing interest in replacing the fuel cladding zirconium-based alloys by other materials to reduce if not eliminate the autocatalytic and exothermic chemical reaction with water and steam at above 1,200 ...

Sukjai, Yanin

2014-01-01T23:59:59.000Z

227

Light-water-reactor safety research program. Quarterly progress report, January-March 1980  

SciTech Connect (OSTI)

This progress report summarizes the Argonne National Laboratory work performed during January, February, and March 1980 on water-reactor-safety problems. The research and development area covered is Transient Fuel Response and Fission-Product Release.

Massey, W.E.; Kyger, J.A.

1980-08-01T23:59:59.000Z

228

Light-water-reactor safety research program: quarterly progress report, July-September, 1980  

SciTech Connect (OSTI)

The progress report summarizes the Argonne National Laboratory work performed during July, August, and September 1980 on water-reactor-safety problems. The research and development area covered is Transient Fuel Response and Fission-product Release.

Massey, W.E.; Till, C.E.

1981-04-01T23:59:59.000Z

229

Feasibility Study of Supercritical Light Water Cooled Reactors for Electric Power Production  

SciTech Connect (OSTI)

The supercritical water reactor (SCWR) has been the object of interest throughout the nuclear Generation IV community because of its high potential: a simple, direct cycle, compact configuration; elimination of many traditional LWR components, operation at coolant temperatures much higher than traditional LWRs and thus high thermal efficiency. It could be said that the SWR was viewed as the water counterpart to the high temperature gas reactor.

Philip MacDonald; Jacopo Buongiorno; James Sterbentz; Cliff Davis; Robert Witt; Gary Was; J. McKinley; S. Teysseyre; Luca Oriani; Vefa Kucukboyaci; Lawrence Conway; N. Jonsson: Bin Liu

2005-02-13T23:59:59.000Z

230

Materials Science and Technology Division Light-Water-Reactor Safety Research Program. Quarterly progress report, April-June 1983. Volume 2  

SciTech Connect (OSTI)

The progress report summarizes the Argonne National Laboratory work performed during April, May, and June 1983 on water reactor safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors, Transient Fuel Response and Fission Product Release, Clad Properties for Code Verification, and Long-Term Embrittlement of Cast Duplex Stainless Steels in LWR Systems.

Shack, W.J.

1984-06-01T23:59:59.000Z

231

Materials Science and Technology Division light-water-reactor safety research program. Quarterly progress report, July-September 1983. Volume 3  

SciTech Connect (OSTI)

This progress report summarizes the Argonne National Laboratory work performed during July, August, and September 1983 on water reactor safety problems. The research and development areas covered are Environmentally Assisted Cracking in Light Water Reactors (reported elsewhere), Transient Fuel Response and Fission Product Release, Clad Properties for Code Verification, and Long-Term Embrittlement of Cast Duplex Stainless Steels in LWR Systems (reported elsewhere).

Not Available

1984-07-01T23:59:59.000Z

232

Nondestructive Examination (NDE) Reliability for Inservice Inspection of Light Water Reactors. Volume 14, Semiannual report, April 1991--September 1991  

SciTech Connect (OSTI)

The Evaluation and Improvement of NDE Reliability for Inservice Inspection of Light Water Reactors (NDE Reliability) Program at the Pacific Northwest Laboratory was established by the Nuclear Regulatory Commission to determine the reliability of current inservice inspection (ISI) techniques and to develop recommendations that will ensure a suitably high inspection reliability. The objectives of this program include determining the reliability of ISI performed on the primary systems of commercial light-water reactors (LWR`s); using probabilistic fracture mechanics analysis to determine the impact of NDE unreliability on system safety; and evaluating reliability improvements that can be achieved with improved and advanced technology. A final objective is to formulate recommended revisions to the Regulatory and ASME Code requirements, based on material properties, service conditions, and NDE uncertainties. The program scope is limited to ISI of the primary systems including the piping, vessel, and other components inspected in accordance with Section XI of the ASME Code. This is a progress report covering the programmatic work from April 1991 through September 1991.

Doctor, S.R.; Diaz, A.A.; Friley, J.R.; Good, M.S.; Greenwood, M.S.; Heasler, P.G.; Hockey, R.L.; Kurtz, R.J.; Simonen, F.A.; Spanner, J.C.; Taylor, T.T.; Vo, T.V. [Pacific Northwest Lab., Richland, WA (United States)

1992-07-01T23:59:59.000Z

233

Nondestructive Examination (NDE) Reliability for Inservice Inspection of Light Water Reactors. Volume 15, Semiannual report: October 1991--March 1992  

SciTech Connect (OSTI)

The Evaluation and Improvement of NDE Reliability for Inservice Inspection of Light Water Reactors (NDE Reliability) Program at the Pacific Northwest Laboratory was established by the Nuclear Regulatory Commission to determine the reliability of current inservice inspection (ISI) techniques and to develop recommendations that will ensure a suitably high inspection reliability. The objectives of this program include determining the reliability of ISI performed on the primary systems of commercial light-water reactors (LWRs); using probabilistic fracture mechanics analysis to determine the impact of NDE unreliability on system safety; and evaluating reliability improvements that can be achieved with improved and advanced technology. A final objective is to formulate recommended revisions to ASME Code and Regulatory requirements, based on material properties, service conditions, and NDE uncertainties. The program scope is limited to ISI of the primary systems including the piping, vessel, and other components inspected in accordance with Section XI of the ASME Code. This is a progress report covering the programmatic work from October 1991 through March 1992.

Doctor, S.R.; Diaz, A.A.; Friley, J.R. [Pacific Northwest Lab., Richland, WA (United States)

1993-09-01T23:59:59.000Z

234

Nondestructive Examination (NDE) Reliability for Inservice Inspection of Light Water Reactors. Semiannual report, April 1992--September 1992: Volume 16  

SciTech Connect (OSTI)

The Evaluation and Improvement of NDE Reliability for Inservice inspection of Light Water Reactors (NDE Reliability) Program at the Pacific Northwest Laboratory was established by the Nuclear Regulatory Commission to determine the reliability of current inservice inspection (ISI) techniques and to develop recommendations that will ensure a suitably high inspection reliability. The objectives of this program include determining the reliability of ISI performed on the primary systems of commercial light-water reactors (LWRs);using probabilistic fracture mechanics analysis to determine the impact of NDE unreliability on system safety; and evaluating reliability improvements that can be achieved with improved and advanced technology. A final objective is to formulate recommended revisions to the Regulatory and ASME Code requirements, based on material properties, service conditions, and NDE uncertainties. The program scope is limited to ISI of the primary systems including the piping, vessel and other components inspected in accordance with Section XI of the ASME Code. This is a programs report covering the programmatic work from April 1992 through September 1992.

Doctor, S.R.; Diaz, A.A.; Friley, J.R.; Greenwood, M.S.; Heasler, P.G.; Kurtz, R.J.; Simonen, F.A.; Spanner, J.C.; Vo, T.V. [Pacific Northwest Lab., Richland, WA (United States)

1993-11-01T23:59:59.000Z

235

Adaptive Management of Water Resources in Light of Future Climate Uncertainty  

SciTech Connect (OSTI)

Water resources managers have always had to make operational decisions in spite of a relatively high degree of uncertainty caused by changing climate, hydrologic, population, land use, socioeconomic, and other conditions. However, based on current climate change predictions and observations of current impacts of climate change or natural variability, the degree of uncertainty appears to be increasing drastically. By better understanding these uncertainties and their policy implications and by managing those uncertainties adaptively, water resources managers and policy makers can reduce the risk of not meeting their management goals and reduce the potential physical, biological and socioeconomic impacts associated with climate change/variation.

Gerald Sehlke; Mark Colosimo

2007-11-01T23:59:59.000Z

236

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

SciTech Connect (OSTI)

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

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

2001-07-15T23:59:59.000Z

237

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

SciTech Connect (OSTI)

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

Not Available

1993-05-13T23:59:59.000Z

238

Qualification requirements of guided ultrasonic waves for inspection of piping in light water reactors  

SciTech Connect (OSTI)

It is anticipated that guided ultrasonic wave (GUW) techniques will eventually see widespread application in the nuclear power industry as there are several near-term and future needs that could benefit from the availability of GUW technologies. Already, GUW techniques are receiving consideration for inspecting buried piping at nuclear power plants and future applications may include several Class 1 and 2 components. To accept the results of a nondestructive examination of safety critical components, the U.S. Nuclear Regulatory Commission requires that the examinations be performed using qualified equipment, personnel, and procedures. As the use of GUW techniques becomes more frequent, qualification may be required. Performance demonstration has been the approach to qualifying conventional NDE methods in the nuclear power industry. This paper highlights potential issues and research needs associated with facilitating GUW qualification for the nuclear power industry. Parametric studies of essential inspection parameters are necessary to understand their influence on inspection performance. The large volume sampling capability introduces several challenges for qualifying GUW techniques including the quantification of performance, potential interference caused by the presence of multiple flaws in the inspection region, and the practicality of manufacturing several large qualification specimens. Computer simulation may have a significant role in reducing the experimental burden associated with qualifying GUW techniques for nuclear power plant examinations.

Meyer, R. M.; Ramuhalli, P.; Doctor, S. R. [Applied Physics, Pacific Northwest National Laboratory, Richland, WA 99352 (United States); Bond, L. J. [Center for Nondestructive Evaluation, Iowa State University, Ames, IA 50011 (United States)

2013-01-25T23:59:59.000Z

239

Status of the Norwegian thorium light water reactor (LWR) fuel development and irradiation test program  

SciTech Connect (OSTI)

Thorium based fuels offer several benefits compared to uranium based fuels and should thus be an attractive alternative to conventional fuel types. In order for thorium based fuel to be licensed for use in current LWRs, material properties must be well known for fresh as well as irradiated fuel, and accurate prediction of fuel behavior must be possible to make for both normal operation and transient scenarios. Important parameters are known for fresh material but the behaviour of the fuel under irradiation is unknown particularly for low Th content. The irradiation campaign aims to widen the experience base to irradiated (Th,Pu)O{sub 2} fuel and (Th,U)O{sub 2} with low Th content and to confirm existing data for fresh fuel. The assumptions with respect to improved in-core fuel performance are confirmed by our preliminary irradiation test results, and our fuel manufacture trials so far indicate that both (Th,U)O{sub 2} and (Th,Pu)O{sub 2} fuels can be fabricated with existing technologies, which are possible to upscale to commercial volumes.

Drera, S.S.; Bjork, K.I.; Kelly, J.F.; Asphjell, O. [Thor Energy AS: Sommerrogaten 13-15, Oslo, NO255 (Norway)

2013-07-01T23:59:59.000Z

240

Electrical, optical, and material characterizations of blue InGaN light emitting diodes submitted to reverse-bias stress in water vapor condition  

SciTech Connect (OSTI)

In this paper, we investigate degradation of InGaN/GaN light emitting diodes (LEDs) under reverse-bias operations in water vapor and dry air. To examine failure origins, electrical characterizations including current-voltage, breakdown current profiles, optical measurement, and multiple material analyses were performed. Our findings indicate that the diffusion of indium atoms in water vapor can expedite degradation. Investigation of reverse-bias stress can help provide insight into the effects of water vapor on LEDs.

Chen, Hsiang, E-mail: hchen@ncnu.edu.tw; Chu, Yu-Cheng; Chen, Yun-Ti; Chen, Chian-You [Department of Applied Materials and Optoelectronic Engineering, National Chi Nan University, No. 1, University Road, Puli, Nantou County 54561, Taiwan (China); Shei, Shih-Chang [Department of Electrical Engineering, National University of Tainan, No.33, Sec. 2, Shulin St., West Central Dist., Tainan City 70005, Taiwan (China)

2014-09-07T23:59:59.000Z

Note: This page contains sample records for the topic "lighting manufacturing water" 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

Measurements and simulations of polarization states of underwater light in clear oceanic waters  

E-Print Network [OSTI]

Remote Sensing Laboratory, The City College of the City University of New York, New York, New York 10031 under various atmospheric, surface, and water conditions, as well as solar and viewing geometries solar elevation. This implies that animals can use the DoLP signal for orientation. © 2011 Optical

Cummings, Molly E.

242

Photoassisted Overall Water Splitting in a Visible Light-Absorbing Dye-Sensitized Photoelectrochemical Cell  

E-Print Network [OSTI]

splitting system based on oxyni- tride semiconductor particles.4 In comparison, progress on overall water the heteroleptic ruthenium dye 1 to serve as both a sensitizer component and a molecular bridge to connect IrO2 ·nH2O particles to a metal oxide semiconductor. Phosphonates are chemically selective for TiO2

243

Light-Water-Reactor Safety Research Program. Quarterly progress report, October-December 1979  

SciTech Connect (OSTI)

This progress report summarizes the Argonne National Laboratory work performed during October, November, and December 1979 on water-reactor-safety problems. The research and development areas covered are: (1) Heat Transfer Coordination for LOCA Research Programs and (2) Transient Fuel Response and Fission-Product Release. 29 refs., 39 figs., 1 tab.

Massey, W.E.; Kyger, J.A.

1980-05-01T23:59:59.000Z

244

Light Water Reactor Fuel Cladding Research and Testing | ornl.gov  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: VegetationEquipment Surfaces and Interfaces Sample6, 2011 LawrenceEfeedstocks and the climateLife a9Light

245

SEIS for the Production of Tritium in a Commercial Light Water Reactor |  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared0 ResourceAwards SAGE Awards ,# , onLightThePrices andSEE HOW

246

Functional issues and environmental qualification of digital protection systems of advanced light-water nuclear reactors  

SciTech Connect (OSTI)

Issues of obsolescence and lack of infrastructural support in (analog) spare parts, coupled with the potential benefits of digital systems, are driving the nuclear industry to retrofit analog instrumentation and control (I&C) systems with digital and microprocessor-based systems. While these technologies have several advantages, their application to safety-related systems in nuclear power plants raises key issues relating to the systems` environmental qualification and functional reliability. To bound the problem of new I&C system functionality and qualification, the authors focused this study on protection systems proposed for use in ALWRs. Specifically, both functional and environmental qualification issues for ALWR protection system I&C were addressed by developing an environmental, functional, and aging data template for a protection division of each proposed ALWR design. By using information provided by manufacturers, environmental conditions and stressors to which I&C equipment in reactor protection divisions may be subjected were identified. The resulting data were then compared to a similar template for an instrument string typically found in an analog protection division of a present-day nuclear power plant. The authors also identified fiber-optic transmission systems as technologies that are relatively new to the nuclear power plant environment and examined the failure modes and age-related degradation mechanisms of fiber-optic components and systems. One reason for the exercise of caution in the introduction of software into safety-critical systems is the potential for common-cause failure due to the software. This study, however, approaches the functionality problem from a systems point of view. System malfunction scenarios are postulated to illustrate the fact that, when dealing with the performance of the overall integrated system, the real issues are functionality and fault tolerance, not hardware vs. software.

Korsah, K.; Clark, R.L.; Wood, R.T. [Oak Ridge National Lab., TN (United States)

1994-04-01T23:59:59.000Z

247

FEASIBILITY OF RECYCLING PLUTONIUM AND MINOR ACTINIDES IN LIGHT WATER REACTORS USING HYDRIDE FUEL  

SciTech Connect (OSTI)

The objective of this DOE NERI program sponsored project was to assess the feasibility of improving the plutonium (Pu) and minor actinide (MA) recycling capabilities of pressurized water reactors (PWRs) by using hydride instead of oxide fuels. There are four general parts to this assessment: 1) Identifying promising hydride fuel assembly designs for recycling Pu and MAs in PWRs 2) Performing a comprehensive systems analysis that compares the fuel cycle characteristics of Pu and MA recycling in PWRs using the promising hydride fuel assembly designs identified in Part 1 versus using oxide fuel assembly designs 3) Conducting a safety analysis to assess the likelihood of licensing hydride fuel assembly designs 4) Assessing the compatibility of hydride fuel with cladding materials and water under typical PWR operating conditions Hydride fuel was found to offer promising transmutation characteristics and is recommended for further examination as a possible preferred option for recycling plutonium in PWRs.

Greenspan, Ehud; Todreas, Neil; Taiwo, Temitope

2009-03-10T23:59:59.000Z

248

Showerhead Manufacturer Agrees to Civil Penalty to Resolve Enforcement...  

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

announced today, the manufacturer also agreed to cease all sales within the United States of showerheads that violate the Department's water conservation standards. Addthis...

249

DOE Institutes Enforcement Action against 4 Showerhead Manufacturers...  

Office of Environmental Management (EM)

to the Department of Energy that showerheads manufactured or distributed by these companies meet the applicable water conservation standard as required by the Energy Policy...

250

Manufacturing of Protected Lithium Electrodes for Advanced Lithium...  

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

Lithium Electrodes for Advanced Lithium-Air, Lithium-Water, and Lithium-Sulfur Batteries, April 2013 Manufacturing of Protected Lithium Electrodes for Advanced Lithium-Air,...

251

Water stress, temperature, and light effects on isoprene emission and photosynthesis of Kudzu leaves  

SciTech Connect (OSTI)

Kudzu (Pueraia lobata (Willd) Ohwi.) emits isoprene, a hydrocarbon which can significantly affect atmospheric chemistry. Isoprene emission under standard conditions of 1000 [mu]mol photons[center dot]M[sup [minus]2][center dot]S[sup [minus]1] and 30[degrees]C developed only after the leaf bad reached full expansion and was not maximal until up to two weeks past the point of full expansion of the leaf. Isoprene emission from kudzu was stimulated by increases in temperature and photon flux density (up to 3000 [mu]mol photons[center dot]m[sup [minus]2][center dot]s[sup [minus]1]). For unstressed plants, 20 % of the carbon fixed in photosynthesis was reemitted as isoprene at 1000 [mu]mol photons[center dot]m[sup [minus]2][center dot]S[sup [minus]1]. Following the relief of water stress, photosynthesis recovered to the prestress rate but isoprene emission increased up to five times the prestress rate. At 1000 [mu]mol photons[center dot]M[sup [minus]2][center dot]S[sup [minus]1] and 35[degrees]C, 67% of the carbon fixed in photosynthesis was reemitted as isoprene eight days after water stress. For some leaves the rate of isoprene emission exceeded 500 nmol[center dot]M[sup [minus]2][center dot]S[sup [minus]1], substantially higher than ever reported before. Leaves of plants grown at less than 20[degrees]C did not make isoprene until an inductive treatment was given. Withholding water from plants or keeping leaves at 30[degrees]C induced isoprene emission. The observation of rapid and dramatic changes in the rate of isoprene emission from leaves in response to water stress and temperature may indicate that isoprene emission improves the ability of plants to cope with these conditions. With the new information on temperature and water stress effects on isoprene emission we speculate on possible reasons for isoprene emission from plants.

Sharkey, T.D.; Loreto, F. (Univ. of Wisconsin, Madison (United States))

1993-05-01T23:59:59.000Z

252

LightManufacturing | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 No revision hasInformation Earth's Heat JumpInc Place:Keystone

253

Efficiency and stray light measurements and calculations of diffraction gratings for the Advanced Light Source  

SciTech Connect (OSTI)

Water-cooled gratings manufactured for spherical grating monochromators of the Advanced Light Source beamlines 7.0, 8.0, and 9.0 were measured with the laser plasma source and reflectometer in the Center for X-ray Optics at Lawrence Berkeley Laboratory. The square-wave gratings are ion milled into the polished electroless nickel surface after patterning by holographic photolithography. Absolute efficiency data are compared with exact electromagnetic theory calculation. Interorder stray light and groove depths can be estimated from the measurements.

McKinney, W.R.; Mossessian, D. (Accelerator and Fusion Research Division, Advanced Light Source, Lawrence Berkeley Laboratory, Berkeley, California 94720 (United States)); Gullikson, E. (Materials Sciences Division, Center for X-ray Optics, Lawrence Berkeley Laboratory, Berkeley, California 94720 (United States)); Heimann, P. (Accelerator and Fusion Research Division, Advanced Light Source, Lawrence Berkeley Laboratory, Berkeley, California 94720 (United States))

1995-02-01T23:59:59.000Z

254

Advanced Computational Thermal Fluid Physics (CTFP) and Its Assessment for Light Water Reactors and Supercritical Reactors  

SciTech Connect (OSTI)

Background: The ultimate goal of the study is the improvement of predictive methods for safety analyses and design of Generation IV reactor systems such as supercritical water reactors (SCWR) for higher efficiency, improved performance and operation, design simplification, enhanced safety and reduced waste and cost. The objective of this Korean / US / laboratory / university collaboration of coupled fundamental computational and experimental studies is to develop the supporting knowledge needed for improved predictive techniques for use in the technology development of Generation IV reactor concepts and their passive safety systems. The present study emphasizes SCWR concepts in the Generation IV program.

D.M. McEligot; K. G. Condie; G. E. McCreery; H. M. McIlroy; R. J. Pink; L.E. Hochreiter; J.D. Jackson; R.H. Pletcher; B.L. Smith; P. Vukoslavcevic; J.M. Wallace; J.Y. Yoo; J.S. Lee; S.T. Ro; S.O. Park

2005-10-01T23:59:59.000Z

255

Light Water Reactor Sustainability Program Risk-Informed Safety Margins Characterization (RISMC) PathwayTechnical Program Plan  

SciTech Connect (OSTI)

Safety is central to the design, licensing, operation, and economics of Nuclear Power Plants (NPPs). As the current Light Water Reactor (LWR) NPPs age beyond 60 years, there are possibilities for increased frequency of Systems, Structures, and Components (SSCs) degradations or failures that initiate safety-significant events, reduce existing accident mitigation capabilities, or create new failure modes. Plant designers commonly “over-design” portions of NPPs and provide robustness in the form of redundant and diverse engineered safety features to ensure that, even in the case of well-beyond design basis scenarios, public health and safety will be protected with a very high degree of assurance. This form of defense-in-depth is a reasoned response to uncertainties and is often referred to generically as “safety margin.” Historically, specific safety margin provisions have been formulated, primarily based on “engineering judgment.”

Curtis Smith; Cristian Rabiti; Richard Martineau

2012-11-01T23:59:59.000Z

256

Acoustic Emission and Guided Ultrasonic Waves for Detection and Continuous Monitoring of Cracks in Light Water Reactor Components  

SciTech Connect (OSTI)

Acoustic emission (AE) and guided ultrasonic waves (GUW) are considered for continuous monitoring and detection of cracks in Light Water Reactor (LWR) components. In this effort, both techniques are applied to the detection and monitoring of fatigue crack growth in a full scale pipe component. AE results indicated crack initiation and rapid growth in the pipe, and significant GUW responses were observed in response to the growth of the fatigue crack. After initiation, the crack growth was detectable with AE for approximately 20,000 cycles. Signals associated with initiation and rapid growth where distinguished based on total rate of activity and differences observed in the centroid frequency of hits. An intermediate stage between initiation and rapid growth was associated with significant energy emissions, though few hits. GUW exhibit a nearly monotonic trend with crack length with an exception of measurements obtained at 41 mm and 46 mm.

Meyer, Ryan M.; Coble, Jamie B.; Ramuhalli, Pradeep; Watson, Bruce E.; Cumblidge, Stephen E.; Doctor, Steven R.; Bond, Leonard J.

2012-06-28T23:59:59.000Z

257

The Application of Structural Materials Data From the BN-350 Fast Reactor to Life Extension of Light Water Reactors  

SciTech Connect (OSTI)

This paper describes the results of investigations of 08Cr16Ni11Mo3 (AISI 316 steel analogue) austenitic stainless steel irradiated in BN-350 breeder reactor at irradiation conditions close to that for Light Water Reactor (LWR) Internals. The pores were found in 08Cr16Ni11Mo3 steel irradiated at temperature 280 deg. C up to rather low damage 1.3 dpa and with dose rate 3.9 x 10{sup -9} dpa/s. There were obtained dose rate dependencies of yield strength, ultimate strength and ductility for 08Cr16Ni11Mo3 steel irradiated up to 7-13 dpa at 302-311 deg. C. These dependencies show a decrease in both yield strength and ultimate strength when dose rate decreases. There was observed an apparent decrease in total elongation when dose rate decreases, which was presumably connected with the pores formation in the steel at low dose rates. (authors)

Romanenko, O.G. [Nuclear Technology Safety Center, Liza Chaikina 4, Almaty 050020 (Kazakhstan); Kislitsin, S.B.; Maksimkin, O.P. [Institute of Nuclear Physics, 1 Ibragimova St., Almaty, 050032 (Kazakhstan); Shiganakov, Sh.B.; Chumakov, Ye.V. [Kazakhstan Atomic Energy Committee, Liza Chaikina 4, Almaty (Kazakhstan); Dumchev, I.V. [MAEC Kazatomprom, Aktau, 130000 (Kazakhstan)

2006-07-01T23:59:59.000Z

258

Computerized operating procedures for shearing and dissolution of segments from LWBR (Light Water Breeder Reactor) fuel rods  

SciTech Connect (OSTI)

This report presents two detailed computerized operating procedures developed to assist and control the shearing and dissolution of irradiated fuel rods. The procedures were employed in the destructive analysis of end-of-life fuel rods from the Light Water Breeder Reactor (LWBR) that was designed by the Westinghouse Electric Corporation Bettis Atomic Power Laboratory. Seventeen entire fuel rods from the end-of-life core of the LWBR were sheared into 169 precisely characterized segments, and more than 150 of these segments were dissolved during execution of the LWBR Proof-of-Breeding (LWBR-POB) Analytical Support Project at Argonne National Laboratory. The procedures illustrate our approaches to process monitoring, data reduction, and quality assurance during the LWBR-POB work.

Osudar, J.; Deeken, P.G.; Graczyk, D.G.; Fagan, J.E.; Martino, F.J.; Parks, J.E.; Levitz, N.M.; Kessie, R.W.; Leddin, J.M.

1987-05-01T23:59:59.000Z

259

Fundamental Understanding of Crack Growth in Structural Components of Generation IV Supercritical Light Water Reactors  

SciTech Connect (OSTI)

This work contributes to the design of safe and economical Generation-IV Super-Critical Water Reactors (SCWRs) by providing a basis for selecting structural materials to ensure the functionality of in-vessel components during the entire service life. During the second year of the project, we completed electrochemical characterization of the oxide film properties and investigation of crack initiation and propagation for candidate structural materials steels under supercritical conditions. We ranked candidate alloys against their susceptibility to environmentally assisted degradation based on the in situ data measure with an SRI-designed controlled distance electrochemistry (CDE) arrangement. A correlation between measurable oxide film properties and susceptibility of austenitic steels to environmentally assisted degradation was observed experimentally. One of the major practical results of the present work is the experimentally proven ability of the economical CDE technique to supply in situ data for ranking candidate structural materials for Generation-IV SCRs. A potential use of the CDE arrangement developed ar SRI for building in situ sensors monitoring water chemistry in the heat transport circuit of Generation-IV SCWRs was evaluated and proved to be feasible.

Iouri I. Balachov; Takao Kobayashi; Francis Tanzella; Indira Jayaweera; Palitha Jayaweera; Petri Kinnunen; Martin Bojinov; Timo Saario

2004-11-17T23:59:59.000Z

260

RRR Niobium Manufacturing Experience  

SciTech Connect (OSTI)

ATI Wah Chang has been manufacturing RRR niobium for more than 30 years using electron beam melting techniques. Fabricated forms include plate, sheet, foil, bar, rod and tubing. This paper provides manufacturing information.

Graham, Ronald A. [ATI Wah Chang, An Allegheny Technologies Company, Albany, Oregon 97321 (United States)

2007-08-09T23:59:59.000Z

Note: This page contains sample records for the topic "lighting manufacturing water" 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

Metrics for Sustainable Manufacturing  

E-Print Network [OSTI]

for implementing green manufacturing”. Trans. of NAMRI/SME,the imple- mentation of green manufacturing, where a wedgemanufacturing scope of the assessment. While it is always important in the development of green

Reich-Weiser, Corinne; Vijayaraghavan, Athulan; Dornfeld, David

2008-01-01T23:59:59.000Z

262

Direct Water Splitting under Visible Light with Nanostructured Hematite and WO3 Photoanodes and a GaInP2 Photocathode  

SciTech Connect (OSTI)

A p-GaInP{sub 2} photocathode was paired with nanostructured hematite and tungsten trioxide photoanodes to investigate the utility of these systems for direct water splitting under visible light illumination. For the hematite system, under illumination at open-circuit conditions, the potential of hematite shifts cathodically and that of the GaInP{sub 2} shifts anodically. Under short-circuit condition and visible light illumination, the combination of the two photoelectrodes can split water, though with a very low rate of a few {micro}A/cm{sup 2} even at an intensity of 1 W/cm{sup 2}. It was determined that the very low photocurrent from the hematite nanorod photoelectrode limits the short-circuit current of the two-photoelectrode combination. Similar potential shifts were observed with the nanostructured WO{sub 3}/GaInP{sub 2} combination. However, at light intensities below 0.2 W/cm{sup 2}, the short-circuited combination would not split water due to an insufficient potential difference. Above 0.2 W/cm{sup 2}, the combination can split water under visible light, with {approx}20 {micro}A/cm{sup 2} obtained at 1 W/cm{sup 2}. A linear photocurrent-light intensity relationship was observed and was attributed to efficient charge transfer and a low recombination of the charge carriers. The bandgap and the associated absorption limit of WO{sub 3} remain a challenge for a higher efficiency system.

Wang, H.; Deutsch, T.; Turner, J. A.

2008-01-01T23:59:59.000Z

263

Demonstration Assessment of Light-Emitting Diode Roadway Lighting on the FDR Drive in New York, New York  

SciTech Connect (OSTI)

This a report about a field study of light-emitting diodes street lights by four different manufacturers installed on the FDR Drive in New York City, NY.

Myer, Michael; Hazra, Oindrila; Kinzey, Bruce R.

2011-12-01T23:59:59.000Z

264

An economic analysis of a light and heavy water moderated reactor synergy: burning americium using recycled uranium  

SciTech Connect (OSTI)

An economic analysis is presented for a proposed synergistic system between 2 nuclear utilities, one operating light water reactors (LWR) and another running a fleet of heavy water moderated reactors (HWR). Americium is partitioned from LWR spent nuclear fuel (SNF) to be transmuted in HWRs, with a consequent averted disposal cost to the LWR operator. In return, reprocessed uranium (RU) is supplied to the HWRs in sufficient quantities to support their operation both as power generators and americium burners. Two simplifying assumptions have been made. First, the economic value of RU is a linear function of the cost of fresh natural uranium (NU), and secondly, plutonium recycling for a third utility running a mixed oxide (MOX) fuelled reactor fleet has been already taking place, so that the extra cost of americium recycling is manageable. We conclude that, in order for this scenario to be economically attractive to the LWR operator, the averted disposal cost due to partitioning americium from LWR spent fuel must exceed 214 dollars per kg, comparable to estimates of the permanent disposal cost of the high level waste (HLW) from reprocessing spent LWR fuel. (authors)

Wojtaszek, D.; Edwards, G. [Atomic Energy of Canada Ltd., Chalk River Laboratories, Chalk River, Ontario (Canada)

2013-07-01T23:59:59.000Z

265

LIGHTING RESEARCH PROGRAM Project 5.4 DALI Lighting Control Device Standard  

E-Print Network [OSTI]

LIGHTING RESEARCH PROGRAM Project 5.4 DALI Lighting Control Device Standard Development FINAL CONTROL DEVICE STANDARD PROPOSED BY NEMA ......10 TECHNICAL ASSESSMENT REPORT Electronics Co.; Al Lombardi, Leviton Manufacturing Co., Inc.; Mike Stein, Universal Lighting Technologies

266

Hollings Manufacturing Extension Partnership: Delivering Measurable Results to Manufacturing Clients  

E-Print Network [OSTI]

of services, from innovation strategies to process improvements to green manufacturing. MEP also worksHollings Manufacturing Extension Partnership: Delivering Measurable Results to Manufacturing Clients MEP · MANUFACTURING EXTENSION PARTNERSHIP NationalInstituteofStandardsandTechnology March2013

Perkins, Richard A.

267

A REVIEW OF LIGHT-WATER REACTOR SAFETY STUDIES. VOLUME 3 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

Charges Relating to Nuclear Reactor Safety," 1976, availablestudies of light-water nuclear reactor safety, emphasizingstudies of overall nuclear reactor safety have been

Nero, A.V.

2010-01-01T23:59:59.000Z

268

Mechanism of Irradiation Assisted Cracking of Core Components in Light Water Reactors  

SciTech Connect (OSTI)

The overall goal of the project is to determine the mechanism of irradiation assisted stress corrosion cracking (IASCC). IASCC has been linked to hardening, microstructural and microchemical changes during irradiation. Unfortunately, all of these changes occur simultaneously and at similar rates during irradiation, making attribution of IASCC to any one of these features nearly impossible to determine. The strategy set forth in this project is to develop means to separate microstructural from microchemical changes to evaluate each separately for their effect on IASCC. In the first part, post irradiation annealing (PIA) treatments are used to anneal the irradiated microstructure, leaving only radiation induced segregation (RIS) for evaluation for its contribution to IASCC. The second part of the strategy is to use low temperature irradiation to produce a radiation damage dislocation loop microstructure without radiation induced segregation in order to evaluate the effect of the dislocation microstructure alone. A radiation annealing model was developed based on the elimination of dislocation loops by vacancy absorption. Results showed that there were indeed, time-temperature annealing combinations that leave the radiation induced segregation profile largely unaltered while the dislocation microstructure is significantly reduced. Proton irradiation of 304 stainless steel irradiated with 3.2 MeV protons to 1.0 or 2.5 dpa resulted in grain boundary depletion of chromium and enrichment of nickel and a radiation damaged microstructure. Post irradiation annealing at temperatures of 500 ? 600°C for times of up to 45 min. removed the dislocation microstructure to a greater degree with increasing temperatures, or times at temperature, while leaving the radiation induced segregation profile relatively unaltered. Constant extension rate tensile (CERT) experiments in 288°C water containing 2 ppm O2 and with a conductivity of 0.2 mS/cm and at a strain rate of 3 x 10-7 s-1 showed that the IASCC susceptibility, as measured by the crack length per unit strain, decreased with very short anneals and was almost completely removed by an anneal at 500°C for 45 min. This annealing treatment removed about 15% of the dislocation microstructure and the irradiation hardening, but did not affect the grain boundary chromium depletion or nickel segregation, nor did it affect the grain boundary content of other minor impurities. These results indicate that RIS is not the sole controlling feature of IASCC in irradiated stainless steels in normal water chemistry. The isolation of the irradiated microstructure was approached using low temperature irradiation or combinations of low and high temperature irradiations to achieve a stable, irradiated microstructure without RIS. Experiments were successful in achieving a high degree of irradiation hardening without any evidence of RIS of either major or minor elements. The low temperature irradiations to doses up to 0.3 dpa at T<75°C were also very successful in producing hardening to levels considerably above that for irradiations conducted under nominal conditions of 1 dpa at 360°C. However, the microstructure consisted of an extremely fine dispersion of defect clusters of sizes that are not resolvable by either transmission electron microscopy (TEM) or small angle x-ray scattering (SAXS). The microstructure was not stable at the 288°C IASCC test temperature and resulted in rapid reduction of hardening and presumably, annealing of the defect clusters at this temperature as well. Nevertheless, the annealing studies showed that treatments that resulted in significant decreases in the hardening produced small changes in the dislocation microstructure that were confined to the elimination of the finest of loops (~1 nm). These results substantiate the importance of the very fine defect microstructure in the IASCC process. The results of this program provide the first definitive evidence that RIS is not the sole controlling factor in the irradiation assisted stress corrosion cracking of austenitic stain

Gary S. Was; Michael Atzmon; Lumin Wang

2003-04-28T23:59:59.000Z

269

Enabling Manufacturing Research through Interoperability  

E-Print Network [OSTI]

sustainable or environmentally benign manufacturing processes andAND SUSTAINABLE FIGURE 8: LIFE-CYCLE OF MANUFACTURING PROCESSES (

Dornfeld, David; Wright, Paul; Helu, Moneer; Vijayaraghavan, Athulan

2009-01-01T23:59:59.000Z

270

Review of experiments to evaluate the ability of electrical heater rods to simulate nuclear fuel rod behavior during postulated loss-of-coolant accidents in light water reactors  

SciTech Connect (OSTI)

Issues related to using electrical fuel rod simulators to simulate nuclear fuel rod behavior during postulated loss-of-coolant accident (LOCA) conditions in light water reactors are summarized. Experimental programs which will provide a data base for comparing electrical heater rod and nuclear fuel rod LOCA responses are reviewed.

McPherson, G D; Tolman, E L

1980-01-01T23:59:59.000Z

271

Evaluation of weapons-grade mixed oxide fuel performance in U.S. Light Water Reactors using COMETHE 4D release 23 computer code  

E-Print Network [OSTI]

The COMETHE 4D Release 23 computer code was used to evaluate the thermal, chemical and mechanical performance of weapons-grade MOX fuel irradiated under U.S. light water reactor typical conditions. Comparisons were made to and UO? fuels exhibited...

Bellanger, Philippe

2012-06-07T23:59:59.000Z

272

Shielding analysis for the 300 area light water reactor spent nuclear fuel within a modified multi-canister overpack canister in a modified multi-canister overpack cask  

SciTech Connect (OSTI)

Spent light water reactor fuel is to be moved out of the 324 Building. It is anticipated that intact fuel assemblies will be loaded in a modified Multi-Canister Overpack Canister, which in turn will be placed in an Overpack Transportation Cask. An estimate of gamma ray dose rates from a transportation cask is desired.

Gedeon, S.R.

1997-04-11T23:59:59.000Z

273

Transmutation Performance Analysis for Inert Matrix Fuels in Light Water Reactors and Computational Neutronics Methods Capabilities at INL  

SciTech Connect (OSTI)

The urgency for addressing repository impacts has grown in the past few years as a result of Spent Nuclear Fuel (SNF) accumulation from commercial nuclear power plants. One path that has been explored by many is to eliminate the transuranic (TRU) inventory from the SNF, thus reducing the need for additional long term repository storage sites. One strategy for achieving this is to burn the separated TRU elements in the currently operating U.S. Light Water Reactor (LWR) fleet. Many studies have explored the viability of this strategy by loading a percentage of LWR cores with TRU in the form of either Mixed Oxide (MOX) fuels or Inert Matrix Fuels (IMF). A task was undertaken at INL to establish specific technical capabilities to perform neutronics analyses in order to further assess several key issues related to the viability of thermal recycling. The initial computational study reported here is focused on direct thermal recycling of IMF fuels in a heterogeneous Pressurized Water Reactor (PWR) bundle design containing Plutonium, Neptunium, Americium, and Curium (IMF-PuNpAmCm) in a multi-pass strategy using legacy 5 year cooled LWR SNF. In addition to this initial high-priority analysis, three other alternate analyses with different TRU vectors in IMF pins were performed. These analyses provide comparison of direct thermal recycling of PuNpAmCmCf, PuNpAm, PuNp, and Pu. The results of this infinite lattice assembly-wise study using SCALE 5.1 indicate that it may be feasible to recycle TRU in this manner using an otherwise typical PWR assembly without violating peaking factor limits.

Michael A. Pope; Samuel E. Bays; S. Piet; R. Ferrer; Mehdi Asgari; Benoit Forget

2009-05-01T23:59:59.000Z

274

Advanced Light Water Reactor Plants System 80+{trademark} Design Certification Program. Annual progress report, October 1, 1992--September 30, 1993  

SciTech Connect (OSTI)

The purpose of this report is to provide a status of the progress that was made towards Design Certification of System 80+{trademark} during the US government`s 1993 fiscal year. The System 80+ Advanced Light Water Reactor (ALWR) is a 3931 MW{sub t} (1350 MWe) Pressurized Water Reactor (PWR). The design consists of an essentially complete plant. It is based on evolutionary improvements to the Standardized System 80 nuclear steam supply system in operation at Palo Verde Units 1, 2, and 3, and the Duke Power Company P-81 balance-of-plant (BOP) that was designed and partially constructed at the Cherokee plant site. The System 80/P-81 original design has been substantially enhanced to increase conformance with the EPRI ALWR Utility Requirements Document (URD). Some design enhancements incorporated in the System 80+ design are included in the four units currently under construction in the Republic of Korea. These units form the basis of the Korean standardization program. The full System 80+ standard design has been offered to the Republic of China, in response to their recent bid specification. The ABB-CE Standard Safety Analysis Report (CESSAR-DC) was submitted to the NRC and a Draft Safety Evaluation Report was issued by the NRC in October 1992. CESSAR-DC contains the technical basis for compliance with the EPRI URD for simplified emergency planning. The Nuclear Steam Supply System (NSSS) is the standard ABB-Combustion Engineering two-loop arrangement with two steam generators, two hot legs and four cold legs each with a reactor coolant pump. The System 80+ standard plant includes a sperical steel containment vessel which is enclosed in a concrete shield building, thus providing the safety advantages of a dual containment.

Not Available

1993-12-31T23:59:59.000Z

275

Prospects for and problems of using light-water supercritical-pressure coolant in nuclear reactors in order to increase the efficiency of the nuclear fuel cycle  

SciTech Connect (OSTI)

Trends in the development of the power sector of the Russian and world power industries both at present time and in the near future are analyzed. Trends in the rise of prices for reserves of fossil and nuclear fuels used for electricity production are compared. An analysis of the competitiveness of electricity production at nuclear power plants as compared to the competitiveness of electricity produced at coal-fired and natural-gas-fired thermal power plants is performed. The efficiency of the open nuclear fuel cycle and various versions of the closed nuclear fuel cycle is discussed. The requirements on light-water reactors under the scenario of dynamic development of the nuclear power industry in Russia are determined. Results of analyzing the efficiency of fuel utilization for various versions of vessel-type light-water reactors with supercritical coolant are given. Advantages and problems of reactors with supercritical-pressure water are listed.

Alekseev, P. N.; Semchenkov, Yu. M.; Sedov, A. A., E-mail: sedov@dhtp.kial.ru; Subbotin, S. A.; Chibinyaev, A. V. [Russian Research Centre Kurchatov Institute (Russian Federation)

2011-12-15T23:59:59.000Z

276

Human-In-The-Loop Simulation in Support of Long-Term Sustainability of Light Water Reactors  

SciTech Connect (OSTI)

Reliable instrumentation, information, and control systems technologies are essential to ensuring safe and efficient operation of the U.S. light water reactor (LWR) fleet. These technologies affect every aspect of nuclear power plant (NPP) and balance-of-plant operations. In 1997, the National Research Council conducted a study concerning the challenges involved in modernization of digital instrumentation and control systems in NPPs. Their findings identified the need for new II&C technology integration. The NPP owners and operators realize that this analog technology represents a significant challenge to sustaining the operation of the current fleet of NPPs. Beyond control systems, new technologies are needed to monitor and characterize the effects of aging and degradation in critical areas of key structures, systems, and components. The objective of the efforts sponsored by the U.S. Department of Energy is to develop, demonstrate, and deploy new digital technologies for II&C architectures and provide monitoring capabilities to ensure the continued safe, reliable, and economic operation of the nation’s NPPs.

Bruce P Hallbert

2015-01-01T23:59:59.000Z

277

Roadmap for Nondestructive Evaluation of Reactor Pressure Vessel Research and Development by the Light Water Reactor Sustainability Program  

SciTech Connect (OSTI)

The Department of Energy s (DOE) Light Water Reactor Sustainability (LWRS) Program is a five year effort which works to develop the fundamental scientific basis to understand, predict, and measure changes in materials and systems, structure, and components as they age in environments associated with continued long-term operations of existing commercial nuclear power reactors. This year, the Materials Aging and Degradation (MAaD) Pathway of this program has placed emphasis on emerging Non-Destructive Evaluation (NDE) methods which support these objectives. DOE funded Research and Development (R&D) on emerging NDE techniques to support commercial nuclear reactor sustainability is expected to begin next year. This summer, the MAaD Pathway invited subject matter experts to participate in a series of workshops which developed the basis for the research plan of these DOE R&D NDE activities. This document presents the results of one of these workshops which are the DOE LWRS NDE R&D Roadmap for Reactor Pressure Vessels (RPV). These workshops made a substantial effort to coordinate the DOE NDE R&D with that already underway or planned by the Electric Power Research Institute (EPRI) and the Nuclear Regulatory Commission (NRC) through their representation at these workshops.

Smith, Cyrus M [ORNL; Nanstad, Randy K [ORNL; Clayton, Dwight A [ORNL; Matlack, Katie [Georgia Institute of Technology; Ramuhalli, Pradeep [Pacific Northwest National Laboratory (PNNL); Light, Glenn [Southwest Research Institute, San Antonio

2012-09-01T23:59:59.000Z

278

A global approach of the representativity concept: Application on a high-conversion light water reactor MOX lattice case  

SciTech Connect (OSTI)

The development of new types of reactor and the increase in the safety specifications and requirements induce an enhancement in both nuclear data knowledge and a better understanding of the neutronic properties of the new systems. This enhancement is made possible using ad hoc critical mock-up experiments. The main difficulty is to design these experiments in order to obtain the most valuable information. Its quantification is usually made by using representativity and transposition concepts. These theories enable to extract some information about a quantity of interest (an integral parameter) on a configuration, but generally a posteriori. This paper presents a more global approach of this theory, with the idea of optimizing the representativity of a new experiment, and its transposition a priori, based on a multiparametric approach. Using a quadratic sum, we show the possibility to define a global representativity which permits to take into account several quantities of interest at the same time. The maximization of this factor gives information about all quantities of interest. An optimization method of this value in relation to technological parameters (over-clad diameter, atom concentration) is illustrated on a high-conversion light water reactor MOX lattice case. This example tackles the problematic of plutonium experiment for the plutonium aging and a solution through the optimization of both the over-clad and the plutonium content. (authors)

Santos, N. D.; Blaise, P.; Santamarina, A. [CEA, DEN/DER/SPRC Cadarache, F-13108 Saint Paul-lez-Durance (France)

2013-07-01T23:59:59.000Z

279

Extended-burnup LWR (light-water reactor) fuel: The amount, characteristics, and potential effects on interim storage  

SciTech Connect (OSTI)

The results of a study on extended-burnup, light-water reactor (LWR) spent fuel are described in this report. The study was performed by Pacific Northwest Laboratory for the US Department of Energy (DOE). The purpose of the study was to collect and evaluate information on the status of in-reactor performance and integrity of extended-burnup LWR fuel and initiate the investigation of the effects of extending fuel burnup on the subsequent handling, interim storage, and other operations (e.g., rod consolidation and shipping) associated with the back end of the fuel cycle. The results of this study will aid DOE and the nuclear industry in assessing the effects on waste management of extending the useful in-reactor life of nuclear fuel. The experience base with extended-burnup fuel is now substantial and projections for future use of extended-burnup fuel in domestic LWRs are positive. The basic performance and integrity of the fuel in the reactor has not been compromised by extending the burnup, and the potential limitations for further extending the burnup are not severe. 104 refs., 15 tabs.

Bailey, W.J.

1989-03-01T23:59:59.000Z

280

Separation and Recovery of Uranium Metal from Spent Light Water Reactor Fuel via Electrolytic Reduction and Electrorefining  

SciTech Connect (OSTI)

A series of bench-scale experiments was performed in a hot cell at Idaho National Laboratory to demonstrate the separation and recovery of uranium metal from spent light water reactor (LWR) oxide fuel. The experiments involved crushing spent LWR fuel to particulate and separating it from its cladding. Oxide fuel particulate was then converted to metal in a series of six electrolytic reduction runs that were performed in succession with a single salt loading of molten LiCl – 1 wt% Li2O at 650 °C. Analysis of salt samples following the series of electrolytic reduction runs identified the diffusion of select fission products from the spent fuel to the molten salt electrolyte. The extents of metal oxide conversion in the post-test fuel were also quantified, including a nominal 99.7% conversion of uranium oxide to metal. Uranium metal was then separated from the reduced LWR fuel in a series of six electrorefining runs that were performed in succession with a single salt loading of molten LiCl-KCl-UCl3 at 500 °C. Analysis of salt samples following the series of electrorefining runs identified additional partitioning of fission products into the molten salt electrolyte. Analyses of the separated uranium metal were performed, and its decontamination factors were determined.

S. D. Herrmann; S. X. Li

2010-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "lighting manufacturing water" 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

Locating Chicago Manufacturing  

E-Print Network [OSTI]

Renaissance Council, is among the nation's leading public high schools focused on manufac- turing area's econ- omy, including how important manufacturing is to that economy, which manufac- turing

Illinois at Chicago, University of

282

Advanced Materials Manufacturing | ORNL  

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

existing manufacturing industries and result in creative new products. Stronger, more corrosion-resistant and lower cost steel alloys are being developed and commercialized to...

283

Manufacturing | Department of Energy  

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

the production of clean energy technologies like electric vehicles, LED bulbs and solar panels. The Department is also working with manufacturers to increase their energy...

284

Acoustics by additive manufacturing:.  

E-Print Network [OSTI]

??This study focuses on exploring the merging field of additive manufacturing and acoustics and introduces a new type of sound absorber which is regulating performance… (more)

Setaki, F.

2012-01-01T23:59:59.000Z

285

Additive Manufacturing: Going Mainstream  

Broader source: Energy.gov [DOE]

Additive manufacturing, or 3D printing, is receiving attention from media, investment communities and governments around the world transforming it from obscurity to something to be talked about.

286

MANUFACTURING & SERVICE OPERATIONS MANAGEMENT  

E-Print Network [OSTI]

MANUFACTURING & SERVICE OPERATIONS MANAGEMENT Vol. 14, No. 4, Fall 2012, pp. 495­511 ISSN 1523 research directions, expanding upon the key points raised by Green [Green LV (2012) The vital role of operations analysis in improving healthcare delivery. Manufacturing Service Oper. Management 14

Boucherie, Richard J.

287

MANUFACTURING & SERVICE OPERATIONS MANAGEMENT  

E-Print Network [OSTI]

;Green and Soares: Note Manufacturing & Service Operations Management 9(1), pp. 54­61, © 2007 INFORMS 55MANUFACTURING & SERVICE OPERATIONS MANAGEMENT Vol. 9, No. 1, Winter 2007, pp. 54­61 issn 1523-Dependent Waiting Time Probabilities in M t /M/s t Queuing Systems Linda V. Green Graduate School of Business

Soares, JoĂŁo LuĂ­s Cardoso

288

Assessment of Possible Cycle Lengths for Fully-Ceramic Micro-Encapsulated Fuel-Based Light Water Reactor Concepts  

SciTech Connect (OSTI)

The tri-isotropic (TRISO) fuel developed for High Temperature reactors is known for its extraordinary fission product retention capabilities [1]. Recently, the possibility of extending the use of TRISO particle fuel to Light Water Reactor (LWR) technology, and perhaps other reactor concepts, has received significant attention [2]. The Deep Burn project [3] currently focuses on once-through burning of transuranic fissile and fissionable isotopes (TRU) in LWRs. The fuel form for this purpose is called Fully-Ceramic Micro-encapsulated (FCM) fuel, a concept that borrows the TRISO fuel particle design from high temperature reactor technology, but uses SiC as a matrix material rather than graphite. In addition, FCM fuel may also use a cladding made of a variety of possible material, again including SiC as an admissible choice. The FCM fuel used in the Deep Burn (DB) project showed promising results in terms of fission product retention at high burnup values and during high-temperature transients. In the case of DB applications, the fuel loading within a TRISO particle is constituted entirely of fissile or fissionable isotopes. Consequently, the fuel was shown to be capable of achieving reasonable burnup levels and cycle lengths, especially in the case of mixed cores (with coexisting DB and regular LWR UO2 fuels). In contrast, as shown below, the use of UO2-only FCM fuel in a LWR results in considerably shorter cycle length when compared to current-generation ordinary LWR designs. Indeed, the constraint of limited space availability for heavy metal loading within the TRISO particles of FCM fuel and the constraint of low (i.e., below 20 w/0) 235U enrichment combine to result in shorter cycle lengths compared to ordinary LWRs if typical LWR power densities are also assumed and if typical TRISO particle dimensions and UO2 kernels are specified. The primary focus of this summary is on using TRISO particles with up to 20 w/0 enriched uranium kernels loaded in Pressurized Water Reactor (PWR) assemblies. In addition to consideration of this 'naive' use of TRISO fuel in LWRs, several refined options are briefly examined and others are identified for further consideration including the use of advanced, high density fuel forms and larger kernel diameters and TRISO packing fractions. The combination of 800 {micro}m diameter kernels of 20% enriched UN and 50% TRISO packing fraction yielded reactivity sufficient to achieve comparable burnup to present-day PWR fuel.

R. Sonat Sen; Michael A. Pope; Abderrafi M. Ougouag; Kemal O. Pasamehmetoglu

2012-04-01T23:59:59.000Z

289

Heavy-Section Steel Irradiation Program on irradiation effects in light-water reactor pressure vessel materials  

SciTech Connect (OSTI)

The safety of commercial light-water nuclear plants is highly dependent on the structural integrity of the reactor pressure vessel (RPV). In the absence of radiation damage to the RPV, fracture of the vessel is difficult to postulate. Exposure to high energy neutrons can result in embrittlement of radiation-sensitive RPV materials. The Heavy-Section Steel Irradiation (HSSI) Program at Oak Ridge National Laboratory, sponsored by the US Nuclear Regulatory Commission (USNRC), is assessing the effects of neutron irradiation on RPV material behavior, especially fracture toughness. The results of these and other studies are used by the USNRC in the evaluation of RPV integrity and regulation of overall nuclear plant safety. In assessing the effects of irradiation, prototypic RPV materials are characterized in the unirradiated condition and exposed to radiation under varying conditions. Mechanical property tests are conducted to provide data which can be used in the development of guidelines for structural integrity evaluations, while metallurgical examinations and mechanistic modeling are performed to improve understanding of the mechanisms responsible for embrittlement. The results of these investigations, in conjunction with results from commercial reactor surveillance programs, are used to develop a methodology for the prediction of radiation effects on RPV materials. This irradiation-induced degradation of the materials can be mitigated by thermal annealing, i.e., heating the RPV to a temperature above that of normal operation. Thus, thermal annealing and evaluation of reirradiation behavior are major tasks of the HSSI Program. This paper describes the HSSI Program activities by summarizing some past and recent results, as well as current and planned studies. 30 refs., 8 figs., 1 tab.

Nanstad, R.K.; Corwin, W.R.; Alexander, D.J.; Haggag, F.M.; Iskander, S.K.; McCabe, D.E.; Sokolov, M.A.; Stoller, R.E. [Oak Ridge National Lab., TN (United States). Metals and Ceramics Div.

1995-07-01T23:59:59.000Z

290

Manufacturing Renaissance: Return of manufacturing to western countries.  

E-Print Network [OSTI]

??Manufacturing Renaissance, i.e. return of manufacturing to west, has been recently observed. This paper analyzes the patterns observed within each of the four main drivers… (more)

Kianian, Babak; Larsson, Tobias

2013-01-01T23:59:59.000Z

291

Manufacturing Licenses Available | Tech Transfer | ORNL  

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

Deposition Manufacturing 201303127 Methods and Materials for Room Temperature Polymer Additive Manufacturing 201303140 Reactive Polymer Fused Deposition Manufacturing 201303151...

292

"Technology Wedges" for Implementing Green Manufacturing  

E-Print Network [OSTI]

issues in green design and manufacturing." ManufacturingFOR IMPLEMENTING GREEN MANUFACTURING David Dornfeld BerkeleyCalifornia KEYWORDS Green Manufacturing, Technology,

Dornfeld, David; Wright, Paul

2007-01-01T23:59:59.000Z

293

MDF | Manufacturing Demonstration Facility | ORNL  

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

MDF Working with MDF NTRC OLCF SNS Titanium robotic hand holding sphere fabricated using additive manufacturing Home | User Facilities | MDF MDF | Manufacturing Demonstration...

294

REMEDIAT1NG AT MANUFACTURED GAS  

E-Print Network [OSTI]

, comhusti- hle gas manufactured Pfrom coke, coal, and oil 1 served as the major gas- eous fuel for urban for the three primary gas production meth- ods: coal carbonization, carbureted water gas production, and oil gas, and metals. Tar resid- uals were produced from the vola- tiIe component of bituminous coals in coal

Peters, Catherine A.

295

CIMplementation™: Evaluating Manufacturing Automation  

E-Print Network [OSTI]

management and labor. In the new shop, ma~? agers will be unable to succeed unless thet earn the respect and cooperation of their I subordinates. Managers need to address th~ fear and resistance of manufacturing emPlofees before and during a transition.... Managers are becoming more interested in these methods, but they should be aware that implementing them will be a slow, complex task. This technology will require changes in manufacturing organization. This paper discusses changes required...

Krakauer, J.

296

Low Cost Lithography Tool for High Brightness LED Manufacturing  

SciTech Connect (OSTI)

The objective of this activity was to address the need for improved manufacturing tools for LEDs. Improvements include lower cost (both capital equipment cost reductions and cost-ofownership reductions), better automation and better yields. To meet the DOE objective of $1- 2/kilolumen, it will be necessary to develop these highly automated manufacturing tools. Lithography is used extensively in the fabrication of high-brightness LEDs, but the tools used to date are not scalable to high-volume manufacturing. This activity addressed the LED lithography process. During R&D and low volume manufacturing, most LED companies use contact-printers. However, several industries have shown that these printers are incompatible with high volume manufacturing and the LED industry needs to evolve to projection steppers. The need for projection lithography tools for LED manufacturing is identified in the Solid State Lighting Manufacturing Roadmap Draft, June 2009. The Roadmap states that Projection tools are needed by 2011. This work will modify a stepper, originally designed for semiconductor manufacturing, for use in LED manufacturing. This work addresses improvements to yield, material handling, automation and throughput for LED manufacturing while reducing the capital equipment cost.

Andrew Hawryluk; Emily True

2012-06-30T23:59:59.000Z

297

Recovery Act Helps GE in-source Manufacturing | Department of...  

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

interior and making a modern, efficient space inside the existing 1950s shell. The hybrid water heaters, which had previously been manufactured in China, will go into production at...

298

Advanced Manufacture of Reflectors  

Broader source: Energy.gov [DOE]

The Advance Manufacture of Reflectors fact sheet describes a SunShot Initiative project being conducted research team led by the University of Arizona, which is working to develop a novel method for shaping float glass. The technique developed by this research team can drastically reduce the time required for the shaping step. By enabling mass production of solar concentrating mirrors at high speed, this project should lead to improved performance and as much as a 40% reduction in manufacturing costs for reflectors made in very high volume.

299

ATS materials/manufacturing  

SciTech Connect (OSTI)

The Materials/Manufacturing Technology subelement is a part of the base technology portion of the Advanced Turbine Systems (ATS) Program. The work in this subelement is being performed predominantly by industry with assistance from national laboratories and universities. The projects in this subelement are aimed toward hastening the incorporation of new materials and components in gas turbines. Work is currently ongoing on thermal barrier coatings (TBCs), the scale-up of single crystal airfoil manufacturing technologies, materials characterization, and technology information exchange. This paper presents highlights of the activities during the past year. 12 refs., 24 figs., 4 tabs.

Karnitz, M.A.; Wright, I.G.; Ferber, M.K. [and others

1997-11-01T23:59:59.000Z

300

Feasibility Study of Supercritical Light Water Cooled Reactors for Electric Power Production, Progress Report for Work Through September 2003, 2nd Annual/8th Quarterly Report  

SciTech Connect (OSTI)

The supercritical water-cooled reactor (SCWR) is one of the six reactor technologies selected for research and development under the Generation-IV program. SCWRs are promising advanced nuclear systems because of their high thermal efficiency (i.e., about 45% vs. about 33% efficiency for current Light Water Reactors, LWRs) and considerable plant simplification. SCWRs are basically LWRs operating at higher pressure and temperatures with a direct once-through cycle. Operation above the critical pressure eliminates coolant boiling, so the coolant remains single-phase throughout the system. Thus the need for recirculation and jet pumps, a pressurizer, steam generators, steam separators and dryers is eliminated. The main mission of the SCWR is generation of low-cost electricity. It is built upon two proven technologies, LWRs, which are the most commonly deployed power generating reactors in the world, and supercritical fossil-fired boilers, a large number of which is also in use around the world.

Philip E. MacDonald

2003-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "lighting manufacturing water" 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

Investigation of the use of nanofluids to enhance the In-Vessel Retention capabilities of Advanced Light Water Reactors  

E-Print Network [OSTI]

Nanofluids at very low concentrations experimentally exhibit a substantial increase in Critical Heat Flux (CHF) compared to water. The use of a nanofluid in the In-Vessel Retention (IVR) severe accident management strategy, ...

Hannink, Ryan Christopher

2007-01-01T23:59:59.000Z

302

Supplier selection and supplier management improvements at an analytical instrument manufacturing company  

E-Print Network [OSTI]

This thesis addresses the challenges of improving the quality of parts received from suppliers at Waters, an analytical instrument manufacturing company. Preliminary analysis identified improvement opportunities at evaluation ...

He, Yan, M. Eng. Massachusetts Institute of Technology

2014-01-01T23:59:59.000Z

303

Feasibility Study of Supercritical Light Water Cooled Fast Reactors for Actinide Burning and Electric Power Production, Progress Report for Work Through September 2002, 4th Quarterly Report  

SciTech Connect (OSTI)

The use of light water at supercritical pressures as the coolant in a nuclear reactor offers the potential for considerable plant simplification and consequent capital and O&M cost reduction compared with current light water reactor (LWR) designs. Also, given the thermodynamic conditions of the coolant at the core outlet (i.e. temperature and pressure beyond the water critical point), very high thermal efficiencies of the power conversion cycle are possible (i.e. up to about 45%). Because no change of phase occurs in the core, the need for steam separators and dryers as well as for BWR-type re-circulation pumps is eliminated, which, for a given reactor power, results in a substantially shorter reactor vessel and smaller containment building than the current BWRs. Furthermore, in a direct cycle the steam generators are not needed. If no additional moderator is added to the fuel rod lattice, it is possible to attain fast neutron energy spectrum conditions in a supercritical water-cooled reactor (SCWR). This type of core can make use of either fertile or fertile-free fuel and retain a hard spectrum to effectively burn plutonium and minor actinides from LWR spent fuel while efficiently generating electricity. One can also add moderation and design a thermal spectrum SCWR. The Generation IV Roadmap effort has identified the thermal spectrum SCWR (followed by the fast spectrum SCWR) as one of the advanced concepts that should be developed for future use. Therefore, the work in this NERI project is addressing both types of SCWRs.

Mac Donald, Philip Elsworth

2002-09-01T23:59:59.000Z

304

Solid-State Lighting R&D Workshop  

Broader source: Energy.gov [DOE]

Join DOE—and lighting industry experts representing the entire SSL supply chain—at the sixth annual SSL Manufacturing R&D Workshop.

305

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

SciTech Connect (OSTI)

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

NONE

1993-09-15T23:59:59.000Z

306

Bio-Manufacturing: A Strategic clean energy manufacturing opportunity  

Broader source: Energy.gov [DOE]

Breakout Session 1: New Developments and Hot Topics Session 1-A: Biomass and the U.S. Competitive Advantages for Manufacturing Clean Energy Products Libby Wayman, Director, EERE Clean Energy Manufacturing Initiative

307

Next Generation Power Electronics National Manufacturing Innovation Institute  

Broader source: Energy.gov [DOE]

The Next Generation Power Electronics National Manufacturing Innovation Institute will focus on wide bandgap (WBG) semiconductors - the same materials used in LED light fixtures and many flat screen TVs. The Institute will use $70 million provided by the U.S. Department of Energy's Advanced Manufacturing Office to support and manage its programs over the next five years. This Institute is one of three new innovation hubs announced by President Obama in his 2013 State of the Union address and part of the National Network for Manufacturing Innovation (NNMI).

308

Light Induced Water Oxidation on Cobalt-Phosphate (Co-Pi) Catalyst Modified Semi-Transparent, Porous SiO2-BiVO4 Electrodes  

SciTech Connect (OSTI)

A facile and simple procedure for the synthesis of semi-transparent and porous SiO{sub 2}-BiVO{sub 4} electrodes is reported. The method involves a surfactant assisted metal-organic decomposition at 500 C. An earth abundant oxygen evolution catalyst (OEC), cobalt phosphate (Co-Pi), has been used to modify the SiO{sub 2}-BiVO{sub 4} electrode by electrodeposition (ED) and photoassisted electrodeposition (PED) methods. Modified electrodes by these two methods have been examined for light induced water oxidation and compared to the unmodified SiO{sub 2}-BiVO{sub 4} electrodes by various photoelectrochemical techniques. The PED method was a more effective method of OEC preparation than the ED method as evidenced by an increased photocurrent magnitude during photocurrent-potential (I-V) characterizations. Electrode surfaces catalyzed by PED exhibited a very large cathodic shift (420 mV) in the onset potential for water oxidation. The chopped-light I-V measurements performed at different intervals over 24-hour extended testing under illumination and applied bias conditions show a fair photostability for PED Co-Pi modified SiO{sub 2}-BiVO{sub 4}.

Pilli, S. K.; Deutsch, T. G.; Furtak, T. E.; Turner, J. A.; Brown, L. D.; Herring, A. M.

2012-04-21T23:59:59.000Z

309

A Comparative Study of Ozone and Ultraviolet Light/Hydrogen Peroxide for Decolorizing Textile Dyeing Waste Water  

E-Print Network [OSTI]

UVjperoxide batch reactor Description of Dyes Ten dyes representing a broad range of types of structure found in dye molecules were included in the study. Azo and anthraquinone structures were included as were water soluble and water insoluble dyes... Diazo o~-io--03~-o-, ~ '101' Yellow 44 29000 Diazo O~-o.-o?~ Table 2: Description of Acid Dyes CI Acid CINo. Classification Structure Red 1 Blue 25 18050 62055 Monazo Anthraquinone OH HMCOCHJ O-:(O,sor o HoO~ . c05'" o HH-Q Yellow 151...

Namboodri, C. G.; Perkins, W. S.; Walsh, W. K.

310

Additive Manufacturing for Fuel Cells  

Office of Energy Efficiency and Renewable Energy (EERE)

Blake Marshall, AMO's lead for Additive Manufacturing Technologies, will provide an overview of current R&D activities in additive manufacturing and its application to fuel cell prototyping and...

311

CdSe-MoS2: A Quantum Size-Confined Photocatalyst for Hydrogen Evolution from Water under Visible Light  

E-Print Network [OSTI]

and for the conversion of carbon dioxides into methanol and hydrocarbons. Metal chalcogenides1­9 are promisingCdSe-MoS2: A Quantum Size-Confined Photocatalyst for Hydrogen Evolution from Water under Visible driven pathway to hydrogen. Hydrogen is not only an environmentally benign fuel for the generation

Osterloh, Frank

312

Light-water-reactor safety fuel systems research programs. Quarterly progress report, January-March 1985. Volume 1  

SciTech Connect (OSTI)

This progress report summarizes work performed by the Materials Science and Technology Division of Argonne National Laboratory during January, February, and March 1985 on water reactor safety problems related to fuel and cladding. The research and development areas covered are Transient Fuel Response and Fission Product Release and Clad Properties for Code Verification. 15 refs.

Not Available

1986-01-01T23:59:59.000Z

313

Light-water-reactor safety fuel systems research programs. Quarterly progress report, January-March 1984. [Fuel and cladding problems  

SciTech Connect (OSTI)

This progress report summarizes work performed by the Materials Science and Technology Division of Argonne National Laboratory during January, February, and March 1984 on water reactor safety problems related to fuel and cladding. The research and development areas covered are Transient Fuel Response and Fission Product Release and Clad Properties for Code Verification.

Not Available

1984-09-01T23:59:59.000Z

314

Light-water-reactor safety fuel systems research programs. Quarterly progress report, July-September 1984. Volume 3  

SciTech Connect (OSTI)

This progress report summarizes work performed by the Materials Science and Technology Division of Argonne National Laboratory during July, August, and September 1984 on water reactor safety problems related to fuel and cladding. The research and development areas covered are Transient Fuel Response and Fission Product Release and Clad Properties for Code Verification. 17 refs., 23 figs., 5 tabs.

Not Available

1985-04-01T23:59:59.000Z

315

Light-water-reactor safety fuel systems research programs. Quarterly progress report, April-June 1984. Volume 2  

SciTech Connect (OSTI)

This progress report report summarizes work performed by the Materials Science and Technology Division of Argonne National Laboratory during April, May, and June 1984 on water reactor safety problems related to fuel and cladding. The research and development areas covered are Transient Fuel Response and Fission Product Release and Clad Properties for Code Verification.

Not Available

1985-02-01T23:59:59.000Z

316

Light-water-reactor safety fuel systems research programs. Quarterly progress report, October-December 1984. Volume 4  

SciTech Connect (OSTI)

This progress report summarizes work performed by the Materials Science and Technology Division of Argonne National Laboratory during October, November, and December 1984 on water reactor safety problems related to fuel and cladding. The research and development areas covered are Transient Fuel Response and Fission Product Release and Clad Properties for Code Verification. 30 refs., 23 figs., 2 tabs.

Not Available

1985-08-01T23:59:59.000Z

317

Manufacturing High Temperature Systems  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustion | Department of Energy Low-TemperatureEnergyAll ManufacturingFoodOctoberto DOE

318

LED Lamp Project Lights the Way to Flicker-Free Replacement Jade Sky Technologies and UC Davis's California Lighting Technology Center demonstrate the  

E-Print Network [OSTI]

, 2014 ­ Jade Sky Technologies ("JST"), a clean-tech start-up manufacturer of LED Technologies and UC Davis's California Lighting Technology Center demonstrate the lighting Specification. JST collaborated with UC Davis's California Lighting Technology Center

California at Davis, University of

319

Manufacturing Success Stories | Department of Energy  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: AlternativeEnvironment, SafetyWater ConservationDepartmentEnergy Manufacturing

320

Water Budgets: Foundations for Effective Water-Resources and  

E-Print Network [OSTI]

for consumption, for producing food, and for manufacturing; we also are attracted to water for its esthetic value pets and livestock--all depend on water. Competition for water among humans and between humans

Note: This page contains sample records for the topic "lighting manufacturing water" 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

Manufacturing Tech Team | Department of Energy  

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

Manufacturing Tech Team Manufacturing Tech Team Clean Energy Manufacturing Initiative Industrial Efficiency and Energy Productivity Video Industrial efficiency and low-cost energy...

322

Leveraging Manufacturing for a Sustainable Future  

E-Print Network [OSTI]

for Implementing Green Manufacturing”, NAMRI Trans. , 35,Strategies for Green Manufacturing,” Proc. 4th CIRPAnd, in specific green manufacturing? This will depend on

Dornfeld, David

2011-01-01T23:59:59.000Z

323

Sustainable Manufacturing – Greening Processes, Systems and Products  

E-Print Network [OSTI]

Strategies for Green Manufacturing, " Proceedings HighFH), Implementing green manufacturing, as the first stepASME, Evanston, IL, Green Manufacturing uk/sustainability/

Dornfeld, David

2010-01-01T23:59:59.000Z

324

Appropriate use of Green Manufacturing Frameworks  

E-Print Network [OSTI]

for Implementing Green Manufacturing,” Trans. North AmericanAppropriate use of Green Manufacturing Frameworks C. Reich-for sustainable or green manufacturing systems and products,

Reich-Weiser, Corinne; Vijayaraghavan, Athulan; Dornfeld, David

2010-01-01T23:59:59.000Z

325

Establishing Greener Products and Manufacturing Processes  

E-Print Network [OSTI]

for implementing green manufacturing,” Trans. North AmericaStrategies for Green Manufacturing,” Proc. of the 4th CIRPAppropriate Use of Green Manufacturing Frameworks,” Proc. of

Linke, Barbara; Huang, Yu-Chu; Dornfeld, David

2012-01-01T23:59:59.000Z

326

Establishing Greener Products and Manufacturing Processes  

E-Print Network [OSTI]

Operation Strategies for Green Manufacturing, Proceedings ofSymposium on Green Manufacturing and Applications (ISGMAfor implementing green manufacturing. Transactions of NAMRI/

Linke, Barbara; Dornfeld, David; Huang, Yu-Chu

2011-01-01T23:59:59.000Z

327

Innovative Manufacturing Initiative Recognition Day, Advanced...  

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

Publications Innovative Manufacturing Initiative Recognition Day Advanced Manufacturing Office Overview Unlocking the Potential of Additive Manufacturing in the Fuel Cells Industry...

328

Precision and Energy Usage for Additive Manufacturing  

E-Print Network [OSTI]

Sustainability of additive manufacturing: measuring theCommittee F42 on Additive Manufacturing Technologies," TheASTM Committee F42 on Additive Manufacturing Technologies. -

Clemon, Lee; Sudradjat, Anton; Jaquez, Maribel; Krishna, Aditya; Rammah, Marwan; Dornfeld, David

2013-01-01T23:59:59.000Z

329

Leveraging Manufacturing for a Sustainable Future  

E-Print Network [OSTI]

2010): “Sustainable Manufacturing – Greening Processes,processes and systems) can play in creating a sustainablesustainable manufacturing as “the creation of manufacturing products that use materials and processes

Dornfeld, David

2011-01-01T23:59:59.000Z

330

Establishing Greener Products and Manufacturing Processes  

E-Print Network [OSTI]

D. , “Sustainable Manufacturing - Greening Processes,Avoid) Increase process efficiency Most sustainable (Improvesustainable manufacturing. 2 They highlighted research needs in four categories: i) manufacturing processes and

Linke, Barbara; Huang, Yu-Chu; Dornfeld, David

2012-01-01T23:59:59.000Z

331

Sustainable Manufacturing – Greening Processes, Systems and Products  

E-Print Network [OSTI]

mittels Sustainable Manufacturing - Greening Processes,Sustainable for manufacturing Manufacturing Cambridge, accessed processes,processes due to energy awareness and environmental consciousness create many opportunities for sustainable

Dornfeld, David

2010-01-01T23:59:59.000Z

332

Establishing Greener Products and Manufacturing Processes  

E-Print Network [OSTI]

D. , Sustainable Manufacturing – Greening Processes, Systemsor impact low Most  sustainable Increase process efficiencysustainable manufacturing [1]. They highlighted research needs in four categories: i) manufacturing processes and

Linke, Barbara; Dornfeld, David; Huang, Yu-Chu

2011-01-01T23:59:59.000Z

333

Efficiency and stray light measurements and calculations of diffraction gratings for the ALS  

SciTech Connect (OSTI)

Water cooled gratings manufactured for spherical grating monochromators of the Advanced Light Source beamlines 7.0, 8.0 and 9.0 were measured with the laser plasma source and reflectometer in the Center for X-ray Optics at LBL. The square-wave gratings are ion-milled into the polished electroless nickel surface after patterning by holographic photolithography. Absolute efficiency data are compared with exact electromagnetic theory calculation. Inter-order stray light and groove depths can be estimated from the measurements.

McKinney, W.R.; Mossessian, D.; Gullikson, E.; Heimann, P.

1994-07-01T23:59:59.000Z

334

SSL Manufacturing Roadmap  

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

for OLED lighting are causing apprehension amongst all of the tool makers. The market for small scale equipment suitable for R&D operations is still healthy and is being pursued...

335

Low-Cost Manufacturable Microchannel Systems for Passive  

E-Print Network [OSTI]

for use in fuel cell systems need development in order to achieve cost targets. Low-cost, highLow-Cost Manufacturable Microchannel Systems for Passive PEM Water Management IIPS Number 16910 LowLow--CostCost;2 Project objective: Create a low cost and passive PEM water management system Project objective

336

Hollings Manufacturing Extension Partnership: A Commercialization Collaborator  

E-Print Network [OSTI]

to process improvements to green manufacturing. MEP also works with partners at the state and federal levelsHollings Manufacturing Extension Partnership: A Commercialization Collaborator MEP · MANUFACTURING to successfully commercialize federal technologies #12;The Manufacturing Extension Partnership

Perkins, Richard A.

337

Seminar Title: Additive Manufacturing Advanced Manufacturing of Polymer and Composite Components  

E-Print Network [OSTI]

Seminar Title: Additive Manufacturing ­ Advanced Manufacturing of Polymer and Composite Components Functionally Integrated Composite Structures, Augsburg, Germany ME Faculty Candidate Abstract: Additive Manufacturing ­ Advanced Manufacturing of Polymer and Composite Components Additive manufacturing technologies

Wisconsin at Madison, University of

338

A domain-specific analysis system for examining nuclear reactor simulation data for light-water and sodium-cooled fast reactors  

E-Print Network [OSTI]

Building a new generation of fission reactors in the United States presents many technical and regulatory challenges. One important challenge is the need to share and present results from new high-fidelity, high-performance simulations in an easily usable way. Since modern multiscale, multi-physics simulations can generate petabytes of data, they will require the development of new techniques and methods to reduce the data to familiar quantities of interest (e.g., pin powers, temperatures) with a more reasonable resolution and size. Furthermore, some of the results from these simulations may be new quantities for which visualization and analysis techniques are not immediately available in the community and need to be developed. This paper describes a new system for managing high-performance simulation results in a domain-specific way that naturally exposes quantities of interest for light water and sodium-cooled fast reactors. It describes requirements to build such a system and the technical challenges faced...

Billings, Jay Jay; Hull, S Forest; Lingerfelt, Eric J; Wojtowicz, Anna

2014-01-01T23:59:59.000Z

339

Possible effects of UO/sub 2/ oxidation on light water reactor spent fuel performance in long-term geologic disposal  

SciTech Connect (OSTI)

Disposal of spent nuclear fuel in a conventionally mined geologic formation is the nearest-term option for permanently isolating radionuclides from the biosphere. Because irradiated uranium dioxide (UO/sub 2/) fuel pellets retain 95 to 99% of the radionuclides generated during normal light water reactor operation, they may represent a significant barrier to radionuclide release. This document presents a technical assessment of published literature representing the current level of understanding of spent fuel characteristics and conditions that may degrade pellet integrity during a geologic disposal sequence. A significant deterioration mechanism is spent UO/sub 2/ oxidation with possible consequences identified as fission gas release, rod diameter increases, cladding breach extension, and release of solid fuel particles containing radionuclides. Areas requiring further study to support development of a comprehensive spent fuel performance prediction model are highlighted. A program and preliminary schedule to obtain the information needed to develop model correlations are also presented.

Almassy, M.Y.; Woodley, R.E.

1982-08-01T23:59:59.000Z

340

Is there a particle-size dependence for the mediation by colloidal redox catalysts of the light-induced hydrogen evolution from water  

SciTech Connect (OSTI)

Particle-size effects for the catalysis by platinum of the light-induced hydrogen evolution from water, using the (Ru(bpy)/sub 3//sup 2 +//methyl viologen/EDTA) model system, were investigated with widely polydispersed colloidal platinum hydrosols and samples with narrower size distributions obtained from the former hydrosols by centrifugation. The optimum values for the hydrogen-formation rates and yields were found to be very similar for all catalysts studied; this was true for those containing polydispersed or selected small (<100 A) as well as large particles (>1000 A). In fact, no platinum particle-size effects on the methyl viologen mediated hydrogen evolutions were observed in the investigated size range. These results are discussed in relation to studies on catalyst-dispersion effects in the field of heterogeous catalysis.

Keller, P.; Moradpour, A.

1980-11-19T23:59:59.000Z

Note: This page contains sample records for the topic "lighting manufacturing water" 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

Proposed and existing passive and inherent safety-related structures, systems, and components (building blocks) for advanced light-water reactors  

SciTech Connect (OSTI)

A nuclear power plant is composed of many structures, systems, and components (SSCs). Examples include emergency core cooling systems, feedwater systems, and electrical systems. The design of a reactor consists of combining various SSCs (building blocks) into an integrated plant design. A new reactor design is the result of combining old SSCs in new ways or use of new SSCs. This report identifies, describes, and characterizes SSCs with passive and inherent features that can be used to assure safety in light-water reactors. Existing, proposed, and speculative technologies are described. The following approaches were used to identify the technologies: world technical literature searches, world patent searches, and discussions with universities, national laboratories and industrial vendors. 214 refs., 105 figs., 26 tabs.

Forsberg, C.W.; Moses, D.L.; Lewis, E.B.; Gibson, R.; Pearson, R.; Reich, W.J.; Murphy, G.A.; Staunton, R.H.; Kohn, W.E.

1989-10-01T23:59:59.000Z

342

Progress in evaluation and improvement in nondestructive examination reliability for inservice inspection of Light Water Reactors (LWRs) and characterize fabrication flaws in reactor pressure vessels  

SciTech Connect (OSTI)

This paper is a review of the work conducted under two programs. One (NDE Reliability Program) is a multi-year program addressing the reliability of nondestructive evaluation (NDE) for the inservice inspection (ISI) of light water reactor components. This program examines the reliability of current NDE, the effectiveness of evolving technologies, and provides assessments and recommendations to ensure that the NDE is applied at the right time, in the right place with sufficient effectiveness that defects of importance to structural integrity will be reliably detected and accurately characterized. The second program (Characterizing Fabrication Flaws in Reactor Pressure Vessels) is assembling a data base to quantify the distribution of fabrication flaws that exist in US nuclear reactor pressure vessels with respect to density, size, type, and location. These programs will be discussed as two separate sections in this report. 4 refs., 7 figs.

Doctor, S.R.; Bowey, R.E.; Good, M.S.; Friley, J.R.; Kurtz, R.J.; Simonen, F.A.; Taylor, T.T.; Heasler, P.G.; Andersen, E.S.; Diaz, A.A.; Greenwood, M.S.; Hockey, R.L.; Schuster, G.J.; Spanner, J.C.; Vo, T.V.

1991-10-01T23:59:59.000Z

343

NRC review of Electric Power Research Institute`s advanced light water reactor utility requirements document. Passive plant designs, chapter 1, project number 669  

SciTech Connect (OSTI)

The Electric Power Research Institute (EPRI) is preparing a compendium of technical requirements, referred to as the {open_quotes}Advanced Light Water Reactor [ALWR] Utility Requirements Document{close_quotes}, that is acceptable to the design of an ALWR power plant. When completed, this document is intended to be a comprehensive statement of utility requirements for the design, construction, and performance of an ALWR power plant for the 1990s and beyond. The Requirements Document consists of three volumes. Volume 1, {open_quotes}ALWR Policy and Summary of Top-Tier Requirements{close_quotes}, is a management-level synopsis of the Requirements Document, including the design objectives and philosophy, the overall physical configuration and features of a future nuclear plant design, and the steps necessary to take the proposed ALWR design criteria beyond the conceptual design state to a completed, functioning power plant. Volume II consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant [approximately 1350 megawatts-electric (MWe)]. Volume III contains utility design requirements for nuclear plants for which passive features will be used in their designs (approximately 600 MWe). In April 1992, the staff of the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, issued Volume 1 and Volume 2 (Parts 1 and 2) of its safety evaluation report (SER) to document the results of its review of Volumes 1 and 2 of the Requirements Document. Volume 1, {open_quotes}NRC Review of Electric Power Research Institute`s Advanced Light Water Reactor Utility Requirements Document - Program Summary{close_quotes}, provided a discussion of the overall purpose and scope of the Requirements Document, the background of the staff`s review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review.

Not Available

1994-08-01T23:59:59.000Z

344

NRC review of Electric Power Research Institute`s advanced light water reactor utility requirements document. Passive plant designs, chapters 2-13, project number 669  

SciTech Connect (OSTI)

The Electric Power Research Institute (EPRI) is preparing a compendium of technical requirements, referred to as the {open_quotes}Advanced Light Water Reactor [ALWR] Utility Requirements Document{close_quotes}, that is acceptable to the design of an ALWR power plant. When completed, this document is intended to be a comprehensive statement of utility requirements for the design, construction, and performance of an ALWR power plant for the 1990s and beyond. The Requirements Document consists of three volumes. Volume I, {open_quotes}ALWR Policy and Summary of Top-Tier Requirements{close_quotes}, is a management-level synopsis of the Requirements Document, including the design objectives and philosophy, the overall physical configuration and features of a future nuclear plant design, and the steps necessary to take the proposed ALWR design criteria beyond the conceptual design state to a completed, functioning power plant. Volume II consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant [approximately 1350 megawatts-electric (MWe)]. Volume III contains utility design requirements for nuclear plants for which passive features will be used in their designs (approximately 600 MWe). In April 1992, the staff of the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, issued Volume 1 and Volume 2 (Parts 1 and 2) of its safety evaluation report (SER) to document the results of its review of Volumes 1 and 2 of the Requirements Document. Volume 1, {open_quotes}NRC Review of Electric Power Research Institute`s Advanced Light Water Reactor Utility Requirements Document - Program Summary{close_quotes}, provided a discussion of the overall purpose and scope of the Requirements Document, the background of the staff`s review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review.

Not Available

1994-08-01T23:59:59.000Z

345

Manufacturing Demonstration Facility  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: VegetationEquipment Surfaces and InterfacesAdministrationManufacturing - GE Appliances, ORNL

346

Industrial Scale Demonstration of Smart Manufacturing Achieving...  

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

Scale Demonstration of Smart Manufacturing Achieving Transformational Energy Productivity Gains Industrial Scale Demonstration of Smart Manufacturing Achieving...

347

Industrial Scale Demonstration of Smart Manufacturing Achieving...  

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

Scale Demonstration of Smart Manufacturing Achieving Transformational Energy Productivity Gains Development of an Open Architecture, Widely Applicable Smart Manufacturing...

348

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

SciTech Connect (OSTI)

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

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

2013-09-01T23:59:59.000Z

349

Manufacturing consumption of energy 1994  

SciTech Connect (OSTI)

This report provides estimates on energy consumption in the manufacturing sector of the U.S. economy based on data from the Manufacturing Energy Consumption Survey. The sample used in this report represented about 250,000 of the largest manufacturing establishments which account for approximately 98 percent of U.S. economic output from manufacturing, and an expected similar proportion of manufacturing energy use. The amount of energy use was collected for all operations of each establishment surveyed. Highlights of the report include profiles for the four major energy-consuming industries (petroleum refining, chemical, paper, and primary metal industries), and an analysis of the effects of changes in the natural gas and electricity markets on the manufacturing sector. Seven appendices are included to provide detailed background information. 10 figs., 51 tabs.

NONE

1997-12-01T23:59:59.000Z

350

Manufacturing consumption of energy 1991  

SciTech Connect (OSTI)

This report provides estimates on energy consumption in the manufacturing sector of the US economy. These estimates are based on data from the 1991 Manufacturing Energy Consumption Survey (MECS). This survey--administered by the Energy End Use and Integrated Statistics Division, Office of Energy Markets and End Use, Energy Information Administration (EIA)--is the most comprehensive source of national-level data on energy-related information for the manufacturing industries.

Not Available

1994-12-01T23:59:59.000Z

351

Robotics and Manufacturing Automation Laboratory (Mechanical Eng'g Dept.) STANDARD OPERATING PROCEDURE (SOP)  

E-Print Network [OSTI]

Robotics and Manufacturing Automation Laboratory (Mechanical Eng'g Dept.) STANDARD OPERATING on the robot control unit and the computer. Once the controller has booted, the green light on the indicator and audible alarm #12;Robotics and Manufacturing Automation Laboratory (Mechanical Eng'g Dept.) STANDARD

Thompson, Michael

352

ITP Nanomanufacturing: Nanomanufacturing Portfolio: Manufacturing...  

Energy Savers [EERE]

More Documents & Publications Sustainable Nanomaterials Workshop Advanced Manufacturing Office, U.S. Department of Energy Nanocomposite Materials for Lithium-Ion Batteries...

353

Manufacturing Spotlight: Boosting American Competitiveness  

Office of Energy Efficiency and Renewable Energy (EERE)

Find out how the Energy Department is helping bring new clean energy technologies to the marketplace and make manufacturing processes more energy efficient.

354

Manufacturing Demonstration Facility Technology Collaborations...  

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

from industry to assess applicability of new technologies that can reduce manufacturing energy intensity or produce new, energy-efficient products. As part of the technology...

355

Paradigm or Paradox: Can we Attribute Species Changes to Global Climate Change in Light of Decreasing Water Temperatures in Central California?  

E-Print Network [OSTI]

California and Adjacent Waters. University of Californiamarmoratus) in California waters as assessed in 2005. ReportMonitoring MPAs in Deep Water off Central California: 2007

Breaker, Laurence; Cailliet, Gregor; Launer, Andrea; Wadsworth, Tom

2012-01-01T23:59:59.000Z

356

Roll-To-Roll Process for Transparent Metal Electrodes in OLED Manufacturing  

SciTech Connect (OSTI)

This program will develop and demonstrate a new manufacturing technology that can help to improve the efficiency and reduce the cost of producing the next generation solid-state lighting (OLEDs)for a broad range of commercial applications. This will not only improve US competitiveness in the manufacturing sector but will also result in a positive impact in meeting the Department of Energy’s goal of developing high efficiency lighting while reducing the environmental impact.

Slafer, W. Dennis

2010-06-02T23:59:59.000Z

357

Report from the Light Water Reactor Sustainability Workshop on Advanced Instrumentation, Information, and Control Systems and Human-System Interface Technologies  

SciTech Connect (OSTI)

The Light Water Reactor Sustainability (LWRS) Program is a research and development (R&D) program sponsored by the U.S. Department of Energy (DOE). The program is operated in close collaboration with industry R&D programs to provide the technical foundations for licensing and managing the long-term, safe, and economical operation of Nuclear Power Plants that are currently in operation. The LWRS Program focus is on longer-term and higher-risk/reward research that contributes to the national policy objectives of energy and environmental security. Advanced instruments and control (I&C) technologies are needed to support the safe and reliable production of power from nuclear energy systems during sustained periods of operation up to and beyond their expected licensed lifetime. This requires that new capabilities to achieve process control be developed and eventually implemented in existing nuclear assets. It also requires that approaches be developed and proven to achieve sustainability of I&C systems throughout the period of extended operation. The strategic objective of the LWRS Program Advanced Instrumentation, Information, and Control Systems Technology R&D pathway is to establish a technical basis for new technologies needed to achieve safety and reliability of operating nuclear assets and to implement new technologies in nuclear energy systems. This will be achieved by carrying out a program of R&D to develop scientific knowledge in the areas of: • Sensors, diagnostics, and prognostics to support characterization and prediction of the effects of aging and degradation phenomena effects on critical systems, structures, and components (SSCs) • Online monitoring of SSCs and active components, generation of information, and methods to analyze and employ online monitoring information • New methods for visualization, integration, and information use to enhance state awareness and leverage expertise to achieve safer, more readily available electricity generation. As an initial step in accomplishing this effort, the Light Water Reactor Sustainability Workshop on Advanced Instrumentation, Information, and Control Systems and Human-System Interface Technologies was held March 20–21, 2009, in Columbus, Ohio, to enable industry stakeholders and researchers in identification of the nuclear industry’s needs in the areas of future I&C technologies and corresponding technology gaps and research capabilities. Approaches for collaboration to bridge or fill the technology gaps were presented and R&D activities and priorities recommended. This report documents the presentations and discussions of the workshop and is intended to serve as a basis for the plan under development to achieve the goals of the I&C research pathway.

Bruce P. Hallbert; J. J. Persensky; Carol Smidts; Tunc Aldemir; Joseph Naser

2009-08-01T23:59:59.000Z

358

Design for manufacturability Design verification  

E-Print Network [OSTI]

ITRS Design #12;Design · Design for manufacturability · Design verification #12;Design for Manufacturability · Architecture challenges · Logic and circuit challenges · Layout and physical design challenges · Expected to be the source of multiple DFM challenges · Invest in variability reduction or design

Patel, Chintan

359

Petrick Technology Trends Of Manufacturing  

E-Print Network [OSTI]

#12;323 Petrick Technology Trends chapter 9 The Future Of Manufacturing Irene Petrick Technology Trends This chapter is a story about the future of manufacturing based on three predictions: · that firms sophisticated modeling and simulation of both new products and production processes; · that additive

360

Freese-casting as a Novel Manufacturing Process for Fast Reactor Fuels  

SciTech Connect (OSTI)

Advanced burner reactors are designed to reduce the amount of long-lived radioactive isotopes that need to be disposed of as waste. The input feedstock for creating advanced fuel forms comes from either recycle of used light water reactor fuel or recycle of fuel from a fast burner reactor. Fuel for burner reqctors requires novel fuel types based on new materials and designs that can acieve higher performance requirements (higher burn up, higher power, and greator margins to fuel melting) then yet achieved. One promising strategy to improved fuel performance is the manufacture of metal or ceramic scaffolds which are designed to allow for a welldefined placement of the fuel into the host, and this in a manner that permits greater control than that possible in the production of typical CERMET fuels.

Wegst, Ulrike G.K.; Allen, Todd; Sridharan, Kumar

2014-04-07T23:59:59.000Z

Note: This page contains sample records for the topic "lighting manufacturing water" 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

A SCOPING STUDY: Development of Probabilistic Risk Assessment Models for Reactivity Insertion Accidents During Shutdown In U.S. Commercial Light Water Reactors  

SciTech Connect (OSTI)

This report documents the scoping study of developing generic simplified fuel damage risk models for quantitative analysis from inadvertent reactivity insertion events during shutdown (SD) in light water pressurized and boiling water reactors. In the past, nuclear fuel reactivity accidents have been analyzed both mainly deterministically and probabilistically for at-power and SD operations of nuclear power plants (NPPs). Since then, many NPPs had power up-rates and longer refueling intervals, which resulted in fuel configurations that may potentially respond differently (in an undesirable way) to reactivity accidents. Also, as shown in a recent event, several inadvertent operator actions caused potential nuclear fuel reactivity insertion accident during SD operations. The set inadvertent operator actions are likely to be plant- and operation-state specific and could lead to accident sequences. This study is an outcome of the concern which arose after the inadvertent withdrawal of control rods at Dresden Unit 3 in 2008 due to operator actions in the plant inadvertently three control rods were withdrawn from the reactor without knowledge of the main control room operator. The purpose of this Standardized Plant Analysis Risk (SPAR) Model development project is to develop simplified SPAR Models that can be used by staff analysts to perform risk analyses of operating events and/or conditions occurring during SD operation. These types of accident scenarios are dominated by the operator actions, (e.g., misalignment of valves, failure to follow procedures and errors of commissions). Human error probabilities specific to this model were assessed using the methodology developed for SPAR model human error evaluations. The event trees, fault trees, basic event data and data sources for the model are provided in the report. The end state is defined as the reactor becomes critical. The scoping study includes a brief literature search/review of historical events, developments of a small set of comprehensive event trees and fault trees and recommendation for future work.

S. Khericha

2011-06-01T23:59:59.000Z

362

Hollings Manufacturing Extension Partnership: A Commercialization Collaborator  

E-Print Network [OSTI]

of services, from innovation strategies to process improvements to green manufacturing. MEP also worksHollings Manufacturing Extension Partnership: A Commercialization Collaborator MEP · MANUFACTURING Manufacturing Extension Partnership (MEP) works with small and mid-sized U.S. manufacturers to help them create

363

Light harvesting arrays  

DOE Patents [OSTI]

A light harvesting array useful for the manufacture of devices such as solar cells comprises: (a) a first substrate comprising a first electrode; and (b) a layer of light harvesting rods electrically coupled to the first electrode, each of the light harvesting rods comprising a polymer of Formula I: X.sup.1.paren open-st.X.sup.m+1).sub.m (I) wherein m is at least 1, and may be from two, three or four to 20 or more; X.sup.1 is a charge separation group (and preferably a porphyrinic macrocycle, which may be one ligand of a double-decker sandwich compound) having an excited-state of energy equal to or lower than that of X.sup.2, and X.sup.2 through X.sup.m+1 are chromophores (and again are preferably porphyrinic macrocycles).

Lindsey, Jonathan S. (Raleigh, NC)

2002-01-01T23:59:59.000Z

364

SCDAP/RELAP5/MOD 3.1 code manual: MATPRO, A library of materials properties for Light-Water-Reactor accident analysis. Volume 4  

SciTech Connect (OSTI)

The SCDAP/RELAP5 code has been developed for best estimate transient simulation of light -- water-reactor coolant systems during a severe accident. The code models the coupled behavior of the reactor coolant system, the core, fission products released during a severe accident transient as well as large and small break loss of coolant accidents, operational transients such as anticipated transient without SCRAM, loss of offsite power, loss of feedwater, and loss of flow. A generic modeling approach is used that permits as much of a particular system to be modeled as necessary. Control system and secondary system components are included to permit modeling of plant controls, turbines, condensers, and secondary feedwater conditioning systems. This volume, Volume IV, describes the material properties correlations and computer subroutines (MATPRO) used by SCDAP/RELAP5. formulation of the materials properties are generally semi-empirical in nature. The materials property subroutines contained in this document are for uranium, uranium dioxide, mixed uranium-plutonium dioxide fuel, zircaloy cladding, zirconium dioxide, stainless steel, stainless steel oxide, silver-indium-cadmium alloy, cadmium, boron carbide, Inconel 718, zirconium-uranium-oxygen melts, fill gas mixtures, carbon steel, and tungsten. This document also contains descriptions of the reaction and solution rate models needed to analyze a reactor accident.

Hagrman, D.T. [ed.; Allison, C.M.; Berna, G.A. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)] [and others

1995-06-01T23:59:59.000Z

365

Validation Work to Support the Idaho National Engineering and Environmental Laboratory Calculational Burnup Methodology Using Shippingport Light Water Breeder Reactor (LWBR) Spent Fuel Assay Data  

SciTech Connect (OSTI)

Six uranium isotopes and fourteen fission product isotopes were calculated on a mass basis at end-of-life (EOL) conditions for three fuel rods from different Light Water Breeder Reactor (LWBR) measurements. The three fuel rods evaluated here were taken from an LWBR seed module, a standard blanket module, and a reflector (Type IV) module. The calculated results were derived using a depletion methodology previously employed to evaluate many of the radionuclide inventories for spent nuclear fuels at the Idaho National Engineering and Environmental Laboratory. The primary goal of the calculational task was to further support the validation of this particular calculational methodology and its application to diverse reactor types and fuels. Result comparisons between the calculated and measured mass concentrations in the three rods indicate good agreement for the three major uranium isotopes (U-233, U-234, U-235) with differences of less than 20%. For the seed and standard blanket rod, the U-233 and U-234 differences were within 5% of the measured values (these two isotopes alone represent greater than 97% of the EOL total uranium mass). For the major krypton and xenon fission product isotopes, differences of less than 20% and less than 30% were observed, respectively. In general, good agreement was obtained for nearly all the measured isotopes. For these isotopes exhibiting significant differences, possible explanations are discussed in terms of measurement uncertainty, complex transmutations, etc.

J. W. Sterbentz

1999-08-01T23:59:59.000Z

366

Smart Lighting ERC Industrial Speaker Series  

E-Print Network [OSTI]

. About Crystal IS Crystal IS Inc. is the world leading manufacturer of ultraviolet light emitting diodes on native AlN high-quality substrates. These layers are fabricated into mid- ultraviolet light emitting diodes with peak wavelengths in the range of 240-275 nm. The low threading dislocation density

Varela, Carlos

367

Radioluminescent lighting technology  

SciTech Connect (OSTI)

The glow-in-the-dark stereotype that characterizes the popular image of nuclear materials is not accidental. When the French scientist, Henri Becquerel, first discovered radioactivity in 1896, he was interested in luminescence. Radioluminescence, the production of light from a mixture of energetic and passive materials, is probably the oldest practical application of the unstable nucleus. Tritium-based radioluminescent lighting, in spite of the biologically favorable character of the gaseous tritium isotope, was included in the general tightening of environmental and safety regulations. Tritium light manufacturers would have to meet two fundamental conditions: (1) The benefit clearly outweighed the risk, to the extent that even the perceived risk of a skeptical public would be overcome. (2) The need was significant enough that the customer/user would be willing and able to afford the cost of regulation that was imposed both in the manufacture, use and eventual disposal of nuclear materials. In 1981, researchers at Oak Ridge National Laboratory were investigating larger radioluminescent applications using byproduct nuclear material such as krypton-85, as well as tritium. By 1982, it appeared that large source, (100 Curies or more) tritium gas tube, lights might be useful for marking runways and drop zones for military operations and perhaps even special civilian aviation applications. The successful development of this idea depended on making the light bright enough and demonstrating that large gas tube sources could be used and maintained safely in the environment. This successful DOE program is now in the process of being completed and closed-out. Working closely with the tritium light industry, State governments and other Federal agencies, the basic program goals have been achieved. This is a detailed report of what they have learned, proven, and discovered. 91 refs., 29 figs., 5 tabs. (JF)

Not Available

1990-01-01T23:59:59.000Z

368

Manufacturing development of low activation vanadium alloys  

SciTech Connect (OSTI)

General Atomics is developing manufacturing methods for vanadium alloys as part of a program to encourage the development of low activation alloys for fusion use. The culmination of the program is the fabrication and installation of a vanadium alloy structure in the DIII-D tokamak as part of the Radiative Divertor modification. Water-cooled vanadium alloy components will comprise a portion of the new upper divertor structure. The first step, procuring the material for this program has been completed. The largest heat of vanadium alloy made to date, 1200 kg of V-4Cr-4Ti, has been produced and is being converted into various product forms. Results of many tests on the material during the manufacturing process are reported. Research into potential fabrication methods has been and continues to be performed along with the assessment of manufacturing processes particularly in the area of joining. Joining of vanadium alloys has been identified as the most critical fabrication issue for their use in the Radiative Divertor Program. Joining processes under evaluation include resistance seam, electrodischarge (stud), friction and electron beam welding. Results of welding tests are reported. Metallography and mechanical tests are used to evaluate the weld samples. The need for a protective atmosphere during different welding processes is also being determined. General Atomics has also designed, manufactured, and will be testing a helium-cooled, high heat flux component to assess the use of helium cooled vanadium alloy components for advanced tokamak systems. The component is made from vanadium alloy tubing, machined to enhance the heat transfer characteristics, and joined to end flanges to allow connection to the helium supply. Results are reported.

Smith, J.P.; Johnson, W.R.; Baxi, C.B.

1996-10-01T23:59:59.000Z

369

Beryllium Manufacturing Processes  

SciTech Connect (OSTI)

This report is one of a number of reports that will be combined into a handbook on beryllium. Each report covers a specific topic. To-date, the following reports have been published: (1) Consolidation and Grades of Beryllium; (2) Mechanical Properties of Beryllium and the Factors Affecting these Properties; (3) Corrosion and Corrosion Protection of Beryllium; (4) Joining of Beryllium; (5) Atomic, Crystal, Elastic, Thermal, Nuclear, and other Properties of Beryllium; and (6) Beryllium Coating (Deposition) Processes and the Influence of Processing Parameters on Properties and Microstructure. The conventional method of using ingot-cast material is unsuitable for manufacturing a beryllium product. Beryllium is a highly reactive metal with a high melting point, making it susceptible to react with mold-wall materials forming beryllium compounds (BeO, etc.) that become entrapped in the solidified metal. In addition, the grain size is excessively large, being 50 to 100 {micro}m in diameter, while grain sizes of 15 {micro}m or less are required to meet acceptable strength and ductility requirements. Attempts at refining the as-cast-grain size have been unsuccessful. Because of the large grain size and limited slip systems, the casting will invariably crack during a hot-working step, which is an important step in the microstructural-refining process. The high reactivity of beryllium together with its high viscosity (even with substantial superheat) also makes it an unsuitable candidate for precision casting. In order to overcome these problems, alternative methods have been developed for the manufacturing of beryllium. The vast majority of these methods involve the use of beryllium powders. The powders are consolidated under pressure in vacuum at an elevated temperature to produce vacuum hot-pressed (VHP) blocks and vacuum hot-isostatic-pressed (HIP) forms and billets. The blocks (typically cylindrical), which are produced over a wide range of sizes (up to 183 cm dia. by 61 cm high), may be cut or machined into parts or be thermomechanically processed to develop the desired microstructure, properties, and shapes. Vacuum hot-isostatic pressing and cold-isostatic pressing (CIP) followed by sintering and possibly by a final HIP'ing (CIP/Sinter/HIP) are important in their use for the production of near net-shaped parts. For the same starting powder, a HIP'ed product will have less anisotropy than that obtained for a VHP'ed product. A schematic presentation illustrating the difference between VHP'ing and HIP'ing is shown in Figure I-1. The types of powders and the various beryllium grades produced from the consolidated powders and their ambient-temperature mechanical properties were presented in the consolidation report referred to above. Elevated-temperature properties and the effect of processing variables on mechanical properties are described in the mechanical properties report. Beryllium can also be deposited as coatings as well as freestanding forms. The microstructure, properties, and various methods used that are related to the deposition of beryllium are discussed in the report on beryllium coatings.

Goldberg, A

2006-06-30T23:59:59.000Z

370

MANUFACTURING ACCELERATING THE INCORPORATION OF MATERIALS  

E-Print Network [OSTI]

MANUFACTURING ACCELERATING THE INCORPORATION OF MATERIALS ADVANCES INTO MANUFACTURING PROCESSES NATIONAL NEED The proposed topic "Accelerating the Incorporation of Materials Advances into Manufacturing organizations, leading researchers from academic institutions, and others. Materials performance is often

Magee, Joseph W.

371

Advanced Manufacture of Reflectors  

SciTech Connect (OSTI)

The main project objective has been to develop an advanced gravity sag method for molding large glass solar reflectors with either line or point focus, and with long or short focal length. The method involves taking standard sized squares of glass, 1.65 m x 1.65 m, and shaping them by gravity sag into precision steel molds. The method is designed for high volume manufacture when incorporated into a production line with separate pre-heating and cooling. The performance objectives for the self-supporting glass mirrors made by this project include mirror optical accuracy of 2 mrad root mean square (RMS), requiring surface slope errors <1 mrad rms, a target not met by current production of solar reflectors. Our objective also included development of new methods for rapidly shaping glass mirrors and coating them for higher reflectivity and soil resistance. Reflectivity of 95% for a glass mirror with anti-soil coating was targeted, compared to the present ~94% with no anti-soil coating. Our mirror cost objective is ~$20/m2 in 2020, a significant reduction compared to the present ~$35/m2 for solar trough mirrors produced for trough solar plants. During the first year a custom batch furnace was built to develop the method with high power radiative heating to simulate transfer of glass into a hot slumping zone in a production line. To preserve the original high polish of the float glass on both front and back surfaces, as required for a second surface mirror, the mold surface is machined to the required shape as grooves which intersect the glass at cusps, reducing the mold contact area to significantly less than 1%. The mold surface is gold-plated to reflect thermal radiation. Optical metrology of glass replicas made with the system has been carried out with a novel, custom-built test system. This test provides collimated, vertically-oriented parallel beams from a linear array of co-aligned lasers translated in a perpendicular direction across the reflector. Deviations of each reflected beam from the paraboloid focus give a direct measure of surface slope error. Key findings • A gravity sag method for large (2.5 m2) second surface glass solar reflectors has been developed and demonstrated to a uniquely high level of accuracy. Mirror surface slope accuracy of 0.65 mrad in one dimension, 0.85 mrad in 2 dimensions (point focus) has been demonstrated by commercial partner REhnu using this process. This accuracy exceeds by a factor of two current solar reflector accuracy. Our replicas meet the Sunshot accuracy objective of 2 mrad optical, which requires better than 1 mrad rms slope error. • Point-focus as well as line-focus mirrors have been demonstrated at 1.65 m x 1.65 m square – a unique capability. • The new process using simple molds is economical. The molds for the 1.65 m square reflectors are bent and machined steel plates on a counter-weighted flotation support. To minimize thermal coupling by radiative heat transfer, the mold surface is grooved and gilded. The molds are simple to manufacture, and have minimal thermal stresses and distortion in use. Lapping and bending techniques have been developed to obtain better than 1 mrad rms surface mold accuracy. Float glass is sagged into the molds by rapid radiative heating, using a custom high power (350 kW) furnace. The method of manufacture is well suited for small as well as large volume production, and as it requires little capital investment and no high technology, it could be used anywhere in the world to make solar concentrating reflectors. • A novel slope metrology method for full 1.65 aperture has been demonstrated, with 25 mm resolution across the face of the replicas. The method is null and therefore inherently accurate: it can easily be reproduced without high-tech equipment and does not need sophisticated calibration. We find by cross calibration with reference trough reflectors from RioGlass that our null-test laser system yields a measurement accuracy better than 0.4 mrad rms slope error. Our system is inexpensive and could have broad application for test

Angel, Roger [University of Arizona

2014-12-17T23:59:59.000Z

372

Light Water Reactor Sustainability Newsletter  

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

the operation of commercial nuclear power plants require conservative mar- gins of fracture toughness for the RPV materials, both during normal operation and under accident...

373

Light Water Reactor Sustainability Newsletter  

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

The small volume required for such analysis is beneficial for correlating with the small-scale mechanical testing currently being investigated. Further studies on the...

374

Opportunities and Challenges to Sustainable Manufacturing and CMP  

E-Print Network [OSTI]

for Implementing Green Manufacturing,” Trans. North AmericanBoyd, S. , LMAS Green Manufacturing Research Presentation,MANUFACTURING AND GREEN MANUFACTURING Sustainability is

Dornfeld, David

2009-01-01T23:59:59.000Z

375

Commercial Lighting  

Broader source: Energy.gov [DOE]

Commercial lighting accounts for more than 20 percent of total commercial building energy use. The Energy Department works to reduce lighting energy use through research and deployment.

376

Cooling Water System Optimization  

E-Print Network [OSTI]

During summer months, many manufacturing plants have to cut back in rates because the cooling water system is not providing sufficient cooling to support higher production rates. There are many low/no-cost techniques available to improve tower...

Aegerter, R.

2005-01-01T23:59:59.000Z

377

New Advanced System Utilizes Industrial Waste Heat to Power Water...  

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

Water Reuse ADVANCED MANUFACTURING OFFICE New Advanced System Utilizes Industrial Waste Heat to Power Water Purification Introduction As population growth and associated factors...

378

Additive Manufacturing Opportunities for Transportation | ornl...  

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

Additive Manufacturing Opportunities for Transportation Mar 13 2015 10:00 AM - 11:00 AM Lonnie Love, Manufacturing Systems Research Group Transportation Science Seminar Series...

379

Clean Energy Manufacturing Initiative: Increasing American Competitive...  

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

for a Clean Energy Manufacturing Innovation Institute related to composite materials and structures. The Manufacturing Demonstration Facility at Oak Ridge National...

380

Advanced Manufacturing Initiative Improves Turbine Blade Productivity...  

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

Advanced Manufacturing Initiative Improves Turbine Blade Productivity Advanced Manufacturing Initiative Improves Turbine Blade Productivity May 20, 2011 - 2:56pm Addthis This is an...

Note: This page contains sample records for the topic "lighting manufacturing water" 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

A Management Strategy for Additive Manufacturing:.  

E-Print Network [OSTI]

??The thesis is about a Management Strategy for Additive Manufacturing - how engineering change influences the NPD process through the adoption of new manufacturing technology.… (more)

Zahn, N.Z.

2014-01-01T23:59:59.000Z

382

National Electrical Manufacturers Association (NEMA) Response...  

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

Electrical Manufacturers Association (NEMA) Response to Smart Grid RFI National Electrical Manufacturers Association (NEMA) Response to Smart Grid RFI The National Electrical...

383

Additive Manufacturing Cluster Strategy | ornl.gov  

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

Additive Manufacturing Cluster Strategy SHARE Additive Manufacturing Cluster Strategy As the nation's premier research laboratory, ORNL is one of the world's most capable resources...

384

Welcome and Advanced Manufacturing Partnership (Text Version...  

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

200 school aged students go into this manufacturing demonstration facility and make 3D printing or other manufacturing parts. Design and make parts for their robots. For their...

385

Mechanical and Manufacturing Engineering Mechatronics Engineering Minor  

E-Print Network [OSTI]

Mechanical and Manufacturing Engineering Mechatronics Engineering Minor Students pursuing a BSc in mechanical or manufacturing engineering have experience and entrepreneurship. Mechatronics is the synergistic combination of mechanical

Calgary, University of

386

Advanced Technology Vehicles Manufacturing Incentive Program...  

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

Advanced Technology Vehicles Manufacturing Incentive Program Advanced Technology Vehicles Manufacturing Incentive Program This is an interim final rule that establishes the...

387

Process systems engineering of continuous pharmaceutical manufacturing  

E-Print Network [OSTI]

Continuous manufacturing offers a number of operational and financial benefits to pharmaceutical companies. This research examines the critical blending step for continuous pharmaceutical manufacturing and the characteristics ...

Abel, Matthew J

2010-01-01T23:59:59.000Z

388

Understanding Manufacturing Energy and Carbon Footprints, October...  

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

More Documents & Publications Understanding the 2010 Manufacturing Energy and Carbon Footprints U.S. Manufacturing Energy Use and Greenhouse Gas Emissions Analysis U.S....

389

Solid-State Lighting Manufacturing R&D Workshop  

Energy Savers [EERE]

Action Plan The Climate Action Plan has three pillars: 1) Mitigation: Cut Carbon Pollution in America 2) Adaptation: Prepare the U.S. for the Impacts of Climate Change 3)...

390

Solid-State Lighting Manufacturing Research and Development ...  

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

anticipated that success will lead to a more rapid adoptioninstallation of high-quality SSL products resulting in a significant reduction of energy use and a corresponding...

391

2009 Solid-State Lighting Vancouver Manufacturing Workshop Highlights |  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-Up from theDepartment( Sample of ShipmentSimulation, Analysisof Energy

392

Solid-State Lighting Manufacturing Research and Development - Round 3  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: AlternativeEnvironment,Institutes and ResponseStaffServicesFutureU.S.Solar CellSolid Oxide

393

Solid-State Lighting Manufacturing Research and Development - Round 4  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: AlternativeEnvironment,Institutes and ResponseStaffServicesFutureU.S.Solar CellSolid

394

Solid-State Lighting Manufacturing Workshop | Department of Energy  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment of Energy U.S. DepartmentCommitmentGovernmentSmartDay 7SolartheMarch 2015Nearly

395

Clean Energy Manufacturing Initiative Solid-State Lighting | Department of  

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

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

396

Manufacturing System Design Framework Manual  

E-Print Network [OSTI]

Previous Lean Aerospace Initiative research in factory operations had indicated that the greatest performance gains are realized when the manufacturing system is designed from the top down and from supplier to the customer. ...

Vaughn, Amanda

2002-01-01T23:59:59.000Z

397

Wind Energy Manufacturing Tax Incentive  

Broader source: Energy.gov [DOE]

With the passage of [http://www.arkansasenergy.org/media/261385/act736.pdf HB 2230 (2009)] in April 2009, the Arkansas Legislature expanded a tax incentive for manufacturers of windmill blades or...

398

Reduction of the Radiotoxicity of Spent Nuclear Fuel Using a Two-Tiered System Comprising Light Water Reactors and Accelerator-Driven Systems  

SciTech Connect (OSTI)

Two main issues regarding the disposal of spent nuclear fuel from nuclear reactors in the United States in the geological repository Yucca Mountain are: (1) Yucca Mountain is not designed to hold the amount of fuel that has been and is proposed to be generated in the next few decades, and (2) the radiotoxicity (i.e., biological hazard) of the waste (particularly the actinides) does not decrease below that of natural uranium ore for hundreds of thousands of years. One solution to these problems may be to use transmutation to convert the nuclides in spent nuclear fuel to ones with shorter half-lives. Both reactor and accelerator-based systems have been examined in the past for transmutation; there are advantages and disadvantages associated with each. By using existing Light Water Reactors (LWRs) to burn a majority of the plutonium in spent nuclear fuel and Accelerator-Driven Systems (ADSs) to transmute the remainder of the actinides, the benefits of each type of system can be realized. The transmutation process then becomes more efficient and less expensive. This research searched for the best combination of LWRs with multiple recycling of plutonium and ADSs to transmute spent nuclear fuel from past and projected nuclear activities (assuming little growth of nuclear energy). The neutronic design of each system is examined in detail although thermal hydraulic performance would have to be considered before a final system is designed. The results are obtained using the Monte Carlo burnup code Monteburns, which has been successfully benchmarked for MOX fuel irradiation and compared to other codes for ADS calculations. The best combination of systems found in this research includes 41 LWRs burning mixed oxide fuel with two recycles of plutonium ({approx}40 years operation each) and 53 ADSs to transmute the remainder of the actinides from spent nuclear fuel over the course of 60 years of operation.

H.R. Trellue

2003-06-01T23:59:59.000Z

399

A study of a zone approach to IAEA (International Atomic Energy Agency) safeguards: The low-enriched-uranium zone of a light-water-reactor fuel cycle  

SciTech Connect (OSTI)

At present the IAEA designs its safeguards approach with regard to each type of nuclear facility so that the safeguards activities and effort are essentially the same for a given type and size of nuclear facility wherever it may be located. Conclusions regarding a state are derived by combining the conclusions regarding the effectiveness of safeguards for the individual facilities within a state. In this study it was convenient to define three zones in a state with a closed light-water-reactor nuclear fuel cycle. Each zone contains those facilities or parts thereof which use or process nuclear materials of the same safeguards significance: low-enriched uranium, radioactive spent fuel, or recovered plutonium. The possibility that each zone might be treated as an extended material balance area for safeguards purposes is under investigation. The approach includes defining the relevant features of the facilities in the three zones and listing the safeguards activities which are now practiced. This study has focussed on the fresh-fuel zone, the several facilities of which use or process low-enriched uranium. At one extreme, flows and inventories would be verified at each material balance area. At the other extreme, the flows into and out of the zone and the inventory of the whole zone would be verified. There are a number of possible safeguards approaches which fall between the two extremes. The intention is to develop a rational approach which will make it possible to compare the technical effectiveness and the inspection effort for the facility-oriented approach, for the approach involving the zone as a material balance area, and for some reasonable intermediate safeguards approaches.

Fishbone, L.G.; Higinbotham, W.A.

1986-06-01T23:59:59.000Z

400

Hollow spherical shell manufacture  

DOE Patents [OSTI]

A process for making a hollow spherical shell of silicate glass composition in which an aqueous suspension of silicate glass particles and an immiscible liquid blowing agent is placed within the hollow spherical cavity of a porous mold. The mold is spun to reduce effective gravity to zero and to center the blowing agent, while being heated so as to vaporize the immiscible liquid and urge the water carrier of the aqueous suspension to migrate into the body of the mold, leaving a green shell compact deposited around the mold cavity. The green shell compact is then removed from the cavity, and is sintered for a time and a temperature sufficient to form a silicate glass shell of substantially homogeneous composition and uniform geometry.

O'Holleran, Thomas P. (Belleville, MI)

1991-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "lighting manufacturing water" 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

Hollow spherical shell manufacture  

DOE Patents [OSTI]

A process is disclosed for making a hollow spherical shell of silicate glass composition in which an aqueous suspension of silicate glass particles and an immiscible liquid blowing agent is placed within the hollow spherical cavity of a porous mold. The mold is spun to reduce effective gravity to zero and to center the blowing agent, while being heated so as to vaporize the immiscible liquid and urge the water carrier of the aqueous suspension to migrate into the body of the mold, leaving a green shell compact deposited around the mold cavity. The green shell compact is then removed from the cavity, and is sintered for a time and a temperature sufficient to form a silicate glass shell of substantially homogeneous composition and uniform geometry. 3 figures.

O'Holleran, T.P.

1991-11-26T23:59:59.000Z

402

Designing a National Network for Manufacturing Innovation  

E-Print Network [OSTI]

Designing a National Network for Manufacturing Innovation NNMI and The Additive Manufacturing Pilot Introduction · NNMI principles · Public NMMI Design · Pilot Institute on Additive Manufacturing #12;IMI Mission Process, such as Additive Manufacturing An Advanced Material ­ e.g. lightweight, low cost carbon fiber

403

Guidelines for Manufacturers and Distributors  

Broader source: Energy.gov [DOE]

The Municipal Solid-State Street Lighting Consortium is intended to be a user's group — focused on the needs of participants making investments in street and area lighting — which provides a...

404

Root cause analysis of solder flux residue incidence in the manufacture of electronic power modules  

E-Print Network [OSTI]

This work investigates the root causes of the incidence of solder flux residue underneath electronic components in the manufacture of power modules. The existing deionized water-based centrifugal cleaning process was ...

Jain, Pranav

2011-01-01T23:59:59.000Z

405

Florida Power and Light- Business Energy Efficiency Rebates  

Broader source: Energy.gov [DOE]

Florida Power and Light (FPL) offers incentives for its business customers to upgrade the HVAC system, building envelope, water heating, refrigeration and lighting systems. The individual rebates...

406

Formation of Nitrogen- and Sulfur-Containing Light-Absorbing...  

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

Nitrogen- and Sulfur-Containing Light-Absorbing Compounds Accelerated by Evaporation of Water from Secondary Formation of Nitrogen- and Sulfur-Containing Light-Absorbing Compounds...

407

Manufacturing Energy and Carbon Footprints (2006 MECS)  

Broader source: Energy.gov [DOE]

Energy and Carbon Footprints provide a mapping of energy from supply to end use in manufacturing. They show us where energy is used and lost—and where greenhouse gases (GHGs) are emitted. Footprints are available below for 15 manufacturing sectors (representing 94% of all manufacturing energy use) and for U.S. manufacturing as a whole. Analysis of these footprints is also available in the U.S. Manufacturing Energy Use and Greenhouse Gas Emissions Analysis report.

408

Manufacturing for the Hydrogen Economy Manufacturing Research & Development  

E-Print Network [OSTI]

to coordinate and leverage the current federal efforts focused on manufacturability issues such as low-cost of the hydrogen and fuel cell technologies needed to move the United States toward a future hydrogen economy of a hydrogen energy economy, moving from today's laboratory-scale fabrication technologies to high

409

Manufacturing Innovation in the DOE  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGY TAX POLICIES7.pdfFuel2007Naval Reactors' Cyber SecurityManufacturingManufacturing

410

Sustainable Manufacturing via Multi-Scale, Physics-Based Process Modeling and Manufacturing-Informed Design, April 2013  

Broader source: Energy.gov [DOE]

Sustainable Manufacturing via Multi-Scale, Physics-Based Process Modeling and Manufacturing-Informed Design

411

Manufacturing Energy and Carbon Footprints  

E-Print Network [OSTI]

Significant opportunities exist for improving energy efficiency in U.S. manufacturing. A first step in realizing these opportunities is to identify how industry is using energy. Where does it come from? What form is it in? Where is it used? How much...

Brueske, S.; Lorenz, T.

2012-01-01T23:59:59.000Z

412

Process for manufacturing multilayer capacitors  

DOE Patents [OSTI]

The invention is directed to a method of manufacture of multilayer electrical components, especially capacitors, and components made by such a method. High capacitance dielectric materials and low cost metallizations layered with such dielectrics may be fabricated as multilayer electrical components by sintering the metallizations and the dielectrics during the fabrication process by application of microwave radiation.

Lauf, Robert J. (Oak Ridge, TN); Holcombe, Cressie E. (Knoxville, TN); Dykes, Norman L. (Oak Ridge, TN)

1996-01-01T23:59:59.000Z

413

Additive manufacturing method of producing  

E-Print Network [OSTI]

Additive manufacturing method of producing silver or copper tracks on polyimide film Problem/stripping) using an additive process support by a novel bio- degradable photo-initiator package. technology. Building on previous work by Hoyd- Gigg Ng et al. [1,2], Heriot-Watt has developed an additive film

Painter, Kevin

414

Heat treating of manufactured components  

DOE Patents [OSTI]

An apparatus for heat treating manufactured components using microwave energy and microwave susceptor material is disclosed. The system typically includes an insulating vessel placed within a microwave applicator chamber. A moderating material is positioned inside the insulating vessel so that a substantial portion of the exterior surface of each component for heat treating is in contact with the moderating material.

Ripley, Edward B. (Knoxville, TN)

2012-05-22T23:59:59.000Z

415

Systems, Inc. Manufacturing Program Manager  

E-Print Network [OSTI]

70819 #12;Advanced Energy Systems, Inc. Outline ·Introduction ·Accomplishments Phase I ·Technical Approach - Second Year ·Manufacturing Schedule Assessment -Top Level Phase II #12;Advanced Energy Systems Design and FEA of 5 cell RF Cavity, He Vessel, Power Coupler, & Cryostat -Interfaces to external piping

416

Water Management Best Practices  

E-Print Network [OSTI]

and Energy Star Programs ? www.epa.gov/watersense www.energystar.gov ? Conserve Florida Water Clearinghouse ? http://www.conservefloridawater.org/ ? Arizona Department of Water Resources ? www.azwater.gov/conservation The True Cost of Water... Future Demands Municipal Manufacturing Mining Steam Electric Agriculture New Codes & Standards Green Certification& Labeling Programs ? Green Restaurants, Hotels, etc. ? Green Guide for Health Care ? LEED ? GBI ? EPA Water Sense ? EPA...

Hoffman, W.

2011-01-01T23:59:59.000Z

417

Smart Lighting Controller!! Smart lighting!  

E-Print Network [OSTI]

1! Smart Lighting Controller!! #12;2! Smart lighting! No need to spend energy lighting the room if://blogs.stthomas.edu/realestate/2011/01/24/residential-real-estate-professionals-how-do-you- develop feedback! There is a connection between the output and the input! Therefore forces inputs to same voltage

Anderson, Betty Lise

418

Commercial Lighting and LED Lighting Incentives  

Broader source: Energy.gov [DOE]

Incentives for energy efficient commercial lighting equipment as well as commercial LED lighting equipment are available to businesses under the Efficiency Vermont Lighting and LED Lighting...

419

Goodman Manufacturing: Order (2012-CE-1509)  

Broader source: Energy.gov [DOE]

DOE ordered Goodman Manufacturing Company L.P. to pay an $8,000 civil penalty after finding Goodman Manufacturing had failed to certify that certain room air conditioners comply with the applicable energy conservation standard.

420

Goodman Manufacturing: Proposed Penalty (2011-SE-4301)  

Broader source: Energy.gov [DOE]

DOE alleged in a Notice of Proposed Civil Penalty that Goodman Manufacturing manufactured and distributed noncompliant basic model CPC180* commercial package air conditioners in the U.S.

Note: This page contains sample records for the topic "lighting manufacturing water" 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

Manufacturing Metallic Parts with Designed Mesostructure  

E-Print Network [OSTI]

Additive Manufacturing Laser Engineered Net Shaping Electron Beam Melting Williams, C. B., F. M. Mistree, D Additive Manufacturing © Christopher B. Williams Electron Beam Melting Electron Beam Melting Direct Metal

422

Mechanics and Design, Manufacturing Professor Hani Naguib  

E-Print Network [OSTI]

Mechanical and Industrial Engineering Manufacturing What is Manufacturing? The transformation of materials. Apple Canada(Se12), Revenue: $5,067,109 9. CGI Group(Se12), Revenue: $4,786,857 10. Siemens Canada(Se12

423

Faculty Position in Mechanical Engineering Additive Manufacturing  

E-Print Network [OSTI]

using additive manufacturing in applications such as, but not limited to the net shape manufacture of) Promoting Well-Being, Finding Cures; (3) Building Communities, Expanding Opportunities; and (4) Harnessing

424

Montana Manufacturing Center www.mtmanufacturingcenter.com  

E-Print Network [OSTI]

Montana Manufacturing Center www.mtmanufacturingcenter.com University Technical Assistance Program and wellness industry. Commenting on the strategy, Chief Opera- tions Officer and Six Sigma Green Belt Brad achieve that. NLI offers premier manufacturing and laboratories services (www

Dyer, Bill

425

Objective assessment of manufacturing technology investments  

E-Print Network [OSTI]

Amgen is a biotechnology company with manufacturing plants throughout the world. New manufacturing technologies are constantly being developed and implemented in order to address cost, quality, regulation, and competitive ...

Rothman, Craig Jeremy

2012-01-01T23:59:59.000Z

426

Building Blocks for the Future of Manufacturing  

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

for the Future of Manufacturing Building Blocks for the Future of Manufacturing Scott Smith 2011.05.04 Even though we grew up on opposite sides of the world, my colleague...

427

Mechanical and Manufacturing Engineering Petroleum Engineering Minor  

E-Print Network [OSTI]

of Chemical and Petroleum Engineering for their petroleum engineering minor. As well, mechanical engineeringMechanical and Manufacturing Engineering Petroleum Engineering Minor The Department of Mechanical and Manufacturing Engineering offers a minor in petroleum engineering within the mechanical engineering major

Calgary, University of

428

USA Manufacturing: Order (2013-CE-5336)  

Broader source: Energy.gov [DOE]

DOE ordered USA Manufacturing to pay a $8,000 civil penalty after finding USA Manufacturing had failed to certify that certain models of walk-in cooler and freezer components comply with the applicable energy conservation standards.

429

Benefits and Barriers of Smart Manufacturing  

E-Print Network [OSTI]

Decision makers in the industrial sector have only recently started to realize the potential of smart manufacturing to transform manufacturing. The potential gains in efficiency at the process and supply-chain level are still largely unknown...

Trombley, D.; Rogers, E.

2014-01-01T23:59:59.000Z

430

Refrigerator Manufacturers: Order (2013-CE-5341)  

Broader source: Energy.gov [DOE]

DOE ordered Refrigerator Manufacturers, LLC to pay a $8,000 civil penalty after finding Refrigerator Manufacturers had failed to certify that certain models of walk-in cooler and freezer components comply with the applicable energy conservation standards.

431

IGSHPA AnnualIGSHPA Annual Manufacturers UpdateManufacturers Update  

E-Print Network [OSTI]

October 9, 2013 #12;Howard Newton HVAC System EngineerHVAC System Engineer Mammoth Water Source Heat Pumps CES Group & Mammoth Springfield, MO · Holland, MI ·Water Source Heat Pumps Packaged Systems EdenbridgeRib Mammoth Vertical Water-to-Air Heat Pump for Space Conditioning 20 #12;Systems In The Geothermal Market New

432

Clean Energy Manufacturing Initiative Industrial Efficiency and...  

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

Industrial Efficiency and Energy Productivity Video Clean Energy Manufacturing Initiative Industrial Efficiency and Energy Productivity Video Addthis Description Industrial...

433

Webinar: Additive Manufacturing for Fuel Cells  

Broader source: Energy.gov [DOE]

Video recording and text version of the webinar titled "Additive Manufacturing for Fuel Cells," originally presented on February 11, 2014.

434

Electromagnetic compatibility in semiconductor manufacturing  

SciTech Connect (OSTI)

Electromagnetic Interference (EMI) causes problems in semiconductor manufacturing facilities that range from nuisances to major disruptions of production. In many instances, these issues are addressed in a reactionary rather than proactive manner by individuals who do not have the experience or the equipment necessary to combat EMI problems in a timely, cost effective manner. This approach leads to expensive retrofits, reduced equipment availability, long recovery times, and in some cases, line yield impacts. The goal of electromagnetic compatibility (EMC) in semiconductor manufacturing is to ensure that semiconductor process, metrology, and support equipment operate as intended without being affected by electromagnetic disturbances either transmitted through air (radiated interference), or transferred into the equipment via a conductive media (conducted interference). Rather than being neglected until serious issues arise, EMC should be considered in the early stages of facility design, in order to gain the most benefit at the lowest cost.

Montoya, J.A. [Intel Corp., Hillsboro, OR (United States)

1995-12-31T23:59:59.000Z

435

Manufacturing of Plutonium Tensile Specimens  

SciTech Connect (OSTI)

Details workflow conducted to manufacture high density alpha Plutonium tensile specimens to support Los Alamos National Laboratory's science campaigns. Introduces topics including the metallurgical challenge of Plutonium and the use of high performance super-computing to drive design. Addresses the utilization of Abaqus finite element analysis, programmable computer numerical controlled (CNC) machining, as well as glove box ergonomics and safety in order to design a process that will yield high quality Plutonium tensile specimens.

Knapp, Cameron M [Los Alamos National Laboratory

2012-08-01T23:59:59.000Z

436

Advanced Manufacturing | Department of Energy  

Energy Savers [EERE]

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustion |Energy UsageAUDITVehiclesTankless orA BRIEF HISTORY OFEnergyAdvanced Manufacturing

437

Manufacturing Perspective | Department of Energy  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustion | Department of Energy Low-TemperatureEnergyAll ManufacturingFoodOctobertoPerspective

438

Manufacturing Energy and Carbon Footprints (2010 MECS) | Department of  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: AlternativeEnvironment, SafetyWater ConservationDepartmentEnergy Manufacturing Energy and

439

Lighting Renovations  

Broader source: Energy.gov [DOE]

When undertaking a lighting renovation in a Federal building, daylighting is the primary renewable energy opportunity. Photovoltaics (PV) also present an excellent opportunity. While this guide...

440

Cerenkov Light  

ScienceCinema (OSTI)

The bright blue glow from nuclear reactors is Cerenkov light. Karl Slifer describes how nuclear physicists can use this phenomenon to study the nucleus of the atom.

Slifer, Karl

2014-05-22T23:59:59.000Z

Note: This page contains sample records for the topic "lighting manufacturing water" 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

Cerenkov Light  

SciTech Connect (OSTI)

The bright blue glow from nuclear reactors is Cerenkov light. Karl Slifer describes how nuclear physicists can use this phenomenon to study the nucleus of the atom.

Slifer, Karl

2013-06-13T23:59:59.000Z

442

Sustainable Manufacturing via Multi-Scale, Physics-Based Process...  

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

Manufacturing via Multi-Scale, Physics-Based Process Modeling and Manufacturing-Informed Design, April 2013 Sustainable Manufacturing via Multi-Scale, Physics-Based Process...

443

Machine Tool Design and Operation Strategies for Green Manufacturing  

E-Print Network [OSTI]

Operation Strategies for Green Manufacturing Nancy DIAZ 1 ,to implement green manufacturing in machining includingopportunities to green manufacturing exist at all levels of

2010-01-01T23:59:59.000Z

444

A Review of Engineering Research in Sustainable Manufacturing  

E-Print Network [OSTI]

SWOT Anal- ysis for Green Manufacturing Strategy Selection,”Yung, K. L. , 2010, “Green Manufacturing Using IntegratedDornfeld, D. , 2013, Green Manufacturing: Fundamentals and

2013-01-01T23:59:59.000Z

445

Decision-Making to Reduce Manufacturing Greenhouse Gas Emissions  

E-Print Network [OSTI]

how to think about green manufacturing and sustainability.for sustainable or green manufacturing is that it is not anthe implementation of green manufacturing, where a wedge

Reich-Weiser, Corinne

2010-01-01T23:59:59.000Z

446

U.S. Advanced Manufacturing and Clean Energy Technology Challenges  

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

Manufacturing and Clean Energy Technology Challenges May 6, 2014 AMO Peer Review Mark Johnson Director Advanced Manufacturing Office www.manufacturing.energy.gov This presentation...

447

Additive Manufacturing in China: Aviation and Aerospace Applications (Part 2)  

E-Print Network [OSTI]

Analysis May 2013 Additive Manufacturing in China: Aviationan overview of China’s additive manufacturing industry wasmilitary achievements in additive manufacturing. 2 Initial

ANDERSON, Eric

2013-01-01T23:59:59.000Z

448

A Review of Engineering Research in Sustainable Manufacturing  

E-Print Network [OSTI]

shape part, e.g. , additive manufacturing, Transactions offace operations. Additive manufacturing of metal componentsenvironmen- tal merits of additive manufacturing relative to

2013-01-01T23:59:59.000Z

449

Contact Manufacturing Demonstration Facility Craig Blue, Ph.D...  

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

Manufacturing Demonstration Facility Craig Blue, Ph.D. Director, Manufacturing Demonstration Facility (865) 574-4351 blueca@ornl.gov INNOVATIONS IN MANUFACTURING www.ornl.gov...

450

Low Temperature PEM Fuel Cell Manufacturing Needs  

E-Print Network [OSTI]

Low Temperature PEM Fuel Cell Manufacturing Needs Presented by Duarte Sousa, PE Manufacturing Fuel Cell Manhattan Project #12; Cost drivers were identified for the following: · MEA · Plates · Balance of Plant (BOP) · Fuel Processing Manufacturing Fuel Cell Project ­ Phase 1 Note that this presentation

451

Energy Manufacturing Matthew Realff and Steven Danyluk  

E-Print Network [OSTI]

Energy Manufacturing Matthew Realff and Steven Danyluk Georgia Institute of Technology This white Foundation and held in Arlington VA, on March 24-25, 2009 on Energy Manufacturing. The workshop attendees participated in discussions and presented their views on energy manufacturing and the presentations

Das, Suman

452

8th Global Conference on Sustainable Manufacturing  

E-Print Network [OSTI]

manufacturing in the UAE · Potentials of renewables · Education for sustainability engineering · Green supply8th Global Conference on Sustainable Manufacturing Architecture for Sustainable Engineering for research institutes and industrial partners related to the area of sustainable manufacturing. It enables

Berlin,Technische Universität

453

Additive manufacturing of metallic tracks on  

E-Print Network [OSTI]

Additive manufacturing of metallic tracks on green ceramic/dielectrics Problem this technology microelectronics such as manufacture of LTCC ceramic/ Dielectric antenna and rapid PCB prototyping or repair (note: may require additional tooling/ set up time) · Rapid Prototyping & small scale manufacture

Painter, Kevin

454

ICME & MGI Big Area Additive Manufacturing  

E-Print Network [OSTI]

ICME & MGI · Big Area Additive Manufacturing · Neutron Characterization for AM · Materials problems in additive manu- facturing (AM). Additive manufacturing, or three-dimensional (3-D) printing of the world's most advanced neu- tron facilities, the HFIR and SNS, to characterize additive manufactured

455

Pseudomonas fluorescens -A robust manufacturing platform  

E-Print Network [OSTI]

Pseudomonas fluorescens -A robust manufacturing platform Reprinted from July/August 2004 Speciality at efficient- ly transporting single chain antibodies and other mammalian-derived proteins. In addition production. Dowpharma, a contract manufacturing services unit of Dow Chemical, has developed a manufacturing

Lebendiker, Mario

456

Manufacturing Research & Development for Systems that will  

E-Print Network [OSTI]

focused on manufacturability issues such as low-cost, high-volume manufacturing systems, advanced to move the United States toward a future hydrogen economy. While many scientific, technical's laboratory-scale fabrication technologies to high-volume commercial manufacturing has been identified as one

457

EFFECTIVE STRUCTURAL HEALTH MONITORING WITH ADDITIVE MANUFACTURING  

E-Print Network [OSTI]

will be presented for components that can be processed by additive manufacturing (AM) or 3D printing. The origin structures. KEYWORDS : structural health monitoring methodology, 3D printing, additive manufacturing, fatigue, intelligent structure INTRODUCTION Additive manufacturing (AM), also known as 3D Printing or Rapid

Boyer, Edmond

458

Manufacturing  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustion | Department of Energy Low-TemperatureEnergy Maine09 BalanceStorageReviewFlow of

459

Light Water Reactor Sustainability (LWRS) Program – Non-Destructive Evaluation (NDE) R&D Roadmap for Determining Remaining Useful Life of Aging Cables in Nuclear Power Plants  

SciTech Connect (OSTI)

The purpose of the non-destructive evaluation (NDE) R&D Roadmap for Cables is to support the Materials Aging and Degradation (MAaD) R&D pathway. The focus of the workshop was to identify the technical gaps in detecting aging cables and predicting their remaining life expectancy. The workshop was held in Knoxville, Tennessee, on July 30, 2012, at Analysis and Measurement Services Corporation (AMS) headquarters. The workshop was attended by 30 experts in materials, electrical engineering, U.S. Nuclear Regulatory Commission (NRC), U.S. Department of Energy (DOE) National Laboratories (Oak Ridge National Laboratory, Pacific Northwest National Laboratory, Argonne National Laboratory, and Idaho National Engineering Laboratory), NDE instrumentation development, universities, commercial NDE services and cable manufacturers, and Electric Power Research Institute (EPRI). The motivation for the R&D roadmap comes from the need to address the aging management of in-containment cables at nuclear power plants (NPPs).

Simmons, Kevin L.; Ramuhalli, Pradeep; Brenchley, David L.; Coble, Jamie B.; Hashemian, Hash; Konnik, Robert; Ray, Sheila

2012-09-14T23:59:59.000Z

460

Light Water Reactor Sustainability (LWRS) Program – Non-Destructive Evaluation (NDE) R&D Roadmap for Determining Remaining Useful Life of Aging Cables in Nuclear Power Plants  

SciTech Connect (OSTI)

Executive Summary [partial] The purpose of the non-destructive evaluation (NDE) R&D Roadmap for Cables is to support the Materials Aging and Degradation (MAaD) R&D pathway. A workshop was held to gather subject matter experts to develop the NDE R&D Roadmap for Cables. The focus of the workshop was to identify the technical gaps in detecting aging cables and predicting their remaining life expectancy. The workshop was held in Knoxville, Tennessee, on July 30, 2012, at Analysis and Measurement Services Corporation (AMS) headquarters. The workshop was attended by 30 experts in materials, electrical engineering, and NDE instrumentation development from the U.S. Nuclear Regulatory Commission (NRC), U.S. Department of Energy (DOE) National Laboratories (Oak Ridge National Laboratory, Pacific Northwest National Laboratory, Argonne National Laboratory, and Idaho National Engineering Laboratory), universities, commercial NDE service vendors and cable manufacturers, and the Electric Power Research Institute (EPRI).

Simmons, K.L.; Ramuhali, P.; Brenchley, D.L.; Coble, J.B.; Hashemian, H.M.; Konnick, R.; Ray, S.

2012-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "lighting manufacturing water" 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

Controls for Solid-State Lighting  

SciTech Connect (OSTI)

This study predicts new hybrid lighting applications for LEDs. In hybrid lighting, LEDs provide a low-energy 'standby' light level while another, more powerful, efficient light source provides light for occupied periods. Lighting controls will allow the two light sources to work together through an appropriate control strategy, typically motion-sensing. There are no technical barriers preventing the use of low through high CRI LEDs for standby lighting in many interior and exterior applications today. The total luminous efficacy of LED systems could be raised by increasing the electrical efficiency of LED drivers to the maximum practically achievable level (94%). This would increase system luminous efficacy by 20-25%. The expected market volumes for many types of LEDs should justify the evolution of new LED drivers that use highly efficient ICs and reduce parts count by means of ASICs. Reducing their electronics parts count by offloading discrete components onto integrated circuits (IC) will allow manufacturers to reduce the cost of LED driver electronics. LED luminaire manufacturers will increasingly integrate the LED driver and thermal management directly in the LED fixture. LED luminaires of the future will likely have no need for separable lamp and ballast because the equipment life of all the LED luminaire components will all be about the same (50,000 hours). The controls and communications techniques used for communicating with conventional light sources, such as dimmable fluorescent lighting, are appropriate for LED illumination for energy management purposes. DALI has been used to control LED systems in new applications and the emerging ZigBee protocol could be used for LEDs as well. Major lighting companies are already moving in this direction. The most significant finding is that there is a significant opportunity to use LEDs today for standby lighting purposes. Conventional lighting systems can be made more efficient still by using LEDs to provide a low-energy standby state when lower light levels are acceptable.

Rubinstein, Francis

2007-06-22T23:59:59.000Z

462

NREL Manufacturing R&D Workshop NREL H2/FC Manufacturing R&D Workshop  

E-Print Network [OSTI]

&D Workshop Fuel Cell Proton Exchange Membrane (PEM) and Solid Oxide Fuel Cell (SOFC) Manufacturing Lines and driving down the cost of fuel cell manufacturing through automation. What are the key technical Membrane Electrode Assembly Manufacturing Hypothetical Fuel Cell Manufacturing Platforms August 11, 2011

463

Research on advanced photovoltaic manufacturing technology  

SciTech Connect (OSTI)

This report outlines opportunities for significantly advancing the scale and economy of high-volume manufacturing of high-efficiency photovoltaic (PV) modules. We propose to pursue a concurrent effort to advance existing crystalline silicon module manufacturing technology and to implement thin film CuInSe{sub 2} (CIS) module manufacturing. This combination of commercial-scale manufacturing of high-efficiency crystalline silicon modules and of pilot-scale manufacturing of low-cost thin film CIS technology will support continued, rapid growth of the US PV industry.

Jester, T.; Eberspacher, C. (Siemens Solar Industries, Camarillo, CA (United States))

1991-11-01T23:59:59.000Z

464

Manufacturing Demonstration Facility Technology Collaborations for US Manufacturers in Advanced  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: VegetationEquipment Surfaces and InterfacesAdministrationManufacturing - GE Appliances, ORNL Low-Cost

465

2011 EL Project Title and Number: Sustainability of Unit Manufacturing Processes  

E-Print Network [OSTI]

such as energy and material consumption, emissions, waste, and water usage of manufacturing processes. However sustainability performance metrics (such as energy and material consumption, emissions, waste, and water usage efficiency, the US industries need reliable measurement methods to evaluate sustainability performances

Perkins, Richard A.

466

THE MASTER OF ENGINEERING IN MANUFACTURING ENGINEERING PROGRAM PLANNING SHEET  

E-Print Network [OSTI]

for Manufacturing ME 526 Simulation of Physical Processes ME 535 Green Manufacturing METHE MASTER OF ENGINEERING IN MANUFACTURING ENGINEERING PROGRAM PLANNING SHEET be at the 500 level or above. 1. Core Manufacturing Requirement ­ 24 credits

467

Ohio Advanced Energy Manufacturing Center  

SciTech Connect (OSTI)

The program goal of the Ohio Advanced Energy Manufacturing Center (OAEMC) is to support advanced energy manufacturing and to create responsive manufacturing clusters that will support the production of advanced energy and energy-efficient products to help ensure the nation's energy and environmental security. This goal cuts across a number of existing industry segments critical to the nation's future. Many of the advanced energy businesses are starting to make the transition from technology development to commercial production. Historically, this transition from laboratory prototypes through initial production for early adopters to full production for mass markets has taken several years. Developing and implementing manufacturing technology to enable production at a price point the market will accept is a key step. Since these start-up operations are configured to advance the technology readiness of the core energy technology, they have neither the expertise nor the resources to address manufacturing readiness issues they encounter as the technology advances toward market entry. Given the economic realities of today's business environment, finding ways to accelerate this transition can make the difference between success and failure for a new product or business. The advanced energy industry touches a wide range of industry segments that are not accustomed to working together in complex supply chains to serve large markets such as automotive and construction. During its first three years, the Center has catalyzed the communication between companies and industry groups that serve the wide range of advanced energy markets. The Center has also found areas of common concern, and worked to help companies address these concerns on a segment or industry basis rather than having each company work to solve common problems individually. EWI worked with three industries through public-private partnerships to sew together disparate segments helping to promote overall industry health. To aid the overall advanced energy industry, EWI developed and launched an Ohio chapter of the non-profit Advanced Energy Economy. In this venture, Ohio joins with six other states including Colorado, Connecticut, Illinois, Maine, Massachusetts, New Hampshire, Rhode Island and Vermont to help promote technologies that deliver energy that is affordable, abundant and secure. In a more specific arena, EWI's advanced energy group collaborated with the EWI-run Nuclear Fabrication Consortium to promote the nuclear supply chain. Through this project EWI has helped bring the supply chain up to date for the upcoming period of construction, and assisted them in understanding the demands for the next generation of facilities now being designed. In a more targeted manner, EWI worked with 115 individual advanced energy companies that are attempting to bring new technology to market. First, these interactions helped EWI develop an awareness of issues common to companies in different advanced energy sectors. By identifying and addressing common issues, EWI helps companies bring technology to market sooner and at a lower cost. These visits also helped EWI develop a picture of industry capability. This helped EWI provide companies with contacts that can supply commercial solutions to their new product development challenges. By providing assistance in developing supply chain partnerships, EWI helped companies bring their technology to market faster and at a lower cost than they might have been able to do by themselves. Finally, at the most granular level EWI performed dedicated research and development on new manufacturing processes for advanced energy. During discussions with companies participating in advanced energy markets, several technology issues that cut across market segments were identified. To address some of these issues, three crosscutting technology development projects were initiated and completed with Center support. This included reversible welds for batteries and high temperature heat exchangers. It also included a novel advanced weld trainer that EWI

Kimberly Gibson; Mark Norfolk

2012-07-30T23:59:59.000Z

468

Manufacturing method of photonic crystal  

DOE Patents [OSTI]

A manufacturing method of a photonic crystal is provided. In the method, a high-refractive-index material is conformally deposited on an exposed portion of a periodic template composed of a low-refractive-index material by an atomic layer deposition process so that a difference in refractive indices or dielectric constants between the template and adjacent air becomes greater, which makes it possible to form a three-dimensional photonic crystal having a superior photonic bandgap. Herein, the three-dimensional structure may be prepared by a layer-by-layer method.

Park, In Sung; Lee, Tae Ho; Ahn, Jin Ho; Biswas, Rana; Constant, Kristen P.; Ho, Kai-Ming; Lee, Jae-Hwang

2013-01-29T23:59:59.000Z

469

Method for manufacturing magnetohydrodynamic electrodes  

DOE Patents [OSTI]

A method of manufacturing electrodes for use in a magnetohydrodynamic (MHD) generator is described comprising the steps of preparing a billet having a core of a first metal, a tubular sleeve of a second metal, and an outer sheath of an extrusile metal; evacuating the space between the parts of the assembled billet; extruding the billet; and removing the outer jacket. The extruded bar may be made into electrodes by cutting and bending to the shape required for an MHD channel frame. The method forms a bond between the first metal of the core and the second metal of the sleeve strong enough to withstand a hot and corrosive environment.

Killpatrick, D.H.; Thresh, H.R.

1980-06-24T23:59:59.000Z

470

Manufacturing Fuel Cell Manhattan Project  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious RankCombustion | Department of Energy Low-TemperatureEnergyAll ManufacturingFoodOctoberto DOE Fuel

471

Manufacturing Initiative | Clean Energy | ORNL  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recovery challenge fund Las ConchasTrail5,722,326ManhattanEnergyManufacturing

472

Surface Light Field Rendering for Virtual Product Design  

E-Print Network [OSTI]

Surface Light Field Rendering for Virtual Product Design Jan MESETH, Gero MĂ?LLER, Reinhard KLEIN illumination solution including accurate materials, which is stored as an outgoing Surface Light Field (SLF-facto standard in manufacturing industries like the automotive industry. They are used, e.g., for performing

Behnke, Sven

473

Main Canal, Maverick County Water Control and Improvement District above Central Power and Light hydro-electric plant, at Maverick and Kinney Counties, Texas  

E-Print Network [OSTI]

BAIN CANAL NA~ICK COUNTY WATW CONTROL AND INPROllZXBZ DISTRICT ABOVE C~ POWER AND LION HYDRO ELECTRIC PLANT& AT, SIAVERICK AND KINNEY COUNT'S, T~~S By John J. Ledbetter, Jr. Approved as to style and content by: (Che man Committee Heed of pa... ment or Student Advisor May l952 MAIN CANAL RIA~ICK C01E1TY EATER CONTROL AND INPROVZGiWZ DISTRICT ABOVE G~ F01' AND LIGHT HYDRO-ELECTRIC PLANT, AT MAVERICK AND KINNEY GGKJZIES ~ TEXAS By John J. Ledbetter, Jr, A Thesis Submitted...

Ledbetter, John J

2012-06-07T23:59:59.000Z

474

Recessed light fixtures: Infiltration energy loss  

SciTech Connect (OSTI)

This article reports that a recent study revealed that fluorescent bulbs can reduce convective energy losses by 15--65% as compared to incandescent bulbs. Recessed light fixtures are commonly installed in offices and homes. However, a problem arises in homes when the fixtures are set in the ceiling such that the top of the light fixture is exposed to the unconditioned air in the attic. Because some air flow is necessary around the light to avoid overheating, the manufacturers do not make all the fixtures leak tight, only those that are rated for lower wattage bulbs. The need for cooling the fixture may conflict with some building efficiency codes.

Bennett, S.M.; Perez-Blanco, H. (Pennsylvania State Univ., University Park, PA (United States))

1994-06-01T23:59:59.000Z

475

Industrial Scale Demonstration of Smart Manufacturing Achieving...  

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

TX National Center for Manufacturing Sciences Ann Arbor, MI Nimbis Services McLean, VA Praxair Tonawanda, NY Rockwell Automation Milwaukee, WI For additional information, please...

476

Manufacturing Ecosystems and Keystone Technologies (Text Version...  

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

Culver, Special Assistant to Program Manager, Advanced Manufacturing Office (AMO) Kelly Visconti, AAAS Science & Technology Policy Fellow, AMO DR. LEO CHRISTODOULOU: I would...

477

Agenda: Fiber Reinforced Polymer Composite Manufacturing Workshop  

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

Blue Team B (Washington II & III) - Manufacturing Process Technology Facilitators - Kelly Visconti and Steve Sikirica; Note taker - Theresa Miller Red Team (Madison Room) -...

478

Manufacturing Demonstration Facility Workshop Videos | Department...  

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

on March 12, 2012. Lauren Culver, Special Assistant to Program Manager, AMO, and Kelly Visconti, AAAS Science & Technology Policy Fellow, AMO, speaking at the Manufacturing...

479

Performance, Market and Manufacturing Constraints relevant to...  

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

Constraints relevant to the Industrialization of Thermoelectric Devices Market pricing of thermoelectric raw materials and processing, cost of manufacture of devices and...

480

Energy & Manufacturing Workforce Training Topics List - Version...  

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

View this searchable list of the training programs in the areas of energy andor manufacturing. Information provided in this list includes: the subjects being taught, grantee,...

Note: This page contains sample records for the topic "lighting manufacturing water" 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

2010 Manufacturing Energy and Carbon Footprints: Definitions...  

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

Definitions and Assumptions 2010 Manufacturing Energy and Carbon Footprints: Definitions and Assumptions This 13-page document defines key terms and details assumptions and...

482

Oak Ridge National Laboratory Manufacturing Demonstration Facility  

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

Oak Ridge National Laboratory Manufacturing Demonstration Facility Technology Collaborations | Proposal Guidelines Proposal Guidelines Proposals should be no more than 5 single...

483

Energy-Related Carbon Emissions in Manufacturing  

Reports and Publications (EIA)

Energy-related carbon emissions in manufacturing analysis and issues related to the energy use, energy efficiency, and carbon emission indicators.

2000-01-01T23:59:59.000Z

484

Supplemental Comments of the Plumbing Manufacturers Instititute...  

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

Supplemental Comments of the Plumbing Manufacturers Instititute Regarding the Economic Impacts of the Proposed Definition of "Showerhead," Docket No. EERE-2010-BT-NOA-0016...

485

Renewable Energy Manufacturing Tax Credit (South Carolina)  

Broader source: Energy.gov [DOE]

South Carolina offers a ten percent income tax credit to the manufacturers of renewable energy operations* for tax years 2010 through 2015.

486

Establishing Greener Products and Manufacturing Processes  

E-Print Network [OSTI]

KEYWORDS: Life Cycle Assessment, LCA, Green manufacturing,cycle phases, Life Cycle Assessment (LCA). The followingimpact. 2.2 Life Cycle Assessment (LCA) and Related Metrics

Linke, Barbara; Huang, Yu-Chu; Dornfeld, David

2012-01-01T23:59:59.000Z

487

Welcome and Advanced Manufacturing Partnership (Text Version)  

Broader source: Energy.gov [DOE]

This is a text version of the Welcome and Advanced Manufacturing Partnership video, originally presented on March 12, 2012 at the MDF Workshop held in Chicago, Illinois.

488

American Energy and Manufacturing Competitiveness Summit  

Broader source: Energy.gov [DOE]

The American Energy and Manufacturing Competitiveness Summit will bring together leaders and perspectives from industry, government, academia, national laboratories, labor, and policy organizations...

489

Clean Energy Manufacturing Initiative Midwest Regional Summit...  

Office of Environmental Management (EM)

Fiber Reinforced Polymer Composite Manufacturing Workshop Multimaterial Joining Workshop Characterization of Thermo-Mechanical Behaviors of Advanced High Strength Steels (AHSS)...

490

Innovative Manufacturing Initiative Recognition Day, Advanced...  

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

infrastructure Education and training Policy EEREAMO Focus * Manufacturing in the US * GDP and employment enhancement * Energy efficiency and clean energy industry * Energy...

491

Manufacturing Barriers to High Temperature PEM Commercialization...  

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

Barriers to High Temperature PEM Commercialization Presented at the NREL Hydrogen and Fuel Cell Manufacturing R&D Workshop in Washington, DC, August 11-12, 2011....

492

Manufacturing Ecosystems and Keystone Technologies (Text Version)  

Broader source: Energy.gov [DOE]

This is a text version of the Manufacturing Ecosystems and Keystone Technologies video, originally presented on March 12, 2012 at the MDF Workshop held in Chicago, Illinois.

493

Solar Manufacturing Incentive Grant (SMIG) Program  

Broader source: Energy.gov [DOE]

Created in 1995 and administered jointly by the Virginia Department of Mines, Minerals and Energy, and the Virginia Economic Development Partnership, the Solar Manufacturing Incentive Grant (SMIG)...

494

Green Manufacturing Initiative Annual Report 2010  

E-Print Network [OSTI]

Green Manufacturing Initiative Annual Report 2010 Dr. John Patten Dr. David Meade May 3, 2011 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 Energy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 Herman Miller Energy Center . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2

de Doncker, Elise

495

Low Energy Ion Implantationin Semiconductor Manufacturing | U...  

Office of Science (SC) Website

Low Energy Ion Implantation in Semiconductor Manufacturing Nuclear Physics (NP) NP Home About Research Facilities Science Highlights Benefits of NP Applications of Nuclear Science...

496

2014 Manufacturing Energy and Carbon Footprints: Definitions...  

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

and Assumptions A number of key terms are used to interpret the manufacturing energy and carbon footprints. The terms associated with the energy footprint analysis are...

497

Project Profile: Improved Large Aperture Collector Manufacturing...  

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

feasibility demonstrations focused in three main areas: an aggressive manufacturing optimization of the collector sub-structures for lower input material costs & mechanized...

498

clean energy manufacturing | netl.doe.gov  

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

efforts across the DOE Office of Energy Efficiency & Renewable Energy's (EERE's) clean energy technology offices and Advanced Manufacturing Office, focusing on American...

499

Solid State Lighting Program (Falcon)  

SciTech Connect (OSTI)

Over the past two years, KLA-Tencor and partners successfully developed and deployed software and hardware tools that increase product yield for High Brightness LED (HBLED) manufacturing and reduce product development and factory ramp times. This report summarizes our development effort and details of how the results of the Solid State Light Program (Falcon) have started to help HBLED manufacturers optimize process control by enabling them to flag and correct identified killer defect conditions at any point of origin in the process manufacturing flow. This constitutes a quantum leap in yield management over current practice. Current practice consists of die dispositioning which is just rejection of bad die at end of process based upon probe tests, loosely assisted by optical in-line monitoring for gross process deficiencies. For the first time, and as a result of our Solid State Lighting Program, our LED manufacturing partners have obtained the software and hardware tools that optimize individual process steps to control killer defects at the point in the processes where they originate. Products developed during our two year program enable optimized inspection strategies for many product lines to minimize cost and maximize yield. The Solid State Lighting Program was structured in three phases: i) the development of advanced imaging modes that achieve clear separation between LED defect types, improves signal to noise and scan rates, and minimizes nuisance defects for both front end and back end inspection tools, ii) the creation of defect source analysis (DSA) software that connect the defect maps from back-end and front-end HBLED manufacturing tools to permit the automatic overlay and traceability of defects between tools and process steps, suppress nuisance defects, and identify the origin of killer defects with process step and conditions, and iii) working with partners (Philips Lumileds) on product wafers, obtain a detailed statistical correlation of automated defect and DSA map overlay to failed die identified using end product probe test results. Results from our two year effort have led to “automated end-to-end defect detection” with full defect traceability and the ability to unambiguously correlate device killer defects to optically detected features and their point of origin within the process. Success of the program can be measured by yield improvements at our partner’s facilities and new product orders.

Meeks, Steven

2012-06-30T23:59:59.000Z

500

Manufactured caverns in carbonate rock  

DOE Patents [OSTI]

Disclosed is a process for manufacturing underground caverns suitable in one embodiment for storage of large volumes of gaseous or liquid materials. The method is an acid dissolution process that can be utilized to form caverns in carbonate rock formations. The caverns can be used to store large quantities of materials near transportation facilities or destination markets. The caverns can be used for storage of materials including fossil fuels, such as natural gas, refined products formed from fossil fuels, or waste materials, such as hazardous waste materials. The caverns can also be utilized for applications involving human access such as recreation or research. The method can also be utilized to form calcium chloride as a by-product of the cavern formation process.

Bruce, David A.; Falta, Ronald W.; Castle, James W.; Murdoch, Lawrence C.

2007-01-02T23:59:59.000Z