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


1

Impact of Nuclear Power Plant Operations on Carbon-14 Generation, Chemical Forms, and Release  

Science Conference Proceedings (OSTI)

As nuclear power plants continue to implement best practices to reduce the total radioactivity in plant effluents, other radionuclides that were not previously significant fractions of the effluent streams will need to be quantified and reported. Carbon-14 can become a principal radionuclide for the gaseous effluent pathway as the concentrations of other radionuclides decrease. This report documents the potential opportunities for further understanding the impact of nuclear power plant operations on Carb...

2011-12-08T23:59:59.000Z

2

Electrical generating plant availability  

SciTech Connect

A discussion is given of actions that can improve availability, including the following: the meaning of power plant availability; The organization of the electric power industry; some general considerations of availability; the improvement of power plant availability--design factors, control of shipping and construction, maintenance, operating practices; sources of statistics on generating plant availability; effects of reducing forced outage rates; and comments by electric utilities on generating unit availability.

1975-05-01T23:59:59.000Z

3

Next Generation Geothermal Power Plants  

Science Conference Proceedings (OSTI)

This report analyzes several approaches to reduce the costs and enhance the performance of geothermal power generation plants. Electricity supply planners, research program managers, and engineers evaluating geothermal power plant additions or modifications can use this report to compare today's geothermal power systems to several near- and long-term future options.

1996-04-05T23:59:59.000Z

4

Next Generation Geothermal Power Plants  

SciTech Connect

A number of current and prospective power plant concepts were investigated to evaluate their potential to serve as the basis of the next generation geothermal power plant (NGGPP). The NGGPP has been envisaged as a power plant that would be more cost competitive (than current geothermal power plants) with fossil fuel power plants, would efficiently use resources and mitigate the risk of reservoir under-performance, and minimize or eliminate emission of pollutants and consumption of surface and ground water. Power plant concepts were analyzed using resource characteristics at ten different geothermal sites located in the western United States. Concepts were developed into viable power plant processes, capital costs were estimated and levelized busbar costs determined. Thus, the study results should be considered as useful indicators of the commercial viability of the various power plants concepts that were investigated. Broadly, the different power plant concepts that were analyzed in this study fall into the following categories: commercial binary and flash plants, advanced binary plants, advanced flash plants, flash/binary hybrid plants, and fossil/geothed hybrid plants. Commercial binary plants were evaluated using commercial isobutane as a working fluid; both air-cooling and water-cooling were considered. Advanced binary concepts included cycles using synchronous turbine-generators, cycles with metastable expansion, and cycles utilizing mixtures as working fluids. Dual flash steam plants were used as the model for the commercial flash cycle. The following advanced flash concepts were examined: dual flash with rotary separator turbine, dual flash with steam reheater, dual flash with hot water turbine, and subatmospheric flash. Both dual flash and binary cycles were combined with other cycles to develop a number of hybrid cycles: dual flash binary bottoming cycle, dual flash backpressure turbine binary cycle, dual flash gas turbine cycle, and binary gas turbine cycle. Results of this study indicate that dual flash type plants are preferred at resources with temperatures above 400 F. Closed loop (binary type) plants are preferred at resources with temperatures below 400 F. A rotary separator turbine upstream of a dual flash plant can be beneficial at Salton Sea, the hottest resource, or at high temperature resources where there is a significant variance in wellhead pressures from well to well. Full scale demonstration is required to verify cost and performance. Hot water turbines that recover energy from the spent brine in a dual flash cycle improve that cycle's brine efficiency. Prototype field tests of this technology have established its technical feasibility. If natural gas prices remain low, a combustion turbine/binary hybrid is an economic option for the lowest temperature sites. The use of mixed fluids appear to be an attractive low risk option. The synchronous turbine option as prepared by Barber-Nichols is attractive but requires a pilot test to prove cost and performance. Dual flash binary bottoming cycles appear promising provided that scaling of the brine/working fluid exchangers is controllable. Metastable expansion, reheater, Subatmospheric flash, dual flash backpressure turbine, and hot dry rock concepts do not seem to offer any cost advantage over the baseline technologies. If implemented, the next generation geothermal power plant concept may improve brine utilization but is unlikely to reduce the cost of power generation by much more than 10%. Colder resources will benefit more from the development of a next generation geothermal power plant than will hotter resources. All values presented in this study for plant cost and for busbar cost of power are relative numbers intended to allow an objective and meaningful comparison of technologies. The goal of this study is to assess various technologies on an common basis and, secondarily, to give an approximate idea of the current costs of the technologies at actual resource sites. Absolute costs at a given site will be determined by the specifics of a giv

Brugman, John; Hattar, Mai; Nichols, Kenneth; Esaki, Yuri

1995-09-01T23:59:59.000Z

5

Next Generation Geothermal Power Plants  

DOE Green Energy (OSTI)

A number of current and prospective power plant concepts were investigated to evaluate their potential to serve as the basis of the next generation geothermal power plant (NGGPP). The NGGPP has been envisaged as a power plant that would be more cost competitive (than current geothermal power plants) with fossil fuel power plants, would efficiently use resources and mitigate the risk of reservoir under-performance, and minimize or eliminate emission of pollutants and consumption of surface and ground water. Power plant concepts were analyzed using resource characteristics at ten different geothermal sites located in the western United States. Concepts were developed into viable power plant processes, capital costs were estimated and levelized busbar costs determined. Thus, the study results should be considered as useful indicators of the commercial viability of the various power plants concepts that were investigated. Broadly, the different power plant concepts that were analyzed in this study fall into the following categories: commercial binary and flash plants, advanced binary plants, advanced flash plants, flash/binary hybrid plants, and fossil/geothed hybrid plants. Commercial binary plants were evaluated using commercial isobutane as a working fluid; both air-cooling and water-cooling were considered. Advanced binary concepts included cycles using synchronous turbine-generators, cycles with metastable expansion, and cycles utilizing mixtures as working fluids. Dual flash steam plants were used as the model for the commercial flash cycle. The following advanced flash concepts were examined: dual flash with rotary separator turbine, dual flash with steam reheater, dual flash with hot water turbine, and subatmospheric flash. Both dual flash and binary cycles were combined with other cycles to develop a number of hybrid cycles: dual flash binary bottoming cycle, dual flash backpressure turbine binary cycle, dual flash gas turbine cycle, and binary gas turbine cycle. Results of this study indicate that dual flash type plants are preferred at resources with temperatures above 400 F. Closed loop (binary type) plants are preferred at resources with temperatures below 400 F. A rotary separator turbine upstream of a dual flash plant can be beneficial at Salton Sea, the hottest resource, or at high temperature resources where there is a significant variance in wellhead pressures from well to well. Full scale demonstration is required to verify cost and performance. Hot water turbines that recover energy from the spent brine in a dual flash cycle improve that cycle's brine efficiency. Prototype field tests of this technology have established its technical feasibility. If natural gas prices remain low, a combustion turbine/binary hybrid is an economic option for the lowest temperature sites. The use of mixed fluids appear to be an attractive low risk option. The synchronous turbine option as prepared by Barber-Nichols is attractive but requires a pilot test to prove cost and performance. Dual flash binary bottoming cycles appear promising provided that scaling of the brine/working fluid exchangers is controllable. Metastable expansion, reheater, Subatmospheric flash, dual flash backpressure turbine, and hot dry rock concepts do not seem to offer any cost advantage over the baseline technologies. If implemented, the next generation geothermal power plant concept may improve brine utilization but is unlikely to reduce the cost of power generation by much more than 10%. Colder resources will benefit more from the development of a next generation geothermal power plant than will hotter resources. All values presented in this study for plant cost and for busbar cost of power are relative numbers intended to allow an objective and meaningful comparison of technologies. The goal of this study is to assess various technologies on an common basis and, secondarily, to give an approximate idea of the current costs of the technologies at actual resource sites. Absolute costs at a given site will be determined by the specifics of a given pr

Brugman, John; Hattar, Mai; Nichols, Kenneth; Esaki, Yuri

1995-09-01T23:59:59.000Z

6

NETL: News Release - Advanced Coal Dryer Boosts Power Plant Performanc...  

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

Release Date: May 24, 2006 Advanced Coal Dryer Boosts Power Plant Performance Latest Project in President's Clean Coal Power Initiative Begins Operations in North Dakota...

7

The Next Generation Nuclear Plant  

DOE Green Energy (OSTI)

The Next Generation Nuclear Plant (NGNP) will be a demonstration of the technical, licensing, operational, and commercial viability of High Temperature Gas-Cooled Reactor (HTGR) technology for the production of process heat, electricity, and hydrogen. This nuclear- based technology can provide high-temperature process heat (up to 950°C) that can be used as a substitute for the burning of fossil fuels for a wide range of commercial applications (see Figure 1). The substitution of the HTGR for burning fossil fuels conserves these hydrocarbon resources for other uses, reduces uncertainty in the cost and supply of natural gas and oil, and eliminates the emissions of greenhouse gases attendant with the burning of these fuels. The HTGR is a passively safe nuclear reactor concept with an easily understood safety basis that permits substantially reduced emergency planning requirements and improved siting flexibility compared to other nuclear technologies.

Dr. David A. Petti

2009-01-01T23:59:59.000Z

8

AEO Early Release 2013 - renewable generation  

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

States will generate a bigger share of its electricity from renewable sources such as solar, wind, and biomass energy in the decades ahead, according to the new long-term...

9

Radioactive Releases Impact from Kozloduy Nuclear Power Plant, Bulgaria into the Environment  

SciTech Connect

The aim of this paper is to present a general overview of the radioactive releases impact generated by Kozloduy Nuclear Power Plant (KNPP), Bulgaria to the environment and public. The liquid releases presented are known as the so called controlled water discharges, that are generated after reprocessing of the inevitable accumulated liquid radioactive waste in the plant operation process. The radionuclides containing in the liquid releases are given in the paper as a result of systematic measuring. Database for radiation doses evaluation on the public around Kozloduy NPP site is developed using IAEA LADTAP computerized program. The computer code LADTAP represents realization of a model that evaluates the public dose as a result of NPP releases under normal operation conditions. The results of this evaluation were the basic licensing document for a new liquid release limit.

Genchev, G. T.; Kuleff, I.; Tanev, N. T.; Delistoyanova, E. S.; Guentchev, T.

2002-02-26T23:59:59.000Z

10

Combustion gas turbine/steam generator plant  

SciTech Connect

A fired steam generator is described that is interconnected with a gas turbine/steam generator plant having at least one gas turbine group followed by an exhaust-gas steam generator. The exhaust-gas steam generator has a preheater and an evaporator. The inlet of the preheater is connected to a feedwater distribution line which also feeds a preheater in the fired steam generator. The outlet of the preheater is connected to the evaporator of the fired steam generator. The evaporator outlet of the exhaust-gas steam generator is connected to the input of a superheater in the fired steam generator.

Aguet, E.

1975-11-18T23:59:59.000Z

11

Solana Generating Plant Solar Power Plant | Open Energy Information  

Open Energy Info (EERE)

Plant Solar Power Plant Plant Solar Power Plant Jump to: navigation, search Name Solana Generating Plant Solar Power Plant Facility Solana Generating Plant Sector Solar Facility Type Concentrating Solar Power Facility Status Under Construction Developer Abengoa Solar Location Gila Bend, Arizona Coordinates 32.916163°, -112.968727° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":32.916163,"lon":-112.968727,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

12

EIA - Annual Energy Outlook 2008 (Early Release)-Electricity Generation  

Gasoline and Diesel Fuel Update (EIA)

Electricity Generation Electricity Generation Annual Energy Outlook 2008 (Early Release) Electricity Generation U.S. electricity consumption—including both purchases from electric power producers and on-site generation—increases steadily in the AEO2008 reference case, at an average rate of 1.3 percent per year. In comparison, electricity consumption grew by annual rates of 4.2 percent, 2.6 percent, and 2.3 percent in the 1970s, 1980s, and 1990s, respectively. The growth rate in the AEO2008 projection is lower than in the AEO2007 reference case (1.5 percent per year), and it leads to lower projections of electricity generation. Figure 4. Electricity generation by fuel, 1980-2030 (billion kilowatthours). Need help, contact the National Energy Information Center at 202-586-8800.

13

Efficiently generate steam from cogeneration plants  

SciTech Connect

As cogeneration gets more popular, some plants have two choices of equipment for generating steam. Plant engineers need to have a decision chart to split the duty efficiently between (oil-fired or gas-fired) steam generators (SGs) and heat recovery steam generators (HRSGs) using the exhaust from gas turbines. Underlying the dilemma is that the load-versus-efficiency characteristics of both types of equipment are different. When the limitations of each type of equipment and its capability are considered, analysis can come up with several selection possibilities. It is almost always more efficient to generate steam in an HRSG (designed for firing) as compared with conventional steam generators. However, other aspects, such as maintenance, availability of personnel, equipment limitations and operating costs, should also be considered before making a final decision. Loading each type of equipment differently also affects the overall efficiency or the fuel consumption. This article describes the performance aspects of representative steam generators and gas turbine HRSGs and suggests how plant engineers can generate steam efficiently. It also illustrates how to construct a decision chart for a typical installation. The equipment was picked arbitrarily to show the method. The natural gas fired steam generator has a maximum capacity of 100,000 lb/h, 400-psig saturated steam, and the gas-turbine-exhaust HRSG has the same capacity. It is designed for supplementary firing with natural gas.

Ganapathy, V. [ABCO Industries, Abilene, TX (United States)

1997-05-01T23:59:59.000Z

14

Mesaba next-generation IGCC plant  

Science Conference Proceedings (OSTI)

Through a US Department of Energy (DOE) cooperative agreement awarded in June 2006, MEP-I LLC plans to demonstrate a next generation integrated gasification-combined cycle (IGCC) electric power generating plant, the Mesaba Energy Project. The 606-MWe plant (the first of two similarly sized plants envisioned by project sponsors) will feature next-generation ConocoPhillips E-Gas{trademark} technology first tested on the DOE-funded Wabash River Coal Gasification Repowering project. Mesaba will benefit from recommendations of an industry panel applying the Value Improving Practices process to Wabash cost and performance results. The project will be twice the size of Wabash, while demonstrating better efficient, reliability and pollutant control. The $2.16 billion project ($36 million federal cost share) will be located in the Iron Range region north of Duluth, Minnesota. Mesaba is one of four projects selected under Round II of the Clean Coal Power Initiative. 1 fig.

NONE

2006-01-01T23:59:59.000Z

15

NETL: News Release - More Electricity, Lower Emissions from Lignite Plants  

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

25, 2004 25, 2004 More Electricity, Lower Emissions from Lignite Plants Are Goals of New Clean Coal Project Fuel Enhancement System Expected to Boost Generating Capacities WASHINGTON, DC - Secretary of Energy Spencer Abraham today announced the testing of the Lignite Fuel Enhancement System, a new process that could dramatically reduce air emissions from certain coal-based power plants while boosting overall generating capacity. The project, conducted by Great River Energy, is expected to boost the generating capacity and efficiency of power plants that burn high-moisture lignite coal, thereby reducing air pollutants and greenhouse gases. The new technology uses waste heat to dry nearly a quarter of the moisture in the coal before it is fed into the power plant boiler.

16

Next Generation Geothermal Power Plants: 2012 Update  

Science Conference Proceedings (OSTI)

The intent of this report is to provide an update of historical and current trends in geothermal power plant technology, extending the previous Next Generation Geothermal Power Plant (NGGPP) report originally developed by EPRI in 1996.BackgroundIn its 1996 study, EPRI evaluated a number of technologies with the potential to lower the cost of geothermal power production or to expand cost effective power production to lower temperature resources, thus opening ...

2012-12-13T23:59:59.000Z

17

Alternative Fuels Data Center: Second Generation Biofuel Plant Depreciation  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Second Generation Second Generation Biofuel Plant Depreciation Deduction Allowance to someone by E-mail Share Alternative Fuels Data Center: Second Generation Biofuel Plant Depreciation Deduction Allowance on Facebook Tweet about Alternative Fuels Data Center: Second Generation Biofuel Plant Depreciation Deduction Allowance on Twitter Bookmark Alternative Fuels Data Center: Second Generation Biofuel Plant Depreciation Deduction Allowance on Google Bookmark Alternative Fuels Data Center: Second Generation Biofuel Plant Depreciation Deduction Allowance on Delicious Rank Alternative Fuels Data Center: Second Generation Biofuel Plant Depreciation Deduction Allowance on Digg Find More places to share Alternative Fuels Data Center: Second Generation Biofuel Plant Depreciation Deduction Allowance on AddThis.com...

18

A Short History of Hanford Waste Generation, Storage, and Release  

Science Conference Proceedings (OSTI)

Nine nuclear reactors and four reprocessing plants at Hanford produced nearly two-thirds of the plutonium used in the United States for government purposes . These site operations also created large volumes of radioactive and chemical waste. Some contaminants were released into the environment, exposing people who lived downwind and downstream. Other contaminants were stored. The last reactor was shut down in 1987, and the last reprocessing plant closed in 1990. Most of the human-made radioactivity and about half of the chemicals remaining onsite are kept in underground tanks and surface facilities. The rest exists in the soil, groundwater, and burial grounds. Hanford contains about 40% of all the radioactivity that exists across the nuclear weapons complex. Today, environmental restoration activities are under way.

Gephart, Roy E.

2003-10-01T23:59:59.000Z

19

Tax Credits and Renewable Generation (released in AEO2009)  

Reports and Publications (EIA)

Tax incentives have been an important factor in the growth of renewable generation over the past decade, and they could continue to be important in the future. The Energy Tax Act of 1978 (Public Law 95-618) established ITCs for wind, and EPACT92 established the Renewable Electricity Production Credit (more commonly called the PTC) as an incentive to promote certain kinds of renewable generation beyond wind on the basis of production levels. Specifically, the PTC provided an inflation-adjusted tax credit of 1.5 cents per kilowatthour for generation sold from qualifying facilities during the first 10 years of operation. The credit was available initially to wind plants and facilities that used closed-loop biomass fuels [75] and were placed in service after passage of the Act and before June 1999.

Information Center

2009-03-31T23:59:59.000Z

20

NETL: News Release - Premier Power Plant Test Facility Achieves Milestone,  

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

May 8, 2000 May 8, 2000 Premier Power Plant Test Facility Achieves Milestone,Raises Hopes for New Clean Coal Technology The world's premier test facility for future power plants has achieved a major milestone - and in the process, raised prospects for a new class of coal technology that researchers now believe could lead to cleaner, more efficient and lower cost electric power generation. The Power System Development Facility The Power System Development Facility at Wilsonville, Alabama, is the Nation's state-of-the-art test facility for 21st century power generating technologies. The U.S. Department of Energy and Southern Company today jointly announced the first successful test of a new type of technology for turning coal into gas. The gas could then be used in future turbines or fuel cells to

Note: This page contains sample records for the topic "generating plants release" 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

NETL: News Release - Wabash River Plant in Indiana to Host 1st...  

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

to US DOE Publications News Release Release Date: July 30, 2002 Wabash River Plant in Indiana to Host 1st Clean Coal-Powered Fuel Cell Decision to Relocate Fuel Cell Gives 2-Year...

22

Second-Generation Pressurized Fluidized Bed Combustion: Small gas turbine induustrial plant study  

SciTech Connect

Second-Generation Pressurized Fluidized Bed Combustion (PFBC) plants provide a coal-fired, high-efficiency, combined-cycle system for the generation of electricity and steam. The plants use lime-based sorbents in PFB combustors to meet environmental air standards without back-end gas desulfurization equipment. The second-generation system is an improvement over earlier PFBC concepts because it can achieve gas temperatures of 2100[degrees]F and higher for improved cycle efficiency while maintaining the fluidized beds at 1600[degrees]F for enhanced sulfur capture and minimum alkali release. Second-generation PFBC systems are capable of supplying the electric and steam process needs of industrial plants. The basic second-generation system can be applied in different ways to meet a variety of process steam and electrical requirements. To evaluate the potential of these systems in the industrial market, conceptual designs have been developed for six second-generation PFBC plants. These plants cover a range of electrical outputs from 6.3 to 41.5 MWe and steam flows from 46,067 to 442,337 lb/h. Capital and operating costs have been estimated for these six plants and for equivalent (in size) conventional, coal-fired atmospheric fluidized bed combustion cogeneration plants. Economic analyses were conducted to compare the cost of steam for both the second-generation plants and the conventional plants.

Shenker, J.; Garland, R.; Horazak, D.; Seifert, F.; Wenglarz, R.

1992-07-01T23:59:59.000Z

23

Second-Generation Pressurized Fluidized Bed Combustion: Small gas turbine industrial plant study  

SciTech Connect

Second-Generation Pressurized Fluidized Bed Combustion (PFBC) plants provide a coal-fired, high-efficiency, combined-cycle system for the generation of electricity and steam. The plants use lime-based sorbents in PFB combustors to meet environmental air standards without back-end gas desulfurization equipment. The second-generation system is an improvement over earlier PFBC concepts because it can achieve gas temperatures of 2100{degrees}F and higher for improved cycle efficiency while maintaining the fluidized beds at 1600{degrees}F for enhanced sulfur capture and minimum alkali release. Second-generation PFBC systems are capable of supplying the electric and steam process needs of industrial plants. The basic second-generation system can be applied in different ways to meet a variety of process steam and electrical requirements. To evaluate the potential of these systems in the industrial market, conceptual designs have been developed for six second-generation PFBC plants. These plants cover a range of electrical outputs from 6.3 to 41.5 MWe and steam flows from 46,067 to 442,337 lb/h. Capital and operating costs have been estimated for these six plants and for equivalent (in size) conventional, coal-fired atmospheric fluidized bed combustion cogeneration plants. Economic analyses were conducted to compare the cost of steam for both the second-generation plants and the conventional plants.

Shenker, J.; Garland, R.; Horazak, D.; Seifert, F.; Wenglarz, R.

1992-07-01T23:59:59.000Z

24

Vogtle Electric Generating Plant ETE Analysis Review  

Science Conference Proceedings (OSTI)

Under contract with the Nuclear Regulatory Commission (NRC), staff from Pacific Northwest National Laboratory (PNNL) and Sandia National Laboratory (SNL)-Albuquerque reviewed the evacuation time estimate (ETE) analysis dated April 2006 prepared by IEM for the Vogtle Electric Generating Plant (VEGP). The ETE analysis was reviewed for consistency with federal regulations using the NRC guidelines in Review Standard (RS)-002, Supplement 2 and Appendix 4 to NUREG-0654, and NUREG/CR-4831. Additional sources of information referenced in the analysis and used in the review included NUREG/CR-6863 and NUREG/CR-6864. The PNNL report includes general comments, data needs or clarifications, and requests for additional information (RAI) resulting from review of the ETE analysis.

Diediker, Nona H.; Jones, Joe A.

2006-12-09T23:59:59.000Z

25

Next Generation Nuclear Plant GAP Analysis Report  

DOE Green Energy (OSTI)

As a follow-up to the phenomena identification and ranking table (PIRT) studies conducted recently by NRC on next generation nuclear plant (NGNP) safety, a study was conducted to identify the significant 'gaps' between what is needed and what is already available to adequately assess NGNP safety characteristics. The PIRT studies focused on identifying important phenomena affecting NGNP plant behavior, while the gap study gives more attention to off-normal behavior, uncertainties, and event probabilities under both normal operation and postulated accident conditions. Hence, this process also involved incorporating more detailed evaluations of accident sequences and risk assessments. This study considers thermal-fluid and neutronic behavior under both normal and postulated accident conditions, fission product transport (FPT), high-temperature metals, and graphite behavior and their effects on safety. In addition, safety issues related to coupling process heat (hydrogen production) systems to the reactor are addressed, given the limited design information currently available. Recommendations for further study, including analytical methods development and experimental needs, are presented as appropriate in each of these areas.

Ball, Sydney J [ORNL; Burchell, Timothy D [ORNL; Corwin, William R [ORNL; Fisher, Stephen Eugene [ORNL; Forsberg, Charles W. [Massachusetts Institute of Technology (MIT); Morris, Robert Noel [ORNL; Moses, David Lewis [ORNL

2008-12-01T23:59:59.000Z

26

An emission time series generator for pollutant release modelling in urban areas  

Science Conference Proceedings (OSTI)

Dynamic priority pollutant (PP) fate models are being developed to assess appropriate strategies for limiting the release of PPs from urban sources and for treating PPs on a variety of spatial scales. Different possible sources of PP releases were mapped ... Keywords: Emission pattern, Generator, Priority pollutants, Release dynamics, Sewer catchment model, Time series

W. De Keyser; V. Gevaert; F. Verdonck; B. De Baets; L. Benedetti

2010-04-01T23:59:59.000Z

27

TRI (Toxic Chemical Release Inventory) for Power Plants RY2012 Version 1.  

Science Conference Proceedings (OSTI)

TRI for Power Plants is a powerful, user-friendly tool for estimating, tracking, and reporting releases of chemicals—primarily trace substances—from fossil-fired steam electric plants. The spreadsheet-like tool has been applied by numerous energy companies to increase the efficiency and reduce the costs of Toxics Release Inventory (TRI)-related analyses while enhancing compliance ...

2013-04-10T23:59:59.000Z

28

Hanford Waste Vitrification Plant hydrogen generation  

DOE Green Energy (OSTI)

The most promising method for the disposal of highly radioactive nuclear wastes is a vitrification process in which the wastes are incorporated into borosilicate glass logs, the logs are sealed into welded stainless steel canisters, and the canisters are buried in suitably protected burial sites for disposal. The purpose of the research supported by the Hanford Waste Vitrification Plant (HWVP) project of the Department of Energy through Battelle Pacific Northwest Laboratory (PNL) and summarized in this report was to gain a basic understanding of the hydrogen generation process and to predict the rate and amount of hydrogen generation during the treatment of HWVP feed simulants with formic acid. The objectives of the study were to determine the key feed components and process variables which enhance or inhibit the.production of hydrogen. Information on the kinetics and stoichiometry of relevant formic acid reactions were sought to provide a basis for viable mechanistic proposals. The chemical reactions were characterized through the production and consumption of the key gaseous products such as H{sub 2}. CO{sub 2}, N{sub 2}0, NO, and NH{sub 3}. For this mason this research program relied heavily on analyses of the gases produced and consumed during reactions of the HWVP feed simulants with formic acid under various conditions. Such analyses, used gas chromatographic equipment and expertise at the University of Georgia for the separation and determination of H{sub 2}, CO, CO{sub 2}, N{sub 2}, N{sub 2}O and NO.

King, R.B.; King, A.D. Jr.; Bhattacharyya, N.K. [and others

1996-02-01T23:59:59.000Z

29

SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT  

E-Print Network (OSTI)

Generating Plant. The enclosed report documents the inspection findings which were discussed on February 22, 2001, with you and other members of your staff. This inspection examined activities conducted under your license as they relate to safety and compliance with the Commission’s rules and regulations and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. Based on the results of this inspection, the inspectors identified two issues of very low safety significance (Green). One of these issues was determined to involve a violation of NRC requirements. However, because of its very low safety significance and because it has been entered into your corrective action program, the NRC is treating the issue as a non-cited violation, in accordance with Section VI.A.1 of the NRC’s Enforcement Policy. If you deny the non-cited violation, you should provide a response with the basis for your denial, within 30 days of the date of this inspection report, to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington DC 20555-0001; with copies to the Regional Administrator,

Dear Mr. Sorensen; Roger D. Lanksbury

2001-01-01T23:59:59.000Z

30

THE NEXT GENERATION NUCLEAR PLANT GRAPHITE PROGRAM  

Science Conference Proceedings (OSTI)

Developing new nuclear grades of graphite used in the core of a High Temperature Gas-cooled Reactor (HTGR) is one of the critical development activities being pursued within the Next Generation Nuclear Plant (NGNP) program. Graphite’s thermal stability (in an inert gas environment), high compressive strength, fabricability, and cost effective price make it an ideal core structural material for the HTGR reactor design. While the general characteristics necessary for producing nuclear grade graphite are understood, historical “nuclear” grades no longer exist. New grades must be fabricated, characterized, and irradiated to demonstrate that current grades of graphite exhibit acceptable non-irradiated and irradiated properties upon which the thermo-mechanical design of the structural graphite in NGNP is based. The NGNP graphite R&D program has selected a handful of commercially available types for research and development activities necessary to qualify this nuclear grade graphite for use within the NGNP reactor. These activities fall within five primary areas; 1) material property characterization, 2) irradiated material property characterization, 3) modeling, and 4) ASTM test development, and 5) ASME code development efforts. Individual research and development activities within each area are being pursued with the ultimate goal of obtaining a commercial operating license for the nuclear graphite from the US NRC.

William E. Windes; Timothy D. Burchell; Robert L. Bratton

2008-09-01T23:59:59.000Z

31

How much electricity does a typical nuclear power plant generate ...  

U.S. Energy Information Administration (EIA)

How much electricity does a typical nuclear power plant generate? ... tariff, and demand charge data? How is electricity used in U.S. homes?

32

North Brawley Power Plant Placed in Service; Currently Generating...  

Open Energy Info (EERE)

Not Provided DOI Not Provided Check for DOI availability: http:crossref.org Online Internet link for North Brawley Power Plant Placed in Service; Currently Generating 17 MW;...

33

EIA - Updated Capital Cost Estimates for Electricity Generation Plants  

U.S. Energy Information Administration (EIA)

... by the costs has changed significantly. Prior estimates were for a highly efficient plant employing gasification and a combined cycle generator; the new ...

34

How much electricity does a typical nuclear power plant generate ...  

U.S. Energy Information Administration (EIA)

... (kWh). There were 65 nuclear power plants with 104 operating nuclear reactors that generated a total of 790 billion kilowatt-hours (kWh), ...

35

NETL: News Release - Studies Begin on Next Generation of Mid...  

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

of the next generation of mid-size electric power generating gas turbines. MORE INFO Gas Turbine R&D Program. The Energy Department has selected: Pratt & Whitney, East...

36

Distributed Generation in Buildings (released in AEO2005)  

Reports and Publications (EIA)

Currently, distributed generation provides a very small share of residential and commercial electricity requirements in the United States. The AEO2005 reference case projects a significant increase in electricity generation in the buildings sector, but distributed generation is expected to remain a small contributor to the sectors energy needs. Although the advent of higher energy prices or more rapid improvement in technology could increase the use of distributed generation relative to the reference case projection, the vast majority of electricity used in buildings is projected to continue to be purchased from the grid.

Information Center

2008-09-24T23:59:59.000Z

37

Next generation geothermal power plants. Draft final report  

DOE Green Energy (OSTI)

The goal of this project is to develop concepts for the next generation geothermal power plant(s) (NGGPP). This plant, compared to existing plants, will generate power for a lower levelized cost and will be more competitive with fossil fuel fired power plants. The NGGPP will utilize geothermal resources efficiently and will be equipped with contingencies to mitigate the risk of reservoir performance. The NGGPP design will attempt to minimize emission of pollutants and consumption of surface water and/or geothermal fluids for cooling service.

Brugman, John; Hattar, John; Nichols, Kenneth; Esaki, Yuri

1994-12-01T23:59:59.000Z

38

Nuclear Power Plant Emergency Diesel Generator Tanks 1  

E-Print Network (OSTI)

Nuclear power provides about 20 % of the total electricity generated in the United States. In 2005, this was about 782 Billion kWh of the total electricity generation (EIA 2006). 2 As with fossil-fueled electricity generating plants, electricity in a nuclear power plant is produced by heated steam that drives a turbine generator. In a nuclear power plant, however, nuclear fission reactions in the core produce heat that is absorbed by a liquid that flows through the system and is converted to steam. Nuclear power plants are highly efficient and have become more so over the last 25 years. Operational efficiency (also referred to as plant performance or electricity production) can be measured by the capacity factor. The capacity factor is the ratio of the actual amount of electricity generated to the maximum possible amount that could be generated in a given period of time – usually a year. Today, nuclear power plants operate at an average 90 % capacity factor (compared to 56 % in 1980) (EIA 2006a). Thus, although nuclear generating capacity has remained roughly constant since 1990, at about 99 gigawatts (or about 10 % of the total U.S. electric generating capacity), the amount of electricity produced has increased 33 % since that time because of increased capacity utilization. Nuclear plants have the highest capacity factors of

unknown authors

2006-01-01T23:59:59.000Z

39

Plant monitoring techniques and second generation designs  

SciTech Connect

Chemical and instrumental monitoring techniques suitable for geothermal use are described in a manner to relate them to plant operational problems and downtime avoidance. The use of these techniques permits the detection of scaling, the onset of scaling, corrosion loss, current corrosion rates and incipient heat exchanger failure. Conceptual advances are noted which simplify the research techniques to approaches that should be usable even in some low-capital well-head type power plants. 10 refs., 8 figs.

Kindle, C.H.; Shannon, D.W.; Robertus, R.J.; Pierce, D.D.; Sullivan, R.G.

1985-03-01T23:59:59.000Z

40

Post-Secondary Curricula for Next-Generation Biofuels Released November 22, 20111 Request for Proposals  

E-Print Network (OSTI)

Post-Secondary Curricula for Next-Generation Biofuels Released November 22, 20111 Request for Proposals Post-Secondary Curricula for Next-Generation Biofuels PROPOSAL SUBMISSION DEADLINE: February 6 for curricula development in the area(s) of `next-generation' biofuels (e.g. new or emerging technologies

Farritor, Shane

Note: This page contains sample records for the topic "generating plants release" 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

Next Generation Nuclear Plant Project Evaluation of Siting a HTGR Co-generation Plant on an Operating Commercial Nuclear Power Plant Site  

Science Conference Proceedings (OSTI)

This paper summarizes an evaluation by the Idaho National Laboratory (INL) Next Generation Nuclear Plant (NGNP) Project of siting a High Temperature Gas-cooled Reactor (HTGR) plant on an existing nuclear plant site that is located in an area of significant industrial activity. This is a co-generation application in which the HTGR Plant will be supplying steam and electricity to one or more of the nearby industrial plants.

L.E. Demick

2011-10-01T23:59:59.000Z

42

NETL: News Release - Abraham Announces Pollution-Free Power Plant...  

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

February 27, 2003 Abraham Announces Pollution-Free Power Plant of the Future 1 Billion 'Living Prototype' to Showcase Cutting-Edge Technologies to Advance President's Climate...

43

The Next Generation Nuclear Plant (NGNP) Project  

DOE Green Energy (OSTI)

The Next Generation Nuclear Power (NGNP) Project will demonstrate emissions-free nuclearassisted electricity and hydrogen production by 2015. The NGNP reactor will be a helium-cooled, graphite moderated, thermal neutron spectrum reactor with a design goal outlet temperature of 1000 C or higher. The reactor thermal power and core configuration will be designed to assure passive decay heat removal without fuel damage during hypothetical accidents. The fuel cycle will be a once-through very high burnup low-enriched uranium fuel cycle. This paper provides a description of the project to build the NGNP at the Idaho National Engineering and Environmental Laboratory (INEEL). The NGNP Project includes an overall reactor design activity and four major supporting activities: materials selection and qualification, NRC licensing and regulatory support, fuel development and qualification, and the hydrogen production plant. Each of these activities is discussed in the paper. All the reactor design and construction activities will be managed under the DOE’s project management system as outlined in DOE Order 413.3. The key elements of the overall project management system discussed in this paper include the client and project management organization relationship, critical decisions (CDs), acquisition strategy, and the project logic and timeline. The major activities associated with the materials program include development of a plan for managing the selection and qualification of all component materials required for the NGNP; identification of specific materials alternatives for each system component; evaluation of the needed testing, code work, and analysis required to qualify each identified material; preliminary selection of component materials; irradiation of needed sample materials; physical, mechanical, and chemical testing of unirradiated and irradiated materials; and documentation of final materials selections. The NGNP will be licensed by the NRC under 10 CFR 50 or 10 CFR 52, for the purpose of demonstrating the suitability of high-temperature gas-cooled reactors for commercial electric power and hydrogen production. Products that will support the licensing of the NGNP include the environmental impact statement, the preliminary safety analysis report, the NRC construction permit, the final safety analysis report, and the NRC operating license. The fuel development and qualification program consists of five elements: development of improved fuel manufacturing technologies, fuel and materials irradiations, safety testing and post-irradiation examinations, fuel performance modeling, and fission product transport and source term modeling. Two basic approaches will be explored for using the heat from the high-temperature helium coolant to produce hydrogen. The first technology of interest is the thermochemical splitting of water into hydrogen and oxygen. The most promising processes for thermochemical splitting of water are sulfur-based and include the sulfur-iodine, hybrid sulfur-electrolysis, and sulfur-bromine processes. The second technology of interest is thermally assisted electrolysis of water. The efficiency of this process can be substantially improved by heating the water to high-temperature steam before applying electrolysis.

F. H. Southworth; P. E. MacDonald

2003-11-01T23:59:59.000Z

44

Electricity Plant Cost Uncertainties (released in AEO2009)  

Reports and Publications (EIA)

Construction costs for new power plants have increased at an extraordinary rate over the past several years. One study, published in mid-2008, reported that construction costs had more than doubled since 2000, with most of the increase occurring since 2005. Construction costs have increased for plants of all types, including coal, nuclear, natural gas, and wind.

Information Center

2009-03-31T23:59:59.000Z

45

Designing plant layouts with toxic releases based on wind statistics  

Science Conference Proceedings (OSTI)

A model to optimize the process plant layout problem is formulated in this paper. The model includes statistical information related to the wind in the site where the plant will be installed. This information is typically collected and stored in databases ... Keywords: Monte Carlo method, dispersion models, layout, uncertainty, wind effect

Richart Vázquez-Román; Jin-Han Lee; Seungho Jung; M. Sam Mannan

2008-08-01T23:59:59.000Z

46

Innovative Design of New Geothermal Generating Plants  

SciTech Connect

This very significant and useful report assessed state-of-the-art geothermal technologies. The findings presented in this report are the result of site visits and interviews with plant owners and operators, representatives of major financial institutions, utilities involved with geothermal power purchases and/or wheeling. Information so obtained was supported by literature research and data supplied by engineering firms who have been involved with designing and/or construction of a majority of the plants visited. The interviews were conducted by representatives of the Bonneville Power Administration, the Washington State Energy Office, and the Oregon Department of Energy during the period 1986-1989. [DJE-2005

Bloomquist, R. Gordon; Geyer, John D.; Sifford, B. Alexander III

1989-07-01T23:59:59.000Z

47

NETL: News Release - Projects Selected to Study Coal Plant Particulate  

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

5, 2004 5, 2004 Projects Selected to Study Coal Plant Particulate Matter, Human Health PITTSBURGH, PA - The Department of Energy has selected three projects to help determine whether fine particulates emitted from coal-fired power plants affect human health, and which components of the particulates may be most problematic. Past studies have established that particulate matter smaller than 2.5 microns in diameter from all sources does affect human health, but there is scant information to provide a link between PM2.5 emitted specifically from coal plants and cardiac or respiratory health problems in humans. PM2.5 refers to particles-invisible to the eye-no more than 1/30th of the width of a human hair Coal plants emit only small quantities of "primary" PM2.5 (e.g., fly ash) because all plants have high-efficiency particulate-collection devices. However, coal plants are responsible for a great deal of "secondary" PM2.5, which forms in the atmosphere from emissions of sulfur dioxide (SO2) and nitrogen oxides (NOx). Data collected in the new studies will be used to help design standards reviews and to devise strategies for controlling power plant emissions of PM2.5, SO2, and NOx.

48

Effects of Globally Waste Disturbing Activities on Gas Generation, Retention, and Release in Hanford Waste Tanks  

SciTech Connect

Various operations are authorized in Hanford single- and double-shell tanks that disturb all or a large fraction of the waste. These globally waste-disturbing activities have the potential to release a large fraction of the retained flammable gas and to affect future gas generation, retention, and release behavior. This report presents analyses of the expected flammable gas release mechanisms and the potential release rates and volumes resulting from these activities. The background of the flammable gas safety issue at Hanford is summarized, as is the current understanding of gas generation, retention, and release phenomena. Considerations for gas monitoring and assessment of the potential for changes in tank classification and steady-state flammability are given.

Stewart, Charles W.; Fountain, Matthew S.; Huckaby, James L.; Mahoney, Lenna A.; Meyer, Perry A.; Wells, Beric E.

2005-08-02T23:59:59.000Z

49

NETL: News Release - Making Tomorrow's Coal-Fired Power Plants...  

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

May 4, 2001 Making Tomorrow's Coal-Fired Power Plants Cleaner and More Efficient August 21, 2001 DOE Selects 5 New Research Projects to Improve Combustors, Reduce Pollutants, and...

50

Table 11b. Coal Prices to Electric Generating Plants, Projected...  

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

b. Coal Prices to Electric Generating Plants, Projected vs. Actual Projected Price in Nominal Dollars (nominal dollars per million Btu) 1993 1994 1995 1996 1997 1998 1999 2000 2001...

51

Industry Participation Sought for Design of Next Generation Nuclear Plant |  

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

Industry Participation Sought for Design of Next Generation Nuclear Industry Participation Sought for Design of Next Generation Nuclear Plant Industry Participation Sought for Design of Next Generation Nuclear Plant June 29, 2006 - 2:41pm Addthis Gen IV Reactor Capable of Producing Electricity and/or Hydrogen WASHINGTON, DC - The U.S. Department of Energy (DOE) is seeking expressions of interest from prospective industry teams interested in participating in the development and conceptual design for the Next Generation Nuclear Plant (NGNP), a very high temperature gas-cooled nuclear reactor prototype with the capability to produce process heat, electricity and/or hydrogen. The very high temperature reactor is based on research and development activities supported by DOE's Generation IV nuclear energy systems initiative.

52

Next Generation Nuclear Plant Materials Research and Development Program Plan  

SciTech Connect

The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Project is envisioned to demonstrate the following: (1) A full-scale prototype VHTR by about 2021; (2) High-temperature Brayton Cycle electric power production at full scale with a focus on economic performance; (3) Nuclear-assisted production of hydrogen (with about 10% of the heat) with a focus on economic performance; and (4) By test, the exceptional safety capabilities of the advanced gas-cooled reactors. Further, the NGNP program will: (1) Obtain a Nuclear Regulatory Commission (NRC) License to construct and operate the NGNP, this process will provide a basis for future performance based, risk-informed licensing; and (2) Support the development, testing, and prototyping of hydrogen infrastructures. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. The NGNP Materials R&D Program includes the following elements: (1) Developing a specific approach, program plan and other project management tools for managing the R&D program elements; (2) Developing a specific work package for the R&D activities to be performed during each government fiscal year; (3) Reporting the status and progress of the work based on committed deliverables and milestones; (4) Developing collaboration in areas of materials R&D of benefit to the NGNP with countries that are a part of the Generation IV International Forum; and (5) Ensuring that the R&D work performed in support of the materials program is in conformance with established Quality Assurance and procurement requirements. The objective of the NGNP Materials R&D Program is to provide the essential materials R&D needed to support the design and licensing of the reactor and balance of plant, excluding the hydrogen plant. The materials R&D program is being initiated prior to the design effort to ensure that materials R&D activities are initiated early enough to support the design process and support the Project Integrator. The thermal, environmental, and service life conditions of the NGNP will make selection and qualification of some high-temperature materials a significant challenge; thus, new materials and approaches may be required.

G.O. Hayner; R.L. Bratton; R.N. Wright

2005-09-01T23:59:59.000Z

53

U.S. Nuclear Power Plants: Continued Life or Replacement After 60? (released in AEO2010)  

Reports and Publications (EIA)

Nuclear power plants generate approximately 20 percent of U.S. electricity, and the plants in operation today are often seen as attractive assets in the current environment of uncertainty about future fossil fuel prices, high construction costs for new power plants (particularly nuclear plants), and the potential enactment of GHG regulations. Existing nuclear power plants have low fuel costs and relatively high power output. However, there is uncertainty about how long they will be allowed to continue operating.

Information Center

2010-05-11T23:59:59.000Z

54

Next Generation Nuclear Plant Research and Development Program Plan  

DOE Green Energy (OSTI)

The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: (1) Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission (2) Demonstrate safe and economical nuclear-assisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: (1) High temperature gas reactor fuels behavior; (2) High temperature materials qualification; (3) Design methods development and validation; (4) Hydrogen production technologies; and (5) Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented in Section 4. The DOE-funded hydrogen production [DOE 2004] and energy conversion technologies programs are described elsewhere.

None

2005-01-01T23:59:59.000Z

55

Next Generation Nuclear Plant Research and Development Program Plan  

DOE Green Energy (OSTI)

The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The objectives of the NGNP Project are to: Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission Demonstrate safe and economical nuclearassisted production of hydrogen and electricity. The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: High temperature gas reactor fuels behavior High temperature materials qualification Design methods development and validation Hydrogen production technologies Energy conversion. The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented in Section 4. The DOE-funded hydrogen production [DOE 2004] and energy conversion technologies programs are described elsewhere.

P. E. MacDonald

2005-01-01T23:59:59.000Z

56

Springerville Generating Station Solar System Solar Power Plant | Open  

Open Energy Info (EERE)

Springerville Generating Station Solar System Solar Power Plant Springerville Generating Station Solar System Solar Power Plant Jump to: navigation, search Name Springerville Generating Station Solar System Solar Power Plant Facility Springerville Generating Station Solar System Sector Solar Facility Type Photovoltaic Developer Tucson Electric Power Location Springerville, Arizona Coordinates 34.1333799°, -109.2859196° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":34.1333799,"lon":-109.2859196,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

57

NETL: News Release - Energy Department Awards Project in Power Plant  

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

24, 2006 24, 2006 Energy Department Awards Project in Power Plant Improvement Initiative Technology Focuses on Nation's 500 Small Coal-Burning Energy Producers WASHINGTON, DC - The U.S. Department of Energy today awarded a contract to CONSOL Energy Inc., a major coal producer, as part of an effort under DOE's Power Plant Improvement Initiative to reduce the ever-increasing demands on U.S. electricity supplies. MORE INFO Read more about the eight PPII project selections made in October 2001 "This award represents yet another step forward in advancing clean coal technologies for the future," said Assistant Secretary for Fossil Energy Jeffrey Jarrett. "With more than half of America's electricity coming from coal, this resource is vital to our nation's energy security. The success

58

Approach to Assessing Fuel Flexibility for Improved Generating Plant Profitability  

Science Conference Proceedings (OSTI)

This report presents the results of an EPRI study of fuel flexibility, a strategy that can increase a power plant's financial performance by matching choices regarding the type of coal burned at a generating station to fluctuations in the market price of electricity. The report presents detailed analytical information as well as conclusions drawn from the study, and includes a checklist utilities can use in evaluating the potential for a plant to benefit by adopting fuel flexibility.

1999-08-24T23:59:59.000Z

59

Turbine-Generator Topics for Plant Engineers: Residual Magnetism  

Science Conference Proceedings (OSTI)

The undesirable magnetization of components of rotating equipment used in the generation of electric power is a problem that has been recognized for many years; but wide understanding of the origins, detection techniques, remediation, and avoidance principles of residual magnetization has been lacking. As part of the series Turbine-Generator Topics for Plant Engineers, EPRI commissioned this report with the purpose of providing engineers active in the operation and maintenance of power ...

2013-08-23T23:59:59.000Z

60

Program on Technology Innovation: The Next Generation Nuclear Plant  

Science Conference Proceedings (OSTI)

This Technology Update documents the Next Generation Nuclear Plant (NGNP) project, which will demonstrate the design, licensing, construction, and operation of a new nuclear energy source using high-temperature gas-cooled reactor (HTGR) technology. This new non-emitting energy source is applicable to a broad range of uses, from generating electricity to providing high-temperature industrial process heat to producing hydrogen. The NGNP project is sponsored as part of the Energy Policy Act of 2005 and envi...

2008-12-15T23:59:59.000Z

Note: This page contains sample records for the topic "generating plants release" 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

Polish plant beats the odds to become model EU generator  

SciTech Connect

Once a Soviet satellite, Poland is now transforming into a thoroughly modern nation. To support its growing economy, this recent European Union member country is modernizing its power industry. Exemplifying the advances in the Polish electricity generation market is the 460 MW Patnow II power plant - the largest, most efficient (supercritical cycle) and environmentally cleanest lignite-fired unit in the country. 3 photos.

Neville, A.

2009-03-15T23:59:59.000Z

62

EIS-0476: Vogtle Electric Generating Plant, Units 3 and 4  

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

This EIS evaluates the environmental impacts of construction and startup of the proposed Units 3 and 4 at the Vogtle Electric Generating Plant in Burke County, Georgia. DOE adopted two Nuclear Regulatory Commission EISs associated with this project (i.e., NUREG-1872, issued 8/2008, and NUREG-1947, issued 3/2011).

63

Power Plant Emission Reductions Using a Generation Performance Standard  

Gasoline and Diesel Fuel Update (EIA)

Power Plant Emission Reductions Power Plant Emission Reductions Using a Generation Performance Standard by J. Alan Beamon, Tom Leckey, and Laura Martin There are many policy instruments available for reducing power plant emissions, and the choice of a policy will affect compliance decisions, costs, and prices faced by consumers. In a previous analysis, the Energy Information Administration analyzed the impacts of power sector caps on nitrogen oxides (NO x ), sulfur dioxide (SO 2 ), and carbon dioxide (CO 2 ) emissions, assuming a policy instru- ment patterned after the SO 2 allowance program created in the Clean Air Act Amendments of 1990. 1 This report compares the results of that work with the results of an analysis that assumes the use of a dynamic generation performance standard (GPS) as an instrument for reducing CO 2 emissions. 2 In general, the results of the two analyses are similar: to reduce

64

IMPROVEMENTS IN OR RELATING TO STEAM GENERATING PLANT  

SciTech Connect

A steam generating plant for marine vessels includes a steam superheater (nuclear reactor, perhaps) from which steam is ducted to the point of use (heat exchanger, etc.). A steam generator receiving the condensed steam from the point of use uses steam from the superheater to evaporate the condensate. The superheated steam used in the evaporation is compressed by a turbo-compressor and directed into the superheater. The condensate evaporated in the generator is used to drive the turbo-compressor. (D.C.W.)

Kendon, M.H.

1963-07-03T23:59:59.000Z

65

Coal-fired power plants the next generation  

Science Conference Proceedings (OSTI)

Coal is today a very important source of energy and the resources are sufficient for a long period. To keep power generation with coal up-to-date in view of minimizing the pollution (especially the CO{sub 2}) and of better economy, we will have introduce new plant technologies. After a general overview three of these are presented and compared with the state-of-the-art PCF technology, in respect to plant efficiency, environmental impact, investment cost, cost of electricity, and unit size.

Schemenau, W.; Schoedel, J. (ABB Kraftwerke AG, Mannheim (DE))

1990-01-01T23:59:59.000Z

66

Next Generation Nuclear Plant Materials Research and Development Program Plan  

DOE Green Energy (OSTI)

The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years.

G. O. Hayner; E.L. Shaber

2004-09-01T23:59:59.000Z

67

AVESTAR Center for Operational Excellence of Electricity Generation Plants  

Science Conference Proceedings (OSTI)

To address industry challenges in attaining operational excellence for electricity generation plants, the U.S. Department of Energy’s (DOE) National Energy Technology Laboratory (NETL) has launched a world-class facility for Advanced Virtual Energy Simulation Training and Research (AVESTARTM). This presentation will highlight the AVESTARTM Center simulators, facilities, and comprehensive training, education, and research programs focused on the operation and control of high-efficiency, near-zero-emission electricity generation plants. The AVESTAR Center brings together state-of-the-art, real-time, high-fidelity dynamic simulators with full-scope operator training systems (OTSs) and 3D virtual immersive training systems (ITSs) into an integrated energy plant and control room environment. AVESTAR’s initial offering combines--for the first time--a “gasification with CO2 capture” process simulator with a “combined-cycle” power simulator together in a single OTS/ITS solution for an integrated gasification combined cycle (IGCC) power plant with carbon dioxide (CO2) capture. IGCC systems are an attractive technology option for power generation, especially when capturing and storing CO2 is necessary to satisfy emission targets. The AVESTAR training program offers a variety of courses that merge classroom learning, simulator-based OTS learning in a control-room operations environment, and immersive learning in the interactive 3D virtual plant environment or ITS. All of the courses introduce trainees to base-load plant operation, control, startups, and shutdowns. Advanced courses require participants to become familiar with coordinated control, fuel switching, power-demand load shedding, and load following, as well as to problem solve equipment and process malfunctions. Designed to ensure work force development, training is offered for control room and plant field operators, as well as engineers and managers. Such comprehensive simulator-based instruction allows for realistic training without compromising worker, equipment, and environmental safety. It also better prepares operators and engineers to manage the plant closer to economic constraints while minimizing or avoiding the impact of any potentially harmful, wasteful, or inefficient events. The AVESTAR Center is also used to augment graduate and undergraduate engineering education in the areas of process simulation, dynamics, control, and safety. Students and researchers gain hands-on simulator-based training experience and learn how the commercial-scale power plants respond dynamically to changes in manipulated inputs, such as coal feed flow rate and power demand. Students also analyze how the regulatory control system impacts power plant performance and stability. In addition, students practice start-up, shutdown, and malfunction scenarios. The 3D virtual ITSs are used for plant familiarization, walk-through, equipment animations, and safety scenarios. To further leverage the AVESTAR facilities and simulators, NETL and its university partners are pursuing an innovative and collaborative R&D program. In the area of process control, AVESTAR researchers are developing enhanced strategies for regulatory control and coordinated plant-wide control, including gasifier and gas turbine lead, as well as advanced process control using model predictive control (MPC) techniques. Other AVESTAR R&D focus areas include high-fidelity equipment modeling using partial differential equations, dynamic reduced order modeling, optimal sensor placement, 3D virtual plant simulation, and modern grid. NETL and its partners plan to continue building the AVESTAR portfolio of dynamic simulators, immersive training systems, and advanced research capabilities to satisfy industry’s growing need for training and experience with the operation and control of clean energy plants. Future dynamic simulators under development include natural gas combined cycle (NGCC) and supercritical pulverized coal (SCPC) plants with post-combustion CO2 capture. These dynamic simulators are targeted for us

Zitney, Stephen

2012-08-29T23:59:59.000Z

68

Updated Capital Cost Estimates for Utility Scale Electricity Generating Plants  

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

Updated Capital Cost Estimates Updated Capital Cost Estimates for Utility Scale Electricity Generating Plants April 2013 Independent Statistics & Analysis www.eia.gov U.S. Department of Energy Washington, DC 20585 U.S. Energy Information Administration | Updated Capital Cost Estimates for Utility Scale Electricity Generating Plants ii This report was prepared by the U.S. Energy Information Administration (EIA), the statistical and analytical agency within the U.S. Department of Energy. By law, EIA's data, analyses, and forecasts are independent of approval by any other officer or employee of the United States Government. The views in this report therefore should not be construed as representing those of the Department of Energy or other Federal agencies.

69

Generator loss of field study for AEP's Rockport plant  

SciTech Connect

Generator loss of field (LOF) conditions occur rarely. However, when LOF and consequent out-of-step conditions occur, the resultant high currents and pulsating torques can damage the turbine-generator under some conditions. Also the electrical system near the disturbance can be impacted by abnormal levels and cyclic swings of power, VArs, and voltages. This article describes the computed performance of AEP's remotely-located 2600 MW Rockport plant after simulated LOF disturbances to one of its 1300 MW cross-compound units. It shows the transmission facilities near Rockport, as well as nearby plants. Because of this topology, LOF on one unit can significantly impact the adjacent Rockport unit, and the reactive power drain could impose a heavy burden on transmission, impacting local voltages.

Rana, R.D.; Schulz, R.P.; Heyeck, M.; Boyer, T.R. Jr. (American Electric Power, Inc., Canton, OH (USA))

1990-04-01T23:59:59.000Z

70

NEXT GENERATION NUCLEAR PLANT LICENSING BASIS EVENT SELECTION WHITE PAPER  

SciTech Connect

The Next Generation Nuclear Plant (NGNP) will be a licensed commercial high temperature gas-cooled reactor (HTGR) plant capable of producing the electricity and high temperature process heat for industrial markets supporting a range of end-user applications. The NGNP Project has adopted the 10 CFR 52 Combined License (COL) application process, as recommended in the Report to Congress, dated August 2008, as the foundation for the NGNP licensing strategy. NRC licensing of the NGNP plant utilizing this process will demonstrate the efficacy of licensing future HTGRs for commercial industrial applications. This white paper is one in a series of submittals that will address key generic issues of the COL priority licensing topics as part of the process for establishing HTGR regulatory requirements.

Mark Holbrook

2010-09-01T23:59:59.000Z

71

LARK-TRIPP -- A Toxic Release Inventory Estimation Tool for Power Plants Version 1.0  

Science Conference Proceedings (OSTI)

LARK-TRIPP is software developed to estimate and keep records on land and air releases, primarily trace substance emissions from fuel steam electric plants. Emissions can be tracked for individual plants containing a single unit or multiple units. Data are gathered by single unit/single year, but output can be combinations of current unit/year or all units/years. LARK-TRIPP enables the user to calculate reportable quantities of elements based on coal or ash data. A record of all input data can then be st...

1999-04-09T23:59:59.000Z

72

NETL: News Release - DOE Takes 2nd Step Toward Ultra-Clean Energy Plant;  

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

August 3, 2000 August 3, 2000 DOE Takes 2nd Step Toward Ultra-Clean Energy Plant; Selects Seven More Projects to Join Vision 21 Program The U.S. Department of Energy today added more of the technological "building blocks" to its Vision 21 program - an effort the agency expects to lead to a nearly pollution-free energy plant by the next decade. A Possible Concept for Tomorrow's Vision 21 Plant It's not your father's power plant. The Vision 21 pollution-free energy plant may look significantly different than a traditional power plant - as this artist's concept shows. "We are building the foundation for a new generation of energy facilities capable of efficiently using our most abundant traditional fuels while virtually eliminating environmental concerns," said Secretary of Energy

73

IMPROVEMENTS IN STEAM GENERATING PLANT AND AN IMPROVED METHOD OF GENERATING STEAM  

SciTech Connect

A steam generating plant, designed for heat transfer from a liquid metal (potassium, sodium, or their alloy) with reduced danger of explosion, is based on the fact that, if steam (especially superheated) rather than water contacts the liquid metal, the risk of explosion is much reduced. In this plant steam is superheated by heat transfer from liquid metal, the steam bsing generated by heat transfer between the superheated steam and water. Diagrams are given for the plant, which comprises a series of heat exchangers in which steam is superheated; part of the superheated steam is recycled to convert water into steam. Apart from the danger of a steam--liquid metal contact, the main danger is that the superheated steam might cool, coming to the saturated condition; this danger can be averted by setting up mceans for detecting low steam temperatures. (D.L.C.)

Zoller, R.E.

1960-09-01T23:59:59.000Z

74

Effect of pressure on second-generation pressurized fluidized bed combustion plants  

Science Conference Proceedings (OSTI)

In the search for a more efficient, less costly, and more environmentally responsible method for generating electrical power from coal, research and development has turned to advanced pressurized fluidized bed combustion (PFBC) and coal gasification technologies. A logical extension of this work is the second- generation PFBC plant, which incorporates key components of each of these technologies. In this new type of plant, coal devolatilized/carbonized before it is injected into the PFB combustor bed, and the low Btu fuel gas produced by this process is burned in a gas turbine topping combustor. By integrating coal carbonization with PFB coal/char combustion, gas turbine inlet temperatures higher than 1149{degrees}C (2100{degrees}F) can be achieved. The carbonizer, PFB combustor, and particulate-capturing hot gas cleanup systems operate at 871{degrees}C (1600{degrees}F), permitting sulfur capture by lime-based sorbents and minimizing the release of coal contaminants to the gases. This paper presents the performance and economics of this new type of plant and provides a brief overview of the pilot plant test programs being conducted to support its development.

Robertson, A. [Foster Wheeler Development Corp., Livingston, NJ (United States); Bonk, D.L. [USDOE Morgantown Energy Technology Center, WV (United States)

1993-06-01T23:59:59.000Z

75

Nuclear plant design and modification guidelines for PWR steam generator reliability  

Science Conference Proceedings (OSTI)

Operating experience gathered from PWR plant operation during the 1960's and 1970's has been incorporated into a series of design guidelines for secondary plant systems and steam generators. Specific guidelines included in this volume are: plant design for PWR steam generator inspection and nondestructive testing, revision 1; guidelines for design of steam generator blowdown systems, revision 1; plant design guidelines for layup and cleanup of steam, feedwater, and condensate systems, revision 1; design guidelines for plant secondary systems, revision 1 and plant design for steam generator replaceability, revision 1. The guidelines are intended to address those aspects of new plant design which will minimize corrosion damage to steam generators by controlling impurity ingress, facilitate steam generator nondestructive testing and provide for eventual replacement of steam generator if necessary. The guidelines, last revised in 1986, are primarily applicable to new plant construction, however, some of the guidelines may also be applicable to major backfits to existing plants.

Not Available

1991-09-01T23:59:59.000Z

76

Next Generation Nuclear Plant Resilient Control System Functional Analysis  

SciTech Connect

Control Systems and their associated instrumentation must meet reliability, availability, maintainability, and resiliency criteria in order for high temperature gas-cooled reactors (HTGRs) to be economically competitive. Research, perhaps requiring several years, may be needed to develop control systems to support plant availability and resiliency. This report functionally analyzes the gaps between traditional and resilient control systems as applicable to HTGRs, which includes the Next Generation Nuclear Plant; defines resilient controls; assesses the current state of both traditional and resilient control systems; and documents the functional gaps existing between these two controls approaches as applicable to HTGRs. This report supports the development of an overall strategy for applying resilient controls to HTGRs by showing that control systems with adequate levels of resilience perform at higher levels, respond more quickly to disturbances, increase operational efficiency, and increase public protection.

Lynne M. Stevens

2010-07-01T23:59:59.000Z

77

released  

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

Arctic Arctic algae, a cereal crop whose genetic code is nearly equivalent to sequencing two full human genomes, and microbial communities in deep- sea hydrothermal vents are among the 35 projects selected by the U.S. Department of Energy (DOE) Joint Genome Institute (JGI) for its 2011 Community Sequencing Program (CSP) to be character- ized for bioenergy and environ- mental applications. Enabling scientists from universities and national labo- ratories around the world to probe the hidden world of microbes and plants to meet the DOE missions of bioenergy, carbon cycling and biogeo- chemistry, this year's CSP portfolio is composed mostly of large-scale projects, which DOE JGI Director Eddy Rubin said was in keeping with the facility's mission of large-scale genomics and analysis. "Advances in sequencing technologies are really chang- ing the landscape and have dramatically

78

Next Generation Nuclear Plant Materials Selection and Qualification Program Plan  

SciTech Connect

The U.S. Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design is a graphite-moderated, helium-cooled, prismatic or pebble bed thermal neutron spectrum reactor with an average reactor outlet temperature of at least 1000 C. The NGNP will use very high burn up, lowenriched uranium, TRISO-Coated fuel in a once-through fuel cycle. The design service life of the NGNP is 60 years.

R. Doug Hamelin; G. O. Hayner

2004-11-01T23:59:59.000Z

79

NETL 2007 News Releases  

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

7 News Releases 7 News Releases News Releases issued in: 2011 | 2010 | 2009 | 2008 | 2007 | 2006 | 2005 | 2004 | 2003 | 2002 | 2001 | 2000 December 18, 2007 Energy Department Awards $66.7 Million for Large-Scale Carbon Sequestration Project DOE awarded $66.7 million to the Midwest Geological Sequestration Consortium for the Department's fourth large scale carbon sequestration project. December 06, 2007 DOE Estimates Future Water Needs for Thermoelectric Power Plants The Office of Fossil Energy's National Energy Technology Laboratory has released a 2007 update to its groundbreaking study, "Estimating Freshwater Needs to Meet Future Thermoelectric Generation Requirements." December 05, 2007 Tax Credit Program Promotes Advanced Coal Power Generation and Gasification Technologies

80

Hydrogen Production from the Next Generation Nuclear Plant  

DOE Green Energy (OSTI)

The Next Generation Nuclear Plant (NGNP) is a high temperature gas-cooled reactor that will be capable of producing hydrogen, electricity and/or high temperature process heat for industrial use. The project has initiated the conceptual design phase and when completed will demonstrate the viability of hydrogen generation using nuclear produced process heat. This paper explains how industry and the U.S. Government are cooperating to advance nuclear hydrogen technology. It also describes the issues being explored and the results of recent R&D including materials development and testing, thermal-fluids research, and systems analysis. The paper also describes the hydrogen production technologies being considered (including various thermochemical processes and high-temperature electrolysis).

M. Patterson; C. Park

2008-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "generating plants release" 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

VANESA: a mechanistic model of radionuclide release and aerosol generation during core debris interactions with concrete  

Science Conference Proceedings (OSTI)

This document describes a model, called VANESA, of the release of radionuclides and generation of aerosol accompanying reactor core melt interactions with structural concrete. The document also serves as a user's manual for an implementation of the VANESA model as a computer code. The technical bases for the VANESA model are reviewed. Mechanical generation of aerosols as bubbles burst at melt surfaces or as a result of liquid entrainment is considered. A description of these processes based on data for gas-sparged water systems is included in the VANESA model. Some limiting solutions to the problem of the competitive processes of nucleation of particles from vapor, condensation of vapors on surfaces, and coagulation of particles are examined. From these examinations an approximate model of the aerosol particle size produced during core debris interactions with concrete is devised. The attenuation of aerosol emission during core debris/concrete interactions by an overlying water pool is discussed. The document concludes with a description of a computer code implementation of the VANESA model. This implementation of the model was used in recent assessments of the behavior of radionuclides during severe reactor accidents. Comparisons of the predictions of radionuclide release during core debris/concrete interactions obtained with the VANESA model and with older models are presented.

Powers, D.A.; Brockmann, J.E.; Shiver, A.W.

1986-07-01T23:59:59.000Z

82

Average effluent releases from U. S. nuclear power reactors, compared with those from fossil-fueled plants, in terms of currently applicable environmental standards  

SciTech Connect

From 3rd international congress of the International Radiation Protection Association meeting; Washington, District of Columbia, USA(9 Sep 1973). Between 1967 and 1972, eighteen second generation'' lightwater-cooled nuclear power plants, with capacities in the range of 500 to 800 MW(e) have been put into operation in the United States. These were in addition to ten smaller demonstration plants and one high-temperature gas-cooled nuclear power plant in operation at the start of this period. The reported yearly air effluent releases of radioactive gases, halogens and particulates, and liquid effluent fission and activation products and of tritium from these plants are evaluated on a Ci/10/sup 3/ MW(e) basis, and the overall yearly averages for the various types of reactors (boiling water (BWR), pressurized water (PWR) and high temperature gas-cooled (HTGR)! are compared. These and the amounts of effluents released from reference 1,000 MW(e) fossil-fueled plants are compared in terms of relative environmental concentrations and their relationship to the applicable U. S. environmental standards for the principal constituents in their respective plant air-effluent streams. 21 references. (auth)

Hull, A.P.

1973-09-19T23:59:59.000Z

83

Efficient gas stream cooling in Second-Generation PFBC plants  

SciTech Connect

The coal-fueled Advanced or Second-Generation Pressurized Fluidized Bed Combustor concept (APFBC) is an efficient combined cycle in which coal is carbonized (partially gasified) to fuel a gas turbine, gas turbine exhaust heats feedwater for the steam cycle, and carbonizer char is used to generate steam for a steam turbine while heating combustion air for the gas turbine. The system can be described as an energy cascade in which chemical energy in solid coal is converted to gaseous form and flows to the gas turbine followed by the steam turbine, where it is converted to electrical power. Likewise, chemical energy in the char flows to both turbines generating electrical power in parallel. The fuel gas and vitiated air (PFBC exhaust) streams must be cleaned of entrained particulates by high-temperature equipment representing significant extensions of current technology. The energy recovery in the APFBC cycle allows these streams to be cooled to lower temperatures without significantly reducing the efficiency of the plant. Cooling these streams would allow the use of lower-temperature gas cleanup equipment that more closely approaches commercially available equipment, reducing cost and technological risk, and providing an earlier path to commercialization. This paper describes the performance effects of cooling the two hottest APFBC process gas streams: carbonizer fuel gas and vitiated air. Each cooling variation is described in terms of energy utilization, cycle efficiency, and cost implications.

White, J.S.; Horazak, D.A. [Foster Wheeler Development Corp., Livingston, NJ (United States); Robertson, A. [Foster Wheeler Development Corp., Livingston, NJ (United States)

1994-07-01T23:59:59.000Z

84

Population dose commitments due to radioactive releases from nuclear power plant sites in 1986  

Science Conference Proceedings (OSTI)

Population radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1986. Fifty-year dose commitments for a one-year exposure from both liquid and atmospheric releases were calculated for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each of 66 reactor sites. This report tabulates the results of these calculations, showing the dose commitments for both water and airborne pathways for each age group and organ. Also included for each of the sites is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The total dose commitments (from both liquid and airborne pathways) for each site ranged from a high of 31 person-rem to a low of 0.0007 person-rem for the sites with plants operating throughout the year with an arithmetic mean of 1.7 person-rem. The total population dose for all sites was estimated at 110 person-rem for the 140 million people considered at risk. The site average individual dose commitment from all pathways ranged from a low of 2 {times} 10{sup -6} mrem to a high of 0.02 mrem. No attempt was made in this study to determine the maximum dose commitment received by any one individual from the radionuclides released at any of the sites. 12 refs.

Baker, D.A. (Pacific Northwest Lab., Richland, WA (USA))

1989-10-01T23:59:59.000Z

85

Population dose commitments due to radioactive releases from nuclear power plant sites in 1985  

Science Conference Proceedings (OSTI)

Population radiation dose commitments have been estimated from reported radionuclide releases from commericial power reactors operating during 1985. Fifty-year dose commitments from a one-year exposure were calculated from both liquid and atmospheric releases for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each of 61 sites. This report tabulates the results of these calculations, showing the dose commitments for both liquid and airborne pathways for each age group and organ. Also included for each of the sites is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The total dose commitments (from both liquid and airborne pathways) for each site ranged from a high of 73 person-rem to a low of 0.011 person-rem for the sites with plants operating throughout the year with an arithmetic mean of 3 person-rem. The total population dose for all sites was estimated at 200 person-rem for the 110 million people considered at risk. The site average individual dose commitment from all pathways ranged from a low of 5 /times/ 10/sup /minus/6/ mrem to a high of 0.02 mrem. No attempt was made in this study to determine the maximum dose commitment received by any one individual from the radionuclides released at any of the sites.

Baker, D.A.

1988-08-01T23:59:59.000Z

86

Population dose commitments due to radioactive releases from nuclear power plant sites in 1984  

Science Conference Proceedings (OSTI)

Population radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1984. Fifty-year dose commitments from a one-year exposure were calculated from both liquid and atmospheric releases for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each of 56 sites. This report tabulates the results of these calculations, showing the dose commitments for both liquid and airborne pathways for each age group and organ. Also included for each of the sites is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The total dose commitments (from both liquid and airborne pathways) for each site ranged from a high of 110 person-rem to a low of 0.002 person-rem for the sites with plants operating throughout the year with an arithmetic mean of 5 person-rem. The total population dose for all sites was estimated at 280 person-rem for the 100 million people considered at risk. The site average individual dose commitment from all pathways ranged from a low of 6 x 10/sup -6/ mrem to a high of 0.04 mrem. No attempt was made in this study to determine the maximum dose commitment received by any one individual from the radionuclides released at any of the sites.

Baker, D.A.

1988-01-01T23:59:59.000Z

87

Population dose commitments due to radioactive releases from nuclear power plant sites in 1982. Volume 4  

Science Conference Proceedings (OSTI)

Population radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1982. Fifty-year dose commitments from a one-year exposure were calculated from both liquid and atmospheric releases for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each of 51 sites. This report tabulates the results of these calculations, showing the dose commitments for both liquid and airborne pathways for each age group and organ. Also included for each site is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The total dose commitments from both liquid and airborne pathways ranged from a high of 30 person-rem to a low of 0.007 person-rem for the sites with plants operating throughout the year with an arithmetic mean of 3 person-rem. The total population dose for all sites was estimated at 130 person-rem for the 100 million people considered at risk. The average individual dose commitment from all pathways on a site basis ranged from a low of 6 x 10/sup -7/ mrem to a high of 0.06 mrem. No attempt was made in this study to determine the maximum dose commitment received by any one individual from the radionuclides released at any of the sites.

Baker, D.A.; Peloquin, R.A.

1986-06-01T23:59:59.000Z

88

HTGR power plant turbine-generator load control system  

SciTech Connect

A control system is disclosed for a high temperature gas cooled reactor power plant, wherein a steam source derives heat from the reactor coolant gas to generate superheated and reheated steam in respective superheater and reheater sections that are included in the steam source. Each of dual turbine-generators includes a high pressure turbine to pass superheated steam and an associated intermediate low pressure turbine to pass reheated steam. A first admission valve means is connected to govern a flow of superheated steam through a high pressure turbine, and a second admission valve means is connected to govern a flow of reheated steam through an intermediate-low pressure turbine. A bypass line and bypass valve means connected therein are connected across a second admission valve means and its intermediate-low pressure turbine. The second admission valve means is positioned to govern the steam flow through the intermediate-low pressure turbine in accordance with the desired power output of the turbine-generator. In response to the steam flow through the intermediate-low pressure turbine, the bypass valve means is positioned to govern the steam flow through the bypass line to maintain a desired minimum flow through the reheater section at times when the steam flow through the intermediate-low pressure turbine is less than such minimum. The power output of the high pressure turbine is controlled by positioning the first admission valve means in predetermined proportionality with the desired power output of the turbine-generator, thereby improving the accuracy of control of the power output of the high pressure turbine at low load levels.

Braytenbah, A.S.; Jaegtnes, K.O.

1976-12-28T23:59:59.000Z

89

Next Generation Nuclear Plant Methods Technical Program Plan  

Science Conference Proceedings (OSTI)

One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

2010-12-01T23:59:59.000Z

90

Next Generation Nuclear Plant Methods Technical Program Plan  

Science Conference Proceedings (OSTI)

One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

2007-01-01T23:59:59.000Z

91

Next Generation Nuclear Plant Methods Technical Program Plan -- PLN-2498  

Science Conference Proceedings (OSTI)

One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

2010-09-01T23:59:59.000Z

92

Modeling a Helical-coil Steam Generator in RELAP5-3D for the Next Generation Nuclear Plant  

SciTech Connect

Options for the primary heat transport loop heat exchangers for the Next Generation Nuclear Plant are currently being evaluated. A helical-coil steam generator is one heat exchanger design under consideration. Safety is an integral part of the helical-coil steam generator evaluation. Transient analysis plays a key role in evaluation of the steam generators safety. Using RELAP5-3D to model the helical-coil steam generator, a loss of pressure in the primary side of the steam generator is simulated. This report details the development of the steam generator model, the loss of pressure transient, and the response of the steam generator primary and secondary systems to the loss of primary pressure. Back ground on High Temperature Gas-cooled reactors, steam generators, the Next Generation Nuclear Plant is provided to increase the readers understanding of the material presented.

Nathan V. Hoffer; Piyush Sabharwall; Nolan A. Anderson

2011-01-01T23:59:59.000Z

93

NETL: News Release - Department of Energy Releases Updated Report Tracking  

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

Department of Energy Releases Updated Report Tracking Resurgence of Coal-Fired Power Plants Department of Energy Releases Updated Report Tracking Resurgence of Coal-Fired Power Plants Report Shows 151 Proposed and New Plants, 90 Gigawatts of Capacity by 2020 WASHINGTON, DC - A newly released Department of Energy report shows that many power producers are turning to coal as the most economic and abundant national resource for electricity generation. The report, titled Tracking New Coal-Fired Power Plants, was developed by the Office of Fossil Energy's National Energy Technology Laboratory (NETL) to provide a snapshot of coal's resurgence in the generation of electric power. The report was derived from a database that NETL maintains to track proposals for new coal-fired power plants. Created in 2002, the database is updated quarterly as new information is released and cataloged. The results contained in the database are derived from information publicly available from a variety of tracking organizations and news groups.

94

Release and disposal of materials during decommissioning of Siemens MOX fuel fabrication plant at Hanau, Germany  

SciTech Connect

In September 2006, decommissioning and dismantling of the Siemens MOX Fuel Fabrication Plant in Hanau were completed. The process equipment and the fabrication buildings were completely decommissioned and dismantled. The other buildings were emptied in whole or in part, although they were not demolished. Overall, the decommissioning process produced approximately 8500 Mg of radioactive waste (including inactive matrix material); clearance measurements were also performed for approximately 5400 Mg of material covering a wide range of types. All the equipment in which nuclear fuels had been handled was disposed of as radioactive waste. The radioactive waste was conditioned on the basis of the requirements specified for the projected German final disposal site 'Schachtanlage Konrad'. During the pre-conditioning, familiar processes such as incineration, compacting and melting were used. It has been shown that on account of consistently applied activity containment (barrier concept) during operation and dismantling, there has been no significant unexpected contamination of the plant. Therefore almost all the materials that were not a priori destined for radioactive waste were released without restriction on the basis of the applicable legal regulations (chap. 29 of the Radiation Protection Ordinance), along with the buildings and the plant site. (authors)

Koenig, Werner [TUEV NORD EnSys Hannover GmbH and Co. KG (Germany); Baumann, Roland [Siemens AG, Power Generation (Germany)

2007-07-01T23:59:59.000Z

95

Electric power generating plant having direct-coupled steam and compressed-air cycles  

DOE Patents (OSTI)

An electric power generating plant is provided with a Compressed Air Energy Storage (CAES) system which is directly coupled to the steam cycle of the generating plant. The CAES system is charged by the steam boiler during off peak hours, and drives a separate generator during peak load hours. The steam boiler load is thereby levelized throughout an operating day.

Drost, M.K.

1981-01-07T23:59:59.000Z

96

Electric power generating plant having direct coupled steam and compressed air cycles  

DOE Patents (OSTI)

An electric power generating plant is provided with a Compressed Air Energy Storage (CAES) system which is directly coupled to the steam cycle of the generating plant. The CAES system is charged by the steam boiler during off peak hours, and drives a separate generator during peak load hours. The steam boiler load is thereby levelized throughout an operating day.

Drost, Monte K. (Richland, WA)

1982-01-01T23:59:59.000Z

97

Nuclear Plant Design and Modification Guidelines for PWR Steam Generator Reliability  

Science Conference Proceedings (OSTI)

Operating and maintenance experience relative to PWR steam generator reliability has produced a variety of "lessons learned." This information has been incorporated in a series of guidelines to aid utilities in major plant modifications and new plant construction.

1991-09-25T23:59:59.000Z

98

RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

amounts released from coal-fired plants without particulatethorium emissions from coal-fired plants may be compared toemissions from coal-fired plants. This comparison, though,

Nero, A.V.

2010-01-01T23:59:59.000Z

99

Evaluation of the generation and release of flammable gases in tank 241-SY-101  

DOE Green Energy (OSTI)

Tank 241-SY-101 is a double shell, high-level waste tank located in the 200 West Area of the Hanford Site. This tank contains about 1 million gallons of waste that was concentrated at the 242-S Evaporator. Shortly after the waste was put in the tank, the waste began to expand because the generation of gases. In 1990 this tank was declared to have an unreviewed safety question because of the periodic release of hydrogen and nitrous oxide. A safety program was established to conduct a characterization of the waste and vented gases and to determine an effective means to prevent the accumulation of flammable gases in the tank dome space and ventilation system. Results of the expanded characterization conducted in fiscal year 1991 are presented. The use of gas chromatographs, mass spectrometers, and hydrogen-specific monitors provided a greater understanding of the vented gases. Additional instrumentation placed in the tank also helped to provide more detailed information on tank temperatures, gas pressure, and gas flow rates. An extensive laboratory study involving the Westinghouse Hanford Company, Pacific Northwest Laboratory, Argonne National Laboratory, and the Georgia Institute of Technology was initiated for the purpose of determining the mechanisms responsible for the generation of various gases. These studies evaluate both radiolytic and thermochemical processes. Results of the first series of experiments are described.

Babad, H.; Johnson, G.D.; Lechelt, J.A.; Reynolds, D.A. (Westinghouse Hanford Co., Richland, WA (United States)) [Westinghouse Hanford Co., Richland, WA (United States); Pederson, L.R.; Strachan, D.M. (Pacific Northwest Lab., Richland, WA (United States)) [Pacific Northwest Lab., Richland, WA (United States); Meisel, D.; Jonah, C. (Argonne National Lab., IL (United States)) [Argonne National Lab., IL (United States); Ashby, E.C. (Georgia Inst. of Tech., Atlanta, GA (United States)) [Georgia Inst. of Tech., Atlanta, GA (United States)

1991-11-01T23:59:59.000Z

100

Risk Framework for the Next Generation Nuclear Power Plant Construction  

E-Print Network (OSTI)

Uncertainty can be either an opportunity or a risk. Every construction project begins with the expectation of project performance. To meet the expectation, construction projects need to be managed through sound risk assessment and management beginning with the front-end of the project life cycle to check the feasibility of a project. The Construction Industry Institute’s (CII) International Project Risk Assessment (IPRA) tool has been developed, successfully used for a variety of heavy industry sector projects, and recently elevated to Best Practice status. However, its current format is inadequate to address the unique challenges of constructing the next generation of nuclear power plants (NPP). To understand and determine the risks associated with NPP projects, the goal of this thesis is to develop tailored risk framework for NPP projects that leverages and modifies the existing IPRA process. The IPRA has 82 elements to assess the risks associated with international construction projects. The modified IPRA adds five major issues (elements) to consider the unique risk factors of typical NPP projects based upon a review of the literature and an evaluation of the performance of previous nuclear-related facilities. The modified IPRA considers the sequence of NPP design that ultimately impacts the risks associated with plant safety and operations. Historically, financial risks have been a major chronic problem with the construction of NPPs. This research suggests that unstable regulations and the lack of design controls and oversight are significant risk issues. This thesis includes a consistency test to initially validate whether the asserted risks exist in actual conditions. Also, an overall risk assessment is performed based on the proposed risk framework for NPP and the list of assessed risk is proposed through a possible scenario. After the assessment, possible mitigation strategies are also provided against the major risks as a part of this thesis. This study reports on the preliminary findings for developing a new risk framework for constructing nuclear power plants. Future research is needed for advanced verification of the proposed elements. Follow-on efforts should include verification and validation of the proposed framework by industry experts and methods to quantify and evaluate the performance and risks associated with the multitude of previous NPP projects.

Yeon, Jaeheum 1981-

2012-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "generating plants release" 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

Method and apparatus for optimizing operation of a power generating plant using artificial intelligence techniques  

DOE Patents (OSTI)

A method and apparatus for optimizing the operation of a power generating plant using artificial intelligence techniques. One or more decisions D are determined for at least one consecutive time increment, where at least one of the decisions D is associated with a discrete variable for the operation of a power plant device in the power generating plant. In an illustrated embodiment, the power plant device is a soot cleaning device associated with a boiler.

Wroblewski, David (Mentor, OH); Katrompas, Alexander M. (Concord, OH); Parikh, Neel J. (Richmond Heights, OH)

2009-09-01T23:59:59.000Z

102

NETL: News Release - Clean Coal Plant to Anchor West Virginia "Eco-Park"  

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

7, 2004 7, 2004 Clean Coal Plant to Anchor West Virginia "Eco-Park" $215 Million Co-Production Demonstration Plant to Create 6,000 New Jobs LEWISBURG, WV - Secretary of Energy Spencer Abraham today commissioned a new $215 million West Virginia clean coal project based on new technology that over the next 60 months will deliver environmental improvements, economic benefits and thousands of new jobs. The project is part of President Bush's Clean Coal Power Initiative, a key component of the National Energy Policy that competitively selects commercial-scale technology demonstrations to continue and expand the use of coal as a fuel source. Development of the new technology, termed atmospheric-pressure circulating fluidized-bed combustion, is a joint-venture between the Department of Energy (DOE) and Western Greenbrier Co-Generation LLC. It will use nearby waste-coal to generate electric power with ultra-low emissions of pollutants while concurrently producing combustion ash byproducts and heat to support industrial activities. The power plant will serve as the anchor tenant for a new "Eco-Park" site in Rainelle, W. Va.

103

Dependable Hydrogen and Industrial Heat Generation from the Next Generation Nuclear Plant  

DOE Green Energy (OSTI)

The Department of Energy is working with industry to develop a next generation, high-temperature gas-cooled nuclear reactor (HTGR) as a part of the effort to supply the US with abundant, clean and secure energy. The Next Generation Nuclear Plant (NGNP) project, led by the Idaho National Laboratory, will demonstrate the ability of the HTGR to generate hydrogen, electricity, and high-quality process heat for a wide range of industrial applications. Substituting HTGR power for traditional fossil fuel resources reduces the cost and supply vulnerability of natural gas and oil, and reduces or eliminates greenhouse gas emissions. As authorized by the Energy Policy Act of 2005, industry leaders are developing designs for the construction of a commercial prototype producing up to 600 MWt of power by 2021. This paper describes a variety of critical applications that are appropriate for the HTGR with an emphasis placed on applications requiring a clean and reliable source of hydrogen. An overview of the NGNP project status and its significant technology development efforts are also presented.

Charles V. Park; Michael W. Patterson; Vincent C. Maio; Piyush Sabharwall

2009-03-01T23:59:59.000Z

104

Population dose commitments due to radioactive releases from nuclear power plant sites in 1988. Volume 10  

Science Conference Proceedings (OSTI)

Population radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1988. Fifty-year commitments for a one-year exposure from both liquid and atmospheric releases were calculated for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each of 71 reactor sites. This report tabulates the results of these calculations, showing the dose commitments for both water and airborne pathways for each age group and organ. Also included for each of the sites is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The total collective dose commitments (from both liquid and airborne pathways) for each site ranged from a high of 16 person-rem to a low of 0.0011 person-rem for the sites with plants operating throughout the year with an arithmetic mean of 1.1 person-rem. The total population dose for all sites was estimated at 75 person-rem for the 150 million people considered at risk. The site average individual dose commitment from all pathways ranged from a low of 3 {times} 10{sup {minus}7} mrem to a high of 0.02 mrem. No attempt was made in this study to determine the maximum dose commitment received by any one individual from the radionuclides released at any of the sites. However, licensee calculation of doses to the maximally exposed individual at some sites indicated values of up to approximately 100 times average individual doses (on the order of a few millirem per year).

Baker, D.A. [Pacific Northwest Lab., Richland, WA (United States)

1992-01-01T23:59:59.000Z

105

Population dose commitments due to radioactive releases from nuclear power plant sites in 1988  

Science Conference Proceedings (OSTI)

Population radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1988. Fifty-year commitments for a one-year exposure from both liquid and atmospheric releases were calculated for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each of 71 reactor sites. This report tabulates the results of these calculations, showing the dose commitments for both water and airborne pathways for each age group and organ. Also included for each of the sites is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The total collective dose commitments (from both liquid and airborne pathways) for each site ranged from a high of 16 person-rem to a low of 0.0011 person-rem for the sites with plants operating throughout the year with an arithmetic mean of 1.1 person-rem. The total population dose for all sites was estimated at 75 person-rem for the 150 million people considered at risk. The site average individual dose commitment from all pathways ranged from a low of 3 {times} 10{sup {minus}7} mrem to a high of 0.02 mrem. No attempt was made in this study to determine the maximum dose commitment received by any one individual from the radionuclides released at any of the sites. However, licensee calculation of doses to the maximally exposed individual at some sites indicated values of up to approximately 100 times average individual doses (on the order of a few millirem per year).

Baker, D.A. (Pacific Northwest Lab., Richland, WA (United States))

1992-01-01T23:59:59.000Z

106

Population dose commitments due to radioactive releases from nuclear power plant sites in 1983  

Science Conference Proceedings (OSTI)

Population radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1983. Fifty-year dose commitments from a one-year exposure were calculated from both liquid and atmospheric releases for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each of 52 sites. This report tabulates the results of these calculations, showing the dose commitments for both liquid and airborne pathways for each age group and organ. Also included for each of the sites is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The total dose commitments (from both liquid and airborne pathways) for each site ranged from a high of 45 person-rem to a low of 0.002 person-rem for the sites with plants operating throughout the year with an arithmetic mean of 3 person-rem. The total population dose for all sites was estimated at 170 person-rem for the 100 million people considered at risk.

Baker, D.A.; Peloquin, R.A.

1987-04-01T23:59:59.000Z

107

Dose commitments due to radioactive releases from nuclear power plant sites in 1989  

Science Conference Proceedings (OSTI)

Population and individual radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1989. Fifty-year dose commitments for a one-year exposure from both liquid and atmospheric releases were calculated for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each of 72 reactor sites. This report tabulates the results of these calculations, showing the dose commitments for both water and airborne pathways for each age group and organ. Also included for each of the sites is an estimate of individual doses which are compared with 10 CFR Part 50, Appendix I design objectives. The total collective dose commitments (from both liquid and airborne pathways) for each site ranged from a high of 14 person-rem to a low of 0.005 person-rem for the sites with plants in operation and producing power during the year. The arithmetic mean was 1.2 person-rem. The total population dose for all sites was estimated at 84 person-rem for the 140 million people considered at risk. The individual dose commitments estimated for all sites were below the Appendix I design objectives.

Baker, D.A. (Pacific Northwest Lab., Richland, WA (United States))

1993-02-01T23:59:59.000Z

108

Performance Calculations and Optimization of a Fresnel Direct Steam Generation CSP Plant with Heat Storage.  

E-Print Network (OSTI)

?? This master thesis deals with the performance calculations of a 9MW linear Fresnel CSP plant withdirect steam generation built by the Solar Division of… (more)

Schlaifer, Perrine

2013-01-01T23:59:59.000Z

109

Land Release Estimating and Record-Keeping TRI at Power Plants (LARK-TRIPP) RY2009 Version 1.0  

Science Conference Proceedings (OSTI)

LARK-TRIPP estimates emissions of chemicals from power plants to air, water, and land to support annual reporting under the U.S. EPA Toxics Release Inventory (TRI) program. LARK-TRIPP is a powerful, user-friendly tool for estimating, tracking, and reporting releases of chemicals primarily trace substances from fossil-fired steam electric plants. The spreadsheet-like tool has been applied by numerous energy companies to increase the efficiency and reduce the costs of TRI-related analyses while enhancing c...

2010-04-26T23:59:59.000Z

110

Worldwide assessment of steam-generator problems in pressurized-water-reactor nuclear power plants  

Science Conference Proceedings (OSTI)

Objective is to assess the reliability of steam generators of pressurized water reactor (PWR) power plants in the United States and abroad. The assessment is based on operation experience of both domestic and foreign PWR plants. The approach taken is to collect and review papers and reports available from the literature as well as information obtained by contacting research institutes both here and abroad. This report presents the results of the assessment. It contains a general background of PWR plant operations, plant types, and materials used in PWR plants. A review of the worldwide distribution of PWR plants is also given. The report describes in detail the degradation problems discovered in PWR steam generators: their causes, their impacts on the performance of steam generators, and the actions to mitigate and avoid them. One chapter is devoted to operating experience of PWR steam generators in foreign countries. Another discusses the improvements in future steam generator design.

Woo, H.H.; Lu, S.C.

1981-09-15T23:59:59.000Z

111

Property:EIA/861/OperatesGeneratingPlant | Open Energy Information  

Open Energy Info (EERE)

OperatesGeneratingPlant OperatesGeneratingPlant Jump to: navigation, search This is a property of type Boolean. Description: Operates Generating Plant Entity operates power generating plants (Y or N) [1] References ↑ EIA Form EIA-861 Final Data File for 2008 - F861 File Layout-2008.doc Pages using the property "EIA/861/OperatesGeneratingPlant" Showing 25 pages using this property. (previous 25) (next 25) A A & N Electric Coop (Virginia) + true + AEP Generating Company + true + AES Eastern Energy LP + true + AGC Division of APG Inc + true + Akiachak Native Community Electric Co + true + Alabama Municipal Elec Authority + true + Alabama Power Co + true + Alaska Electric & Energy Coop + true + Alaska Electric Light&Power Co + true + Alaska Energy Authority + true +

112

Assessment of next generation nuclear plant intermediate heat exchanger design.  

DOE Green Energy (OSTI)

The Next Generation Nuclear Plant (NGNP), which is an advanced high temperature gas reactor (HTGR) concept with emphasis on production of both electricity and hydrogen, involves helium as the coolant and a closed-cycle gas turbine for power generation with a core outlet/gas turbine inlet temperature of 900-1000 C. In the indirect cycle system, an intermediate heat exchanger is used to transfer the heat from primary helium from the core to the secondary fluid, which can be helium, nitrogen/helium mixture, or a molten salt. The system concept for the vary high temperature reactor (VHTR) can be a reactor based on the prismatic block of the GT-MHR developed by a consortium led by General Atomics in the U.S. or based on the PBMR design developed by ESKOM of South Africa and British Nuclear Fuels of U.K. This report has made an assessment on the issues pertaining to the intermediate heat exchanger (IHX) for the NGNP. A detailed thermal hydraulic analysis, using models developed at ANL, was performed to calculate heat transfer, temperature distribution, and pressure drop. Two IHX designs namely, shell and straight tube and compact heat exchangers were considered in an earlier assessment. Helical coil heat exchangers were analyzed in the current report and the results were compared with the performance features of designs from industry. In addition, a comparative analysis is presented between the shell and straight tube, helical, and printed circuit heat exchangers from the standpoint of heat exchanger volume, primary and secondary sides pressure drop, and number of tubes. The IHX being a high temperature component, probably needs to be designed using ASME Code Section III, Subsection NH, assuming that the IHX will be classified as a class 1 component. With input from thermal hydraulic calculations performed at ANL, thermal conduction and stress analyses were performed for the helical heat exchanger design and the results were compared with earlier-developed results on shell and straight tube and printed circuit heat exchangers.

Majumdar, S.; Moisseytsev, A.; Natesan, K.; Nuclear Engineering Division

2008-10-17T23:59:59.000Z

113

Next Generation Geothermal Power Plants (NGGPP) process data for binary cycle plants  

DOE Green Energy (OSTI)

The Next Generation Geothermal Power Plants (NGGPP) study provides the firm estimates - in the public domain - of the cost and performance of U.S. geothermal systems and their main components in the early 1990s. The study was funded by the U.S. Department of Energy Geothermal Research Program, managed for DOE by Evan Hughes of the Electric Power Research Institute, Palo Alto, CA, and conducted by John Brugman and others of the CE Holt Consulting Firm, Pasadena, CA. The printed NGGPP reports contain detailed data on the cost and performance for the flash steam cycles that were characterized, but not for the binary cycles. The nine Tables in this document are the detailed data sheets on cost and performance for the air cooled binary systems that were studied in the NGGPP.

Not Available

1996-10-02T23:59:59.000Z

114

Updated Capital Cost Estimates for Electricity Generation Plants  

Reports and Publications (EIA)

This paper provides information on the cost of building new electricity power plants. These cost estimates are critical inputs in the development of energy projections and analyses.

Michael Leff

2010-11-18T23:59:59.000Z

115

Ownership Change, Incentives and Plant Efficiency: The Divestiture of U.S. Electric Generation Plants  

E-Print Network (OSTI)

compiles data on power plant operations and characteristicscharacteristics (e.g. power plant unit, state, grid controlBaseCase contains hourly power-plant unit-level information

Bushnell, James B.; Wolfram, Catherine

2005-01-01T23:59:59.000Z

116

Next Generation Nuclear Plant Reactor Pressure Vessel Materials Research and Development Plan (PLN-2803)  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy (DOE) has selected the High-Temperature Gas-cooled Reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production, with an outlet gas temperature in the range of 750°C, and a design service life of 60 years. The reactor design will be a graphite-moderated, helium-cooled, prismatic, or pebble bed reactor and use low-enriched uranium, Tri-Isotopic (TRISO)-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. Selection of the technology and design configuration for the NGNP must consider both the cost and risk profiles to ensure that the demonstration plant establishes a sound foundation for future commercial deployments. The NGNP challenge is to achieve a significant advancement in nuclear technology while setting the stage for an economically viable deployment of the new technology in the commercial sector soon after 2020. This technology development plan details the additional research and development (R&D) required to design and license the NGNP RPV, assuming that A 508/A 533 is the material of construction. The majority of additional information that is required is related to long-term aging behavior at NGNP vessel temperatures, which are somewhat above those commonly encountered in the existing database from LWR experience. Additional data are also required for the anticipated NGNP environment. An assessment of required R&D for a Grade 91 vessel has been retained from the first revision of the R&D plan in Appendix B in somewhat less detail. Considerably more development is required for this steel compared to A 508/A 533 including additional irradiation testing for expected NGNP operating temperatures, high-temperature mechanical properties, and extensive studies of long-term microstructural stability.

J. K. Wright; R. N. Wright

2010-07-01T23:59:59.000Z

117

North Brawley Power Plant Placed in Service; Currently Generating 17 MW;  

Open Energy Info (EERE)

North Brawley Power Plant Placed in Service; Currently Generating 17 MW; North Brawley Power Plant Placed in Service; Currently Generating 17 MW; Additional Operations Update Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: North Brawley Power Plant Placed in Service; Currently Generating 17 MW; Additional Operations Update Author Electric Energy Publications Inc. Published Publisher Not Provided, Date Not Provided DOI Not Provided Check for DOI availability: http://crossref.org Online Internet link for North Brawley Power Plant Placed in Service; Currently Generating 17 MW; Additional Operations Update Citation Electric Energy Publications Inc.. North Brawley Power Plant Placed in Service; Currently Generating 17 MW; Additional Operations Update [Internet]. [updated 2010;cited 2010]. Available from:

118

EIS-0476: Vogtle Electric Generating Plant, Units 3 and 4 | Department of  

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

76: Vogtle Electric Generating Plant, Units 3 and 4 76: Vogtle Electric Generating Plant, Units 3 and 4 EIS-0476: Vogtle Electric Generating Plant, Units 3 and 4 Summary This EIS evaluates the environmental impacts of construction and startup of the proposed Units 3 and 4 at the Vogtle Electric Generating Plant in Burke County, Georgia. DOE adopted two Nuclear Regulatory Commission EISs associated with this project (i.e., NUREG-1872, issued 8/2008, and NUREG-1947, issued 3/2011). Public Comment Opportunities No public comment opportunities available at this time. Documents Available for Download February 17, 2012 EIS-0476: Notice of Adoption of Final Environmental Impact Statement Vogtle Electric Generating Plant, Units 3 and 4, Issuance of a Loan Guarantee to Support Funding for Construction, Burke County, GA

119

How much electricity does a typical nuclear power plant generate ...  

U.S. Energy Information Administration (EIA)

Nuclear Reactor Operational Status Tables (Information and data on nuclear power reactors Generation: by State and Reactor. Annual Energy Review, ...

120

Commercial second-generation PFBC plant transient model: Task 15  

Science Conference Proceedings (OSTI)

The advanced pressurized fluidized bed combustor (APFBC) power plant combines an efficient gas-fired combined cycle, a low-emission PFB combustor, and a coal pyrolysis unit (carbonizer) that converts coal, America`s most plentiful fuel, into the gas turbine fuel. From an operation standpoint, the APFBC plant is similar to an integrated gasification combined cycle (IGCC) plant, except that the PFBC and fluid bed heat exchanger (FBHE) allow a considerable fraction of coal energy to be shunted around the gas turbine and sent directly to the steam turbine. By contrast, the fuel energy in IGCC plants and most other combined cycles is primarily delivered to the gas turbine and then to the steam turbine. Another characteristic of the APFBC plant is the interaction among three large thermal inertias--carbonizer, PFBC, and FBHE--that presents unique operational challenges for modeling and operation of this type of plant. This report describes the operating characteristics and dynamic responses of the APFBC plant and discusses the advantages and shortcomings of several alternative control strategies for the plant. In particular, interactions between PFBC, FBHE, and steam bottoming cycle are analyzed and the effect of their interactions on plant operation is discussed. The technical approach used in the study is described in Section 2. The dynamic model is introduced in Section 3 and described is detail in the appendices. Steady-state calibration and transient simulations are presented in Sections 4 and 5. The development of the operating philosophy is discussed in Section 6. Potential design changes to the dynamic model and trial control schemes are listed in Sections 7 and 8. Conclusions derived from the study are presented in Section 9.

White, J.S.; Getty, R.T.; Torpey, M.R.

1995-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "generating plants release" 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

ESTIMATES FOR RELEASE OF RADIONUCLIDES FROM POTENTIALLY CONTAMINATED CONCRETE AT THE HADDAM NECK NUCLEAR PLANT.  

Science Conference Proceedings (OSTI)

Decommissioning of the Haddam Neck Nuclear Power Plant operated by Connecticut Yankee is in progress. Figure 1 shows a schematic of the Containment Building and Spent Fuel Pool (SFP) Building. Consideration is being given to leaving some subsurface concrete from the Containment, Spent Fuel and certain other buildings in place following NRC license termination. Characterization data of most of these structures show small amounts of residual contamination. The In-Core Sump area of the Containment Building has shown elevated levels of tritium, Co-60, Fe-55, and Eu-152 and lesser quantities of other radionuclides due to neutron activation of the concrete in this area. This analysis is provided to determine levels of residual contamination that will not cause releases to the groundwater in excess of the acceptable dose limits. The objective is to calculate a conservative relationship between the radionuclide concentration of subsurface concrete and the maximum groundwater concentration (pCi/L) for the concrete that may remain following license termination at Connecticut Yankee.

SULLIVAN, T.

2004-09-15T23:59:59.000Z

122

IMPROVEMENTS IN OR RELATING TO STEAM GENERATING PLANT  

SciTech Connect

A nuclear power plant is designed using a heavy-watermoderated, steam- cooled reactor. In this plant, feed water is heated by the moderator and reactor steam to form feed steam, which is then superheated by superheated reactor steam and expanded through a nozzle. The feed steam issuing from the nozzie has added to it the superheated reactor steam, and the resulting steam is compressed, heated further in the reactor, and part of it passed to the turbine. (D.L.C.)

Bauer, S.G.; Jubb, D.H.

1962-10-10T23:59:59.000Z

123

AVESTAR Center for operational excellence of electricity generation plants  

SciTech Connect

To address challenges in attaining operational excellence for clean energy plants, the U.S.Department of Energy’s National Energy Technology Laboratory has launched a world-class facility for Advanced Virtual Energy Simulation Training and Research (AVESTAR™). The AVESTAR Center brings together state-of-the-art, real time,high-fidelity dynamic simulators with operator training systems and 3D virtual immersive training systems into an integrated energy plant and control room environment.

Zitney, S.

2012-01-01T23:59:59.000Z

124

Examination of Heat Recovery Steam Generator (HRSG) Plants  

Science Conference Proceedings (OSTI)

Previous EPRI reports have documented problems associated with operation and maintenance of complex heat recovery steam generators (HRSGs). The EPRI report Heat Recovery Steam Generator Tube Failure Manual (1004503) provides information about known HRSG tube failures and necessary steps that can be taken to diagnose and prevent similar problems. The EPRI report Delivering High Reliability Heat Recovery Steam Generators (1004240) provides guidance for continued and reliable operation of HRSGs from initial...

2005-11-30T23:59:59.000Z

125

EIA - Updated Capital Cost Estimates for Electricity Generation Plants  

U.S. Energy Information Administration (EIA)

Almost all of these factors can vary by region, as do capacity factors for renewable generation, operations and maintenance costs associated with individual ...

126

Distributed Generation and Virtual Power Plants: Barriers and Solutions.  

E-Print Network (OSTI)

??The present technological and regulatory power system needs to adapt to the increase in the share of distributed generation. This research focuses on the applicability… (more)

Olejniczak, T.

2011-01-01T23:59:59.000Z

127

Carbon Capture and Water Emissions Treatment System (CCWESTRS) at Fossil-Fueled Electric Generating Plants  

Science Conference Proceedings (OSTI)

The Tennessee Valley Authority (TVA), the Electric Power Research Institute (EPRI), and the Department of Energy-National Energy Technologies Laboratory (DOE-NETL) are evaluating and demonstrating integration of terrestrial carbon sequestration techniques at a coal-fired electric power plant through the use of Flue Gas Desulfurization (FGD) system gypsum as a soil amendment and mulch, and coal fly ash pond process water for periodic irrigation. From January to March 2002, the Project Team initiated the construction of a 40 ha Carbon Capture and Water Emissions Treatment System (CCWESTRS) near TVA's Paradise Fossil Plant on marginally reclaimed surface coal mine lands in Kentucky. The CCWESTRS is growing commercial grade trees and cover crops and is expected to sequester 1.5-2.0 MT/ha carbon per year over a 20-year period. The concept could be used to meet a portion of the timber industry's needs while simultaneously sequestering carbon in lands which would otherwise remain non-productive. The CCWESTRS includes a constructed wetland to enhance the ability to sequester carbon and to remove any nutrients and metals present in the coal fly ash process water runoff. The CCWESTRS project is a cooperative effort between TVA, EPRI, and DOE-NETL, with a total budget of $1,574,000. The proposed demonstration project began in October 2000 and has continued through December 2005. Additional funding is being sought in order to extend the project. The primary goal of the project is to determine if integrating power plant processes with carbon sequestration techniques will enhance carbon sequestration cost-effectively. This goal is consistent with DOE objectives to provide economically competitive and environmentally safe options to offset projected growth in U.S. baseline emissions of greenhouse gases after 2010, achieve the long-term goal of $10/ton of avoided net costs for carbon sequestration, and provide half of the required reductions in global greenhouse gases by 2025. Other potential benefits of the demonstration include developing a passive technology for water treatment for trace metal and nutrient release reductions, using power plant by-products to improve coal mine land reclamation and carbon sequestration, developing wildlife habitat and green-space around production facilities, generating Total Maximum Daily Load (TMDL) credits for the use of process water, and producing wood products for use by the lumber and pulp and paper industry. Project activities conducted during the five year project period include: Assessing tree cultivation and other techniques used to sequester carbon; Project site assessment; Greenhouse studies to determine optimum plant species and by-product application; Designing, constructing, operating, monitoring, and evaluating the CCWESTRS system; and Reporting (ongoing). The ability of the system to sequester carbon will be the primary measure of effectiveness, measured by accessing survival and growth response of plants within the CCWESTRS. In addition, costs associated with design, construction, and monitoring will be evaluated and compared to projected benefits of other carbon sequestration technologies. The test plan involves the application of three levels each of two types of power plant by-products--three levels of FGD gypsum mulch, and three levels of ash pond irrigation water. This design produces nine treatment levels which are being tested with two species of hardwood trees (sweet gum and sycamore). The project is examining the effectiveness of applications of 0, 8-cm, and 15-cm thick gypsum mulch layers and 0, 13 cm, and 25 cm of coal fly ash water for irrigation. Each treatment combination is being replicated three times, resulting in a total of 54 treatment plots (3 FGD gypsum levels X 3 irrigation water levels x 2 tree species x 3 replicates). Survival and growth response of plant species in terms of sequestering carbon in plant material and soil will be the primary measure of effectiveness of each treatment. Additionally, the ability of the site soils and unsaturated zone subsurface m

P. Alan Mays; Bert R. Bock; Gregory A. Brodie; L. Suzanne Fisher; J. Devereux Joslin; Donald L. Kachelman; Jimmy J. Maddox; N. S. Nicholas; Larry E. Shelton; Nick Taylor; Mark H. Wolfe; Dennis H. Yankee; John Goodrich-Mahoney

2005-08-30T23:59:59.000Z

128

Next Generation Nuclear Plant: A Report to Congress | Department of Energy  

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

Next Generation Nuclear Plant: A Report to Congress Next Generation Nuclear Plant: A Report to Congress Next Generation Nuclear Plant: A Report to Congress The U.S. Department of Energy's (DOE's) Next Generation Nuclear Plant (NGNP) project helps address the President's goals for reducing greenhouse gas emissions and enhancing energy security. The NGNP project was formally established by the Energy Policy Act of 2005 (EPAct 2005), designated as Public Law 109-58, 42 USC 16021, to demonstrate the generation of electricity and/or hydrogen with a high-temperature nuclear energy source. The project is being executed in collaboration with industry, DOE national laboratories, and U.S. universities. The U.S. Nuclear Regulatory Commission (NRC) is responsible for licensing and regulatory oversight of the demonstration nuclear reactor.

129

Letter to NEAC to Review the Next Generation Nuclear Plant Activities |  

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

to NEAC to Review the Next Generation Nuclear Plant to NEAC to Review the Next Generation Nuclear Plant Activities Letter to NEAC to Review the Next Generation Nuclear Plant Activities The Next Generation Nuclear Plant (NGNP) project was established under the Energy Policy Act in August 2005 (EPACT-2005). EPACT-2005 defined an overall plan and timetable for NGNP research, design, licensing, construction and operation by the end of FY 2021. At the time that EPACT-2005 was passed, it was envisioned that key aspects of the project included: NGNP is based on R&D activities supported by the Gen-IV Nuclear Energy initiative; ï‚· NGNP is to be used to generate electricity, to produce hydrogen or (to do) both; ï‚· The Idaho National Laboratory (INL) will be the lead national lab for the project; ï‚· NGNP will be sited at the INL in

130

Next Generation Nuclear Plant: A Report to Congress | Department of Energy  

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

Next Generation Nuclear Plant: A Report to Congress Next Generation Nuclear Plant: A Report to Congress Next Generation Nuclear Plant: A Report to Congress The U.S. Department of Energy's (DOE's) Next Generation Nuclear Plant (NGNP) project helps address the President's goals for reducing greenhouse gas emissions and enhancing energy security. The NGNP project was formally established by the Energy Policy Act of 2005 (EPAct 2005), designated as Public Law 109-58, 42 USC 16021, to demonstrate the generation of electricity and/or hydrogen with a high-temperature nuclear energy source. The project is being executed in collaboration with industry, DOE national laboratories, and U.S. universities. The U.S. Nuclear Regulatory Commission (NRC) is responsible for licensing and regulatory oversight of the demonstration nuclear reactor.

131

Next Generation Nuclear Plant Reactor Pressure Vessel Materials Research and Development Plan (PLN-2803)  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy has selected the High Temperature Gas-cooled Reactor design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production. It will have an outlet gas temperature in the range of 900°C and a plant design service life of 60 years. The reactor design will be a graphite moderated, helium-cooled, prismatic, or pebble-bed reactor and use low-enriched uranium, Tri-Isotopic-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Materials Research and Development Program is responsible for performing research and development on likely NGNP materials in support of the NGNP design, licensing, and construction activities. Selection of the technology and design configuration for the NGNP must consider both the cost and risk profiles to ensure that the demonstration plant establishes a sound foundation for future commercial deployments. The NGNP challenge is to achieve a significant advancement in nuclear technology while setting the stage for an economically viable deployment of the new technology in the commercial sector soon after 2020. Studies of potential Reactor Pressure Vessel (RPV) steels have been carried out as part of the pre-conceptual design studies. These design studies generally focus on American Society of Mechanical Engineers (ASME) Code status of the steels, temperature limits, and allowable stresses. Three realistic candidate materials have been identified by this process: conventional light water reactor RPV steels A508/533, 2¼Cr-1Mo in the annealed condition, and modified 9Cr 1Mo ferritic martenistic steel. Based on superior strength and higher temperature limits, the modified 9Cr-1Mo steel has been identified by the majority of design engineers as the preferred choice for the RPV. All of the vendors have concluded, however, that with adequate engineered cooling of the vessel, the A508/533 steels are also acceptable.

J. K. Wright; R. N. Wright

2008-04-01T23:59:59.000Z

132

Power Plant Electrical Reference Series, Volume 1: Electric Generators  

Science Conference Proceedings (OSTI)

This comprehensive and practical guide to electric power apparatus and electrical phenomena provides an up-to-date source book for power plant managers, engineers, and operating personnel. Aiding in the recognition and prevention of potential problems, the 16-volume guide can help utilities save staff time and reduce operating expenses.

1988-05-01T23:59:59.000Z

133

CAES (conventional compressed-air energy storage) plant with steam generation: Preliminary design and cost analysis  

Science Conference Proceedings (OSTI)

A study was performed to evaluate the performance and cost characteristics of two alternative CAES-plant concepts which utilize the low-pressure expander's exhaust-gas heat for the generation of steam in a heat recovery steam generator (HRSG). Both concepts result in increased net-power generation relative to a conventional CAES plant with a recuperator. The HRSG-generated steam produces additional power in either a separate steam-turbine bottoming cycle (CAESCC) or by direct injection into and expansion through the CAES-turboexpander train (CAESSI). The HRSG, which is a proven component of combined-cycle and cogeneration plants, replaces the recuperator of a conventional CAES plant, which has demonstrated the potential for engineering and operating related problems and higher costs than were originally estimated. To enhance the credibility of the results, the analyses performed were based on the performance, operational and cost data of the 110-MW CAES plant currently under construction for the Alabama Electric Cooperative (AEC). The results indicate that CAESCC- and CAESSI-plant concepts are attractive alternatives to the conventional CAES plant with recuperator, providing greater power generation, up to 44-MW relative to the AEC CAES plant, with competitive operating and capital costs. 5 refs., 43 figs., 26 tabs.

Nakhamkin, M.; Swensen, E.C.; Abitante, P.A. (Energy Storage and Power Consultants, Mountainside, NJ (USA))

1990-10-01T23:59:59.000Z

134

Improving heat capture for power generation in coal gasification plants  

E-Print Network (OSTI)

Improving the steam cycle design to maximize power generation is demonstrated using pinch analysis targeting techniques. Previous work models the steam pressure level in composite curves based on its saturation temperature ...

Botros, Barbara Brenda

2011-01-01T23:59:59.000Z

135

Mathematical model of steam generator feed system at power unit of nuclear plant  

Science Conference Proceedings (OSTI)

A mathematical model of a steam generator feed system at a power unit of a nuclear plant with variable values of transfer function coefficients is presented. The model is realized in the MATLAB/Simulink/Stateflow event-driven simulation.

E. M. Raskin; L. A. Denisova; V. P. Sinitsyn; Yu. V. Nesterov

2011-05-01T23:59:59.000Z

136

DOE Seeks Additional Input on Next Generation Nuclear Plant | Department of  

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

Seeks Additional Input on Next Generation Nuclear Plant Seeks Additional Input on Next Generation Nuclear Plant DOE Seeks Additional Input on Next Generation Nuclear Plant April 17, 2008 - 10:49am Addthis WASHINGTON, DC -The U.S. Department of Energy (DOE) today announced it is seeking public and industry input on how to best achieve the goals and meet the requirements for the Next Generation Nuclear Plant (NGNP) demonstration project work at DOE's Idaho National Laboratory. DOE today issued a Request for Information and Expressions of Interest from prospective participants and interested parties on utilizing cutting-edge high temperature gas reactor technology in the effort to reduce greenhouse gas emissions by enabling nuclear energy to replace fossil fuels used by industry for process heat. "This is an opportunity to advance the development of safe, reliable, and

137

DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant |  

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

DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant August 15, 2008 - 3:15pm Addthis WASHINGTON, DC -The U.S. Department of Energy (DOE) and the U.S. Nuclear Regulatory Commission (NRC) today delivered to Congress the Next Generation Nuclear Plant (NGNP) Licensing Strategy Report which describes the licensing approach, the analytical tools, the research and development activities and the estimated resources required to license an advanced reactor design by 2017 and begin operation by 2021. The NGNP represents a new concept for nuclear energy utilization, in which a gas-cooled reactor provides process heat for any number of industrial applications including electricity production, hydrogen production, coal-to-liquids, shale oil

138

DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant |  

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

DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant August 15, 2008 - 3:15pm Addthis WASHINGTON, DC -The U.S. Department of Energy (DOE) and the U.S. Nuclear Regulatory Commission (NRC) today delivered to Congress the Next Generation Nuclear Plant (NGNP) Licensing Strategy Report which describes the licensing approach, the analytical tools, the research and development activities and the estimated resources required to license an advanced reactor design by 2017 and begin operation by 2021. The NGNP represents a new concept for nuclear energy utilization, in which a gas-cooled reactor provides process heat for any number of industrial applications including electricity production, hydrogen production, coal-to-liquids, shale oil

139

Next Generation Nuclear Plant Project Technology Development Roadmaps: The Technical Path Forward  

SciTech Connect

This document presents the Next Generation Nuclear Plant (NGNP) Systems, Subsystems, and Components, establishes a baseline for the current technology readiness status, and provides a path forward to achieve increasing levels of technical maturity.

John Collins

2009-01-01T23:59:59.000Z

140

Main Generator and Exciter Life Cycle Management Plans at STARS Nuclear Plants  

Science Conference Proceedings (OSTI)

As the electric power industry becomes more competitive, life cycle management (LCM) of systems, structures, and components (SSCs) becomes more important to keep nuclear power plants economically viable throughout their remaining licensed operating terms, whether 40 or 60 years. This CD is a compilation of six optimum LCM plans for the main generators and exciters at the six STARS plants and also contains a generic LCM information "sourcebook" for generators.

2003-09-30T23:59:59.000Z

Note: This page contains sample records for the topic "generating plants release" 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

Small-Scale, Biomass-Fired Gas Turbine Plants Suitable for Distributed and Mobile Power Generation  

Science Conference Proceedings (OSTI)

This study evaluated the cost-effectiveness of small-scale, biomass-fired gas turbine plants that use an indirectly-fired gas turbine cycle. Such plants were originally thought to have several advantages for distributed generation, including portability. However, detailed analysis of two designs revealed several problems that would have to be resolved to make the plants feasible and also determined that a steam turbine cycle with the same net output was more economic than the gas turbine cycle. The incre...

2007-01-19T23:59:59.000Z

142

Life Cycle Management Plan for Main Generator and Exciter at Callaway Nuclear Plant: Generic Version  

Science Conference Proceedings (OSTI)

As the electric power industry becomes more competitive, life cycle management (LCM) of systems, structures, and components (SSCs) becomes more important to keep nuclear power plants economically viable throughout their remaining licensed operating terms, whether 40 or 60 years. This report provides Ameren UE with an optimized LCM plan for the main generator and exciter at Callaway Plant.

2003-09-30T23:59:59.000Z

143

DOE Releases Filing Instructions for Federal Risk Insurance for New Nuclear Power Plants  

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

Outlines Five Steps for New Nuclear Plant Sponsors to Enter Into a Conditional Agreement for Risk Insurance

144

Table 2. Ten Largest Plants by Generation Capacity, 2010  

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

Oklahoma" Oklahoma" "1. Northeastern","Coal","Public Service Co of Oklahoma",1815 "2. Muskogee","Coal","Oklahoma Gas & Electric Co",1524 "3. Seminole","Gas","Oklahoma Gas & Electric Co",1504 "4. Kiamichi Energy Facility","Gas","Kiowa Power Partners LLC",1178 "5. Redbud Power Plant","Gas","Oklahoma Gas & Electric Co",1160 "6. Oneta Energy Center","Gas","Calpine Central L P",1086 "7. Riverside","Gas","Public Service Co of Oklahoma",1070 "8. Sooner","Coal","Oklahoma Gas & Electric Co",1046 "9. GRDA","Coal","Grand River Dam Authority",1010

145

Production Tax Credit for Renewable Electricity Generation (released in AEO2005)  

Reports and Publications (EIA)

In the late 1970s and early 1980s, environmental and energy security concerns were addressed at the Federal level by several key pieces of energy legislation. Among them, the Public Utility Regulatory Policies Act of 1978 (PURPA), P.L. 95-617, required regulated power utilities to purchase alternative electricity generation from qualified generating facilities, including small-scale renewable generators; and the Investment Tax Credit (ITC), P.L. 95-618, part of the Energy Tax Act of 1978, provided a 10-percent Federal tax credit on new investment in capital-intensive wind and solar generation technologies.

Information Center

2005-04-01T23:59:59.000Z

146

Nuclear Energy Research Initiative (NERI): On-Line Intelligent Self-Diagnostic Monitoring for Next Generation Nuclear Plants - Phase I Annual Report  

Science Conference Proceedings (OSTI)

OAK-B135 This OSTI ID belongs to an IWO and is being released out of the system. The Program Manager Rebecca Richardson has confirmed that all reports have been received. The objective of this project is to design and demonstrate the operation of the real-time intelligent self-diagnostic and prognostic system for next generation nuclear power plant systems. This new self-diagnostic technology is titled, ''On-Line Intelligent Self-Diagnostic Monitoring System'' (SDMS). This project provides a proof-of-principle technology demonstration for SDMS on a pilot plant scale service water system, where a distributed array of sensors is integrated with active components and passive structures typical of next generation nuclear power reactor and plant systems. This project employs state-of-the-art sensors, instrumentation, and computer processing to improve the monitoring and assessment of the power reactor system and to provide diagnostic and automated prognostics capabilities.

L. J. Bond; S. R. Doctor; R. W. Gilbert; D. B. Jarrell; F. L. Greitzer; R. J. Meador

2000-09-01T23:59:59.000Z

147

Lead Risk Minimization Program at Palisades Generating Plant  

Science Conference Proceedings (OSTI)

Lead-assisted stress corrosion cracking (PbSCC) can affect all steam generator tubing materials in current use. The state-of-knowledge regarding lead transport, the effects of lead on tube degradation, and possible PbSCC mitigation measures were summarized in the Pressurized Water Reactor Lead Sourcebook: Identification and Mitigation of Lead in PWR Secondary Systems (EPRI 1013385). The Sourcebook outlines several actions that could be taken by utilities to assess and reduce the risk of PbSCC. This repor...

2008-12-08T23:59:59.000Z

148

NETL: News Release - DOE Sets Target Date to Launch Power Plant...  

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

January 22, 2001 DOE Sets Target Date to Launch Power Plant Improvement Initiative Major Emphasis is to Strengthen Reliability of Nation's Power System with Improved Coal-Based...

149

New generation enrichment monitoring technology for gas centrifuge enrichment plants  

SciTech Connect

The continuous enrichment monitor, developed and fielded in the 1990s by the International Atomic Energy Agency, provided a go-no-go capability to distinguish between UF{sub 6} containing low enriched (approximately 4% {sup 235}U) and highly enriched (above 20% {sup 235}U) uranium. This instrument used the 22-keV line from a {sup 109}Cd source as a transmission source to achieve a high sensitivity to the UF{sub 6} gas absorption. The 1.27-yr half-life required that the source be periodically replaced and the instrument recalibrated. The instrument's functionality and accuracy were limited by the fact that measured gas density and gas pressure were treated as confidential facility information. The modern safeguarding of a gas centrifuge enrichment plant producing low-enriched UF{sub 6} product aims toward a more quantitative flow and enrichment monitoring concept that sets new standards for accuracy stability, and confidence. An instrument must be accurate enough to detect the diversion of a significant quantity of material, have virtually zero false alarms, and protect the operator's proprietary process information. We discuss a new concept for advanced gas enrichment assay measurement technology. This design concept eliminates the need for the periodic replacement of a radioactive source as well as the need for maintenance by experts. Some initial experimental results will be presented.

Ianakiev, Kiril D [Los Alamos National Laboratory; Alexandrov, Boian, S. [Los Alamos National Laboratory; Boyer, Brian, D. [Los Alamos National Laboratory; Hill, Thomas, R. [Los Alamos National Laboratory; Macarthur, Duncan, W. [Los Alamos National Laboratory; Marks, Thomas [Los Alamos National Laboratory; Moss, Calvin, E. [Los Alamos National Laboratory; Sheppard, Gregory, A. [Los Alamos National Laboratory; Swinhoe, Martyn, T. [Los Alamos National Laboratory

2008-01-01T23:59:59.000Z

150

Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) Volume 6: Process Heat and Hydrogen Co-Generation PIRTs  

DOE Green Energy (OSTI)

A Phenomena Identification and Ranking Table (PIRT) exercise was conducted to identify potential safety-0-related physical phenomena for the Next Generation Nuclear Plant (NGNP) when coupled to a hydrogen production or similar chemical plant. The NGNP is a very high-temperature reactor (VHTR) with the design goal to produce high-temperature heat and electricity for nearby chemical plants. Because high-temperature heat can only be transported limited distances, the two plants will be close to each other. One of the primary applications for the VHTR would be to supply heat and electricity for the production of hydrogen. There was no assessment of chemical plant safety challenges. The primary application of this PIRT is to support the safety analysis of the NGNP coupled one or more small hydrogen production pilot plants. However, the chemical plant processes to be coupled to the NGNP have not yet been chosen; thus, a broad PIRT assessment was conducted to scope alternative potential applications and test facilities associated with the NGNP. The hazards associated with various chemicals and methods to minimize risks from those hazards are well understood within the chemical industry. Much but not all of the information required to assure safe conditions (separation distance, relative elevation, berms) is known for a reactor coupled to a chemical plant. There is also some experience with nuclear plants in several countries that have produced steam for industrial applications. The specific characteristics of the chemical plant, site layout, and the maximum stored inventories of chemicals can provide the starting point for the safety assessments. While the panel identified events and phenomena of safety significance, there is one added caveat. Multiple high-temperature reactors provide safety-related experience and understanding of reactor safety. In contrast, there have been only limited safety studies of coupled chemical and nuclear plants. The work herein provides a starting point for those studies; but, the general level of understanding of safety in coupling nuclear and chemical plants is less than in other areas of high-temperature reactor safety.

Forsberg, Charles W [ORNL; Gorensek, M. B. [Savannah River National Laboratory (SRNL); Herring, S. [Idaho National Laboratory (INL); Pickard, P. [Sandia National Laboratories (SNL)

2008-03-01T23:59:59.000Z

151

Co-Generation at a Practical Plant Level  

E-Print Network (OSTI)

The Steam Turbine: A basic description of how a steam turbine converts available heat into mechanical energy to define the formulae used for the cost comparisons in the subsequent examples. Co-Generation: Comparison between condensing cycle and back pressure turbine exhausting to useful process, identifies potential energy savings. Process Power Recovery: Replacing pressure reducing valve with steam turbine produces mechanical or electrical energy in conjunction with process heat. Steam vs. Electric Motor: Comparison of electric motor operating cost with steam turbines to show that cost-savings depend on application. Waste Heat Recovery: The addition of a steam turbine can justify waste heat projects that were previously not feasible on an economic basis.

Feuell, J.

1980-01-01T23:59:59.000Z

152

User's Guide for RIVRISK Version 5.0: A Model to Assess Potential Human Health and Ecological Risks from Power Plant and Industrial Facility Releases to Rivers  

Science Conference Proceedings (OSTI)

This is a user's guide to EPRI's RIVRISK framework, Version 5.0, which can be used to assess human health and ecological risks associated with industrial and power plant chemical and thermal releases to rivers. The report also documents RIVRISK's theoretical foundation and graphical user interface. Industrial and government staff concerned with chemical and thermal releases will find this report useful.

2000-11-29T23:59:59.000Z

153

MHK Technologies/The Ocean Hydro Electricity Generator Plant | Open Energy  

Open Energy Info (EERE)

MHK Technologies/The Ocean Hydro Electricity Generator Plant MHK Technologies/The Ocean Hydro Electricity Generator Plant < MHK Technologies Jump to: navigation, search << Return to the MHK database homepage The Ocean Hydro Electricity Generator Plant.jpg Technology Profile Primary Organization Free Flow 69 Technology Resource Click here Current Technology Type Click here Axial Flow Turbine Technology Readiness Level Click here TRL 1 3 Discovery Concept Def Early Stage Dev Design Engineering Technology Description The O H E G plant is a revolutionary concept using tidal energy designed by FreeFlow 69 The plant uses tidal energy to create electricity 24 hours a day making this a unique project 24 hour power is produced by using both the kinetic energy in tidal flow and the potential energy created by tidal height changes The O H E G plant is completely independent of the wind farm however it does make an ideal foundation for offshore wind turbines combining both tidal energy and wind energy The O H E G plant is not detrimental to the surrounding environment or ecosystem and due to its offshore location it will not be visually offensive

154

NETL: News Release - Coal Gasification Plant Returns $79 Million to DOE in  

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

2, 2006 2, 2006 Coal Gasification Plant Returns $79 Million to DOE in Revenue-Sharing Gas Sales Plant Currently Supplies Carbon Dioxide for DOE Sequestration Project Washington, DC -A coal gasification plant purchased from the U.S. Department of Energy (DOE) in 1988 recently paid millions of dollars to DOE as part of a revenue sharing agreement and continues to be an integral part of a Department project to sequester millions of tons of carbon dioxide while doubling an oil field's recovery rate. MORE INFO Learn more about the Great Plains Synfuels Plant The Dakota Gasification Company (DGC), which purchased the Great Plains Synfuels Plant near Beulah, N.D., recently announced the payment of more than $79 million to DOE as part of a revenue-sharing agreement signed in

155

Limited Electricity Generation Supply and Limited Natural Gas Supply Cases (released in AEO2008)  

Reports and Publications (EIA)

Development of U.S. energy resources and the permitting and construction of large energy facilities have become increasingly difficult over the past 20 years, and they could become even more difficult in the future. Growing public concern about global warming and CO2 emissions also casts doubt on future consumption of fossil fuelsparticularly coal, which releases the largest amount of CO2 per unit of energy produced. Even without regulations to limit greenhouse gas emissions in the United States, the investment community may already be limiting the future use of some energy options. In addition, there is considerable uncertainty about the future availability of, and access to, both domestic and foreign natural gas resources.

Information Center

2008-06-26T23:59:59.000Z

156

National Lab Helping to Train Operators for Next Generation of Power Plants  

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

National Lab Helping to Train Operators for Next Generation of National Lab Helping to Train Operators for Next Generation of Power Plants National Lab Helping to Train Operators for Next Generation of Power Plants January 25, 2013 - 11:10am Addthis AVESTAR provides high-quality, hands-on, simulator-based workforce training delivered by an experienced team of power industry training professionals for West Virginia students. | Photo courtesy of the Office of Fossil Energy. AVESTAR provides high-quality, hands-on, simulator-based workforce training delivered by an experienced team of power industry training professionals for West Virginia students. | Photo courtesy of the Office of Fossil Energy. Gayland Barksdale Technical Writer, Office of Fossil Energy What Does AVESTAR Provide? Advanced dynamic simulation, control and virtual plant technologies

157

National Lab Helping to Train Operators for Next Generation of Power Plants  

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

Lab Helping to Train Operators for Next Generation of Lab Helping to Train Operators for Next Generation of Power Plants National Lab Helping to Train Operators for Next Generation of Power Plants January 25, 2013 - 11:10am Addthis AVESTAR provides high-quality, hands-on, simulator-based workforce training delivered by an experienced team of power industry training professionals for West Virginia students. | Photo courtesy of the Office of Fossil Energy. AVESTAR provides high-quality, hands-on, simulator-based workforce training delivered by an experienced team of power industry training professionals for West Virginia students. | Photo courtesy of the Office of Fossil Energy. Gayland Barksdale Technical Writer, Office of Fossil Energy What Does AVESTAR Provide? Advanced dynamic simulation, control and virtual plant technologies

158

The importance of combined cycle generating plants in integrating large levels of wind power generation  

Science Conference Proceedings (OSTI)

Integration of high wind penetration levels will require fast-ramping combined cycle and steam cycles that, due to higher operating costs, will require proper pricing of ancillary services or other forms of compensation to remain viable. Several technical and policy recommendations are presented to help realign the generation mix to properly integrate the wind. (author)

Puga, J. Nicolas

2010-08-15T23:59:59.000Z

159

Destructive Examination of Tube R31C66 From the Ginna Nuclear Plant Steam Generator  

Science Conference Proceedings (OSTI)

Like some other PWR steam generators, the Ginna plant has experienced loss of steam pressure for several years. Deposits of up to 8 mils thick have been found and may explain the steam pressure loss. In addition, destructive and nondestructive examinations found a through-wall crack in the roll transition of a hot leg tube removed from this plant as well as shallow intergranular attack (IGA) in the tubesheet crevice region.

1991-07-01T23:59:59.000Z

160

NETL: News Release - New Mexico Coal-Fired Power Plant to Demonstrate...  

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

October 14, 2004 New Mexico Coal-Fired Power Plant to Demonstrate Multi-Pollutant Controls Project Will Help Meet President's Commitment to Clean Coal and Address National Energy...

Note: This page contains sample records for the topic "generating plants release" 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

Next Generation Nuclear Plant Intermediate Heat Exchanger Materials Research and Development Plan (PLN-2804)  

Science Conference Proceedings (OSTI)

DOE has selected the High Temperature Gas-cooled Reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production. It will have an outlet gas temperature in the range of 900°C and a plant design service life of 60 years. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed reactor and use low-enriched uranium, Tri-Isotopic (TRISO)-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. Today’s high-temperature alloys and associated ASME Codes for reactor applications are approved up to 760°C. However, some primary system components, such as the Intermediate Heat Exchanger (IHX) for the NGNP will require use of materials that can withstand higher temperatures. The thermal, environmental, and service life conditions of the NGNP will make selection and qualification of some high-temperature materials a significant challenge. Examples include materials for the core barrel and core internals, such as the control rod sleeves. The requirements of the materials for the IHX are among the most demanding. Selection of the technology and design configuration for the NGNP must consider both the cost and risk profiles to ensure that the demonstration plant establishes a sound foundation for future commercial deployments. The NGNP challenge is to achieve a significant advancement in nuclear technology while at the same time setting the stage for an economically viable deployment of the new technology in the commercial sector soon after 2020. A number of solid solution strengthened nickel based alloys have been considered for application in heat exchangers and core internals for the NGNP. The primary candidates are Inconel 617, Haynes 230, Incoloy 800H and Hastelloy XR. Based on the technical maturity, availability in required product forms, experience base, and high temperature mechanical properties all of the vendor pre-conceptual design studies have specified Alloy 617 as the material of choice for heat exchangers. Also a draft code case for Alloy 617 was developed previously. Although action was suspended before the code case was accepted by ASME, this draft code case provides a significant head start for achieving codification of the material. Similarly, Alloy 800H is the material of choice for control rod sleeves. In addition to the above listed considerations, Alloy 800H is already listed in the nuclear section of the ASME Code; although the maximum use temperature and time need to be increased.

J. K. Wright

2008-04-01T23:59:59.000Z

162

Tracking new coal-fired power plants: coal's resurgence in electric power generation  

Science Conference Proceedings (OSTI)

This information package is intended to provide an overview of 'Coal's resurgence in electric power generation' by examining proposed new coal-fired power plants that are under consideration in the USA. The results contained in this package are derived from information that is available from various tracking organizations and news groups. Although comprehensive, this information is not intended to represent every possible plant under consideration but is intended to illustrate the large potential that exists for new coal-fired power plants. It should be noted that many of the proposed plants are likely not to be built. For example, out of a total portfolio (gas, coal, etc.) of 500 GW of newly planned power plant capacity announced in 2001, 91 GW have been already been scrapped or delayed. 25 refs.

NONE

2007-05-01T23:59:59.000Z

163

Turbine-Generator Topics for Power Plant Engineers: Synchronous Generator Voltage Regulator Basics  

Science Conference Proceedings (OSTI)

This material is intended for the new engineer, the control room operator, management, or the non-engineer. The basics of a synchronous generator excitation system; the fundamentals of the voltage regulator; and its controls and functions are discussed. The typical exciter types are covered, but not in detail. There is also basic information on voltage regulator maintenance issues. Put simply, the excitation system is made up of three basic component systems. The voltage regulator monitors the synchronou...

2012-02-16T23:59:59.000Z

164

CONCEPTUAL DESIGN AND ECONOMICS OF A NOMINAL 500 MWe SECOND-GENERATION PFB COMBUSTION PLANT  

SciTech Connect

Research has been conducted under United States Department of Energy Contract DE-AC21-86MC21023 to develop a new type of coal-fired plant for electric power generation. This new type of plant, called a Second Generation Pressurized Fluidized Bed Combustion Plant (2nd Gen PFB), offers the promise of efficiencies greater than 48 percent, with both emissions and a cost of electricity that are significantly lower than those of conventional pulverized coal-fired (PC) plants with wet flue gas desulfurization. The 2nd Gen PFB plant incorporates the partial gasification of coal in a carbonizer, the combustion of carbonizer char in a pressurized circulating fluidized bed boiler, and the combustion of carbonizer syngas in a gas turbine combustor to achieve gas turbine inlet temperatures of 2300 F and higher. A conceptual design and an economic analysis was previously prepared for this plant. When operating with a Siemens Westinghouse W501F gas turbine, a 2400psig/1000 F/1000 F/2-1/2 in. Hg. steam turbine, and projected carbonizer, PCFB, and topping combustor performance data, the plant generated 496 MWe of power with an efficiency of 44.9 percent (coal higher heating value basis) and a cost of electricity 22 percent less than a comparable PC plant. The key components of this new type of plant have been successfully tested at the pilot plant stage and their performance has been found to be better than previously assumed. As a result, the referenced conceptual design has been updated herein to reflect more accurate performance predictions together with the use of the more advanced Siemens Westinghouse W501G gas turbine. The use of this advanced gas turbine, together with a conventional 2400 psig/1050 F/1050 F/2-1/2 in. Hg. steam turbine increases the plant efficiency to 48.2 percent and yields a total plant cost of $1,079/KW (January 2002 dollars). The cost of electricity is 40.7 mills/kWh, a value 12 percent less than a comparable PC plant.

A. Robertson; H. Goldstein; D. Horazak; R. Newby

2003-09-01T23:59:59.000Z

165

Population dose commitments due to radioactive releases from nuclear power plant sites in 1987  

Science Conference Proceedings (OSTI)

Population radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1987. Fifty-year dose commitments for a one-year exposure from both liquid and atmospheric releases were calculated for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each of 70 reactor sites. This report tabulates the results of these calculations, showing the dose commitments for both water and airborne pathways for each age group and organ. Also included for reach of the sites is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The site average individual dose commitment from all pathways ranged from a low of 2 {times} 10{sup {minus}6} mrem to a high of 0.009 mrem. No attempt was made in this study to determine the maximum dose commitment received by any one individual from the radionuclides released at any of the sites. However, licensee calculation of doses to the maximally exposed individual at some sites indicated values of up to approximately 100 times average individual doses (on the order of a few millirem per year). 2 refs., 2 figs., 7 tabs.

Baker, D.A. (Pacific Northwest Lab., Richland, WA (USA))

1990-08-01T23:59:59.000Z

166

Turbine-Generator Topics for Power Plant Engineers: Fundamentals of Electromagnetic Signature Analysis  

Science Conference Proceedings (OSTI)

Electromagnetic signature analysis (EMSA) is the process used to evaluate the electromagnetic interference (EMI) generated by abnormalities in almost any energized power plant equipment—from cable connections to broken rotor bars in a motor to the isolated phase bus and generator step-up transformer. EMSA will detect any defect that involves EMI, noise, arcing, corona, partial discharge, gap discharge, sparking or microsparking, or any combination of these.With EMSA, every signal ...

2013-02-15T23:59:59.000Z

167

Steam Generator Tube Integrity Risk Assessment: Volume 2: Application to Diablo Canyon Power Plant  

Science Conference Proceedings (OSTI)

Damage to steam generator tubing can impair its ability to adequately perform the required safety functions in terms of structural stability and leakage. This report describes the Diablo Canyon Power Plant application of a method for calculating risk for severe accidents involving steam generator tube failure. The method helps utilities determine risks associated with application of alternate repair criteria and/or operation with degraded tubing.

2000-08-08T23:59:59.000Z

168

Steam Generator Management Program: Applicability of EDF's Steam Generator Blockage Ratio Estimation Method to Plant Shutdown Transients  

Science Conference Proceedings (OSTI)

Electricité de France (EDF) has developed a technique that it uses to estimate the level of deposit buildup on steam generator tube support plates at its pressurized water reactor (PWR) units in France. The technique could potentially be of use to other PWR operators, but it needs to be carefully evaluated to determine what adaptations would be necessary to enable it to be used accurately at other plants. This report documents work undertaken by the Electric Power Research Institute (EPRI) and EDF to det...

2012-02-16T23:59:59.000Z

169

Next Generation Nuclear Plant Structures, Systems, and Components Safety Classification White Paper  

SciTech Connect

This white paper outlines the relevant regulatory policy and guidance for a risk-informed approach for establishing the safety classification of Structures, Systems, and Components (SSCs) for the Next Generation Nuclear Plant and sets forth certain facts for review and discussion in order facilitate an effective submittal leading to an NGNP Combined Operating License application under 10 CFR 52.

Pete Jordan

2010-09-01T23:59:59.000Z

170

Design Features and Technology Uncertainties for the Next Generation Nuclear Plant  

Science Conference Proceedings (OSTI)

This report presents the conclusions, observations, and recommendations of the Independent Technology Review Group (ITRG) regarding design features and important technology uncertainties associated with very-high-temperature nuclear system concepts for the Next Generation Nuclear Plant (NGNP). The ITRG performed its reviews during the period November 2003 through April 2004.

John M. Ryskamp; Phil Hildebrandt; Osamu Baba; Ron Ballinger; Robert Brodsky; Hans-Wolfgang Chi; Dennis Crutchfield; Herb Estrada; Jeane-Claude Garnier; Gerald Gordon; Richard Hobbins; Dan Keuter; Marilyn Kray; Philippe Martin; Steve Melancon; Christian Simon; Henry Stone; Robert Varrin; Werner von Lensa

2004-06-01T23:59:59.000Z

171

Martin Next Generation Solar Energy Center Solar Power Plant | Open Energy  

Open Energy Info (EERE)

Center Solar Power Plant Center Solar Power Plant Jump to: navigation, search Name Martin Next Generation Solar Energy Center Solar Power Plant Facility Martin Next Generation Solar Energy Center Sector Solar Facility Type Concentrating Solar Power Facility Status In Service Developer FPL Energy Location Martin County, Florida Coordinates 27.051214°, -80.553389° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":27.051214,"lon":-80.553389,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

172

Population dose commitments due to radioactive releases from nuclear power plant sites in 1980  

Science Conference Proceedings (OSTI)

Population radiation dose commitments have been estimated from reported radionuclide releases from commercial power reactors operating during 1980. In addition doses derived from the shutdown reactors at the Three Mile Island site were included. Fifty-year dose commitments from a one-year exposure were calculated from both liquid and atmospheric releases for four population groups (infant, child, teen-ager and adult) residing between 2 and 80 km from each site. This report tabulates the results of these calculations, showing the dose commitments for both liquid and airborne pathways for each age group and organ. Also included for each site is a histogram showing the fraction of the total population within 2 to 80 km around each site receiving various average dose commitments from the airborne pathways. The total dose commitment from both liquid and airborne pathways ranged from a high of 40 person-rem to a low of 0.02 person-rem with an arithmetic mean of 4 person-rem. The total population dose for all sites was estimated at 180 person-rem for the 96 million people considered at risk.

Baker, D.A.; Peloquin, R.A.

1983-08-01T23:59:59.000Z

173

NETL: News Release - DOE-Funded Innovation Promotes Reduced Coal Plant  

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

21, 2007 21, 2007 DOE-Funded Innovation Promotes Reduced Coal Plant Emissions Novel Catalyst System Bolsters NOx Control Washington, DC - A catalyst-activity testing tool developed with funding from the U.S. Department of Energy is now commercially available and offers a major breakthrough in managing the selective catalytic reduction systems that are used in power plants to control nitrogen oxides (NOx) emissions. The much-needed innovation will promote both cleaner air and cost savings for electric customers by helping plant operators to more cost-effectively comply with NOx emissions regulations, including the new Clean Air Interstate Rule. Most of America's energy systems rely on combustion processes. A drawback of combustion is the formation of NOx - a group of highly reactive gases that form when fuel is burned at high temperatures and which contribute to smog, acid rain, and global warming. Selective catalytic reduction (SCR) systems control NOx emissions by injecting ammonia or urea into flue gas in the presence of a catalyst, converting NOx into nitrogen and water.

174

Hanford Waste Vitrification Plant hydrogen generation study: Formation of ammonia from nitrate and nitrate in hydrogen generating systems  

DOE Green Energy (OSTI)

The Hanford Waste Vitrification Plant (HWVP) is being designed for the Departrnent of Energy (DOE) to immobilize pretreated highly radioactive wastes in glass for permanent disposal in the HWVP, formic acid is added to the waste before vitrification to adjust glass redox and melter feed rheology. The operation of the glass melter and durability of the glass are affected by the glass oxidation state. Formation of a conductive metallic sludge in an over-reduced melt can result in a shortened melter lifetime. An over-oxidized melt may lead to foaming and loss of ruthenium as volatile RuO{sub 4}. Historically, foaming in the joule heated ceramic melter has been attributed to gas generation in the melt which is controlled by instruction of a reductant such as formic acid into the melter feed. Formic acid is also found to decrease the melter feed viscosity thereby facilitating pumping. This technical report discusses the noble metal catalyzed formic acid reduction of nitrite and/or nitrate to ammonia, a problem of considerable concern because of the generation of a potential ammonium nitrate explosion hazard in the plant ventilation system.

King, R.B.; Bhattacharyya, N.K.

1996-02-01T23:59:59.000Z

175

Design Option of Heat Exchanger for the Next Generation Nuclear Plant  

DOE Green Energy (OSTI)

The Next Generation Nuclear Plant (NGNP), a very High temperature Gas-Cooled Reactor (VHTGRS) concept, will provide the first demonstration of a closed-loop Brayton cycle at a commercial scale of a few hundred megawatts electric and hydrogen production. The power conversion system (PCS) for the NGNP will take advantage of the significantly higher reactor outlet temperatures of the VHTGRS to provide higher efficiencies than can be achieved in the current generation of light water reactors. Besides demonstrating a system design that can be used directly for subsequent commercial deployment, the NGNP will demonstrate key technology elements that can be used in subsequent advanced power conversion systems for other Generation IV reactors. In anticipation of the design, development and procurement of an advanced power conversion system for the NGNP, the system integration of the NGNP and hydrogen plant was initiated to identify the important design and technology options that must be considered in evaluating the performance of the proposed NGNP. As part of the system integration of the VHTGRS and hydrogen production plant, the intermediate heat exchanger is used to transfer the process heat from VHTGRS to hydrogen plant. Therefore, the design and configuration of the intermediate heat exchanger are very important. This paper will include analysis of one stage versus two stage heat exchanger design configurations and thermal stress analyses of a printed circuit heat exchanger, helical coil heat exchanger, and shell/tube heat exchanger.

Eung Soo Kim; Chang Oh

2008-09-01T23:59:59.000Z

176

Cooldown control system for a combined cycle electrical power generation plant  

SciTech Connect

This patent describes a combined cycle electrical power plant including a steam turbine, a heat recovery steam generator for supplying steam to the steam turbine, a gas turbine for supplying heat to the heat recovery steam generator. The steam generator and gas turbine both produce electrical power under load, and the gas turbine has a control circuit determining the operation therof. A cooldown control system is described for the power generation plant. The system comprises: first means for detecting one of a steaming condition and a non-steaming condition in the heat recovery steam generator; second means responsive to the steaming condition and to a gas turbine STOP signal for reducing the load of the gas turbine toward a minimum load level; third means responsive to the non-steaming condition and to the minimum load level being reached for generating a STOP command and applying the STOP command to the control circuit of the gas turbine, thereby to indicate a sequence of steps to stop the gas turbine.

Martens, A.; Snow, B.E.

1987-01-27T23:59:59.000Z

177

Space Coast Next Generation Solar Energy Center Solar Power Plant | Open  

Open Energy Info (EERE)

Space Coast Next Generation Solar Energy Center Solar Power Plant Space Coast Next Generation Solar Energy Center Solar Power Plant Jump to: navigation, search Name Space Coast Next Generation Solar Energy Center Solar Power Plant Facility Space Coast Next Generation Solar Energy Center Sector Solar Facility Type Photovoltaic Developer FPL Energy Location Orlando, Florida Coordinates 28.5383355°, -81.3792365° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":28.5383355,"lon":-81.3792365,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

178

DeSoto Next Generation Solar Energy Center Solar Power Plant | Open Energy  

Open Energy Info (EERE)

Next Generation Solar Energy Center Solar Power Plant Next Generation Solar Energy Center Solar Power Plant Jump to: navigation, search Name DeSoto Next Generation Solar Energy Center Solar Power Plant Facility DeSoto Next Generation Solar Energy Center Sector Solar Facility Type Photovoltaic Developer FPL Energy Location DeSoto County, Florida Coordinates 27.2142078°, -81.7787021° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":27.2142078,"lon":-81.7787021,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

179

Heat recovery steam generator outlet temperature control system for a combined cycle power plant  

Science Conference Proceedings (OSTI)

This patent describes a command cycle electrical power plant including: a steam turbine and at least one set comprising a gas turbine, an afterburner and a heat recovery steam generator having an attemperator for supplying from an outlet thereof to the steam turbine superheated steam under steam turbine operating conditions requiring predetermined superheated steam temperature, flow and pressure; with the gas turbine and steam turbine each generating megawatts in accordance with a plant load demand; master control means being provided for controlling the steam turbine and the heat recovery steam generator so as to establish the steam operating conditions; the combination of: first control means responsive to the gas inlet temperature of the heat recovery steam generator and to the plant load demand for controlling the firing of the afterburner; second control means responsive to the superheated steam predetermined temperature and to superheated steam temperature from the outlet for controlling the attemperator between a closed and an open position; the first and second control means being operated concurrently to maintain the superheated steam outlet temperature while controlling the load of the gas turbine independently of the steam turbine operating conditions.

Martens, A.; Myers, G.A.; McCarty, W.L.; Wescott, K.R.

1986-04-01T23:59:59.000Z

180

NETL 2003 Releases  

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

3 Releases 3 Releases News Releases issued in: 2011 | 2010 | 2009 | 2008 | 2007 | 2006 | 2005 | 2004 | 2003 | 2002 | 2001 | 2000 December 30, 2003 Advanced Natural Gas Turbine Hailed as Top Power Project of 2003 A power plant featuring a next-generation gas turbine developed as part of DOE's advanced turbine systems program has been selected by Power Engineering magazine as one of three 2003 Projects of the Year. December 8, 2003 Historically Black, Other Minority Colleges Encouraged to Compete for Grants for Fossil Energy Research DOE has issued its annual call for fossil fuel research proposals from historically black and other minority colleges and universities. December 5, 2003 Massachusetts Institute of Technology Professor is 2003 Lowry Award Winner The Energy Department's 2003 Homer H. Lowry Award will go to a Massachusetts Institute of Technology professor emeritus whose combustion research continues to influence the design and commercialization of cleaner, 'low NOx' combustors widely used in the power industry.

Note: This page contains sample records for the topic "generating plants release" 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

Preliminary analysis of two aspects of magma-powered electric-generation plants  

DOE Green Energy (OSTI)

Two aspects critical to the development of magma electric generation plants using closed heat exchanger systems are addressed. The heat transfer between the cold fluid in the downcomer and the hot fluid in the upcomer is analyzed using an NTU-effectiveness technique. The results indicate the hot fluid must be thermally insulated from the colder fluid in order to yield a useful temperature difference at the surface. A preliminary system analysis is conducted to determine the well cost requirements of an economically competitive magma electric plant. There is no economic incentive to make the magma tap wellbore larger than conventional deep gas wells. The cost competitiveness of a magma/electric plant is influenced by the depth to the magma, the convective heat flux of the magma, and the expected life of each well.

Hoover, E.R.

1980-09-01T23:59:59.000Z

182

Flexible Operation of Current and Next-Generation Coal Plants, With and Without Carbon Capture  

Science Conference Proceedings (OSTI)

Based on input from research sponsored by the Electric Power Research Institute (EPRI), and other respected industry sources, this report aims to initially highlight the implications for existing pulverized coal (PC) plants when they are required to operate frequently under changing load conditions. The report presents design improvements to enable more flexible operation of the current and next generation coal fleet. It also discusses the implications on operation flexibility of both new and ...

2013-12-31T23:59:59.000Z

183

CFCC Development Program: commercial plant stacked combustor/steam generator design evaluation (Task 2. 1)  

SciTech Connect

The Coal Fired Combined Cycle (CFCC) is the unique power plant concept developed under the leadership of the General Electric Company to provide a direct coal-burning gas turbine and steam turbine combined cycle power plant. The advantages of the combined cycle for higher efficiency and the potential of the pressurized fluidized bed (PFB) combustor for improvements in emissions could offer a new and attractive option to the electric utility industry after its successful development. The CFCC approach provides cooling of the fluid bed combustor through the use of steam tubes in the bed, which supply a steam turbine-generator. The partially cooled combustion gases exiting from the combustor drive a gas turbine-generator after passing through a hot-gas cleanup train. On the basis of previous studies and confirming work under this contract, General Electric continues to believe that the CFCC approach offers these important advantages over alternate approaches: higher power plant efficiency in the combustor temperature range of interest; reduced combustor/steam generator corrosion potential, due to low fluid-bed tube temperature (as contrasted to the air in tube cycle); reduced hot-gas cleanup flow rate (as contrasted with the uncooled combustor cycle); and increased gas turbine bucket life through use of corrosion resistant material protection systems.

1978-06-01T23:59:59.000Z

184

Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents  

Science Conference Proceedings (OSTI)

Nuclear power plants report the amount of radioactivity released through permitted effluent pathways in their plant annual reports. This report provides users with a method for calculating the amount of carbon-14 (14C) generated in a light water reactor (LWR) core and released through plant gaseous effluent pathways.

2010-12-21T23:59:59.000Z

185

A Systems Engineering Framework for Design, Construction and Operation of the Next Generation Nuclear Plant  

DOE Green Energy (OSTI)

Not since the International Space Station has a project of such wide participation been proposed for the United States. Ten countries, the European Union, universities, Department of Energy (DOE) laboratories, and industry will participate in the research and development, design, construction and/or operation of the fourth generation of nuclear power plants with a demonstration reactor to be built at a DOE site and operational by the middle of the next decade. This reactor will be like no other. The Next Generation Nuclear Plant (NGNP) will be passively safe, economical, highly efficient, modular, proliferation resistant, and sustainable. In addition to electrical generation, the NGNP will demonstrate efficient and cost effective generation of hydrogen to support the President’s Hydrogen Initiative. To effectively manage this multi-organizational and technologically complex project, systems engineering techniques and processes will be used extensively to ensure delivery of the final product. The technological and organizational challenges are complex. Research and development activities are required, material standards require development, hydrogen production, storage and infrastructure requirements are not well developed, and the Nuclear Regulatory Commission may further define risk-informed/performance-based approach to licensing. Detailed design and development will be challenged by the vast cultural and institutional differences across the participants. Systems engineering processes must bring the technological and organizational complexity together to ensure successful product delivery. This paper will define the framework for application of systems engineering to this $1.5B - $1.9B project.

Edward J. Gorski; Charles V. Park; Finis H. Southworth

2004-06-01T23:59:59.000Z

186

An approach to estimating radiological risk of offsite release from a design basis earthquake for the Process Experimental Pilot Plant (PREPP)  

SciTech Connect

In compliance with Department of Energy (DOE) Order 6430.1A, a seismic analysis was performed on DOE's Process Experimental Pilot Plant (PREPP), a facility for processing low-level and transuranic (TRU) waste. Because no hazard curves were available for the Idaho National Engineering Laboratory (INEL), DOE guidelines were used to estimate the frequency for the specified design-basis earthquake (DBE). A dynamic structural analysis of the building was performed, using the DBE parameters, followed by a probabilistic risk assessment (PRA). For the PRA, a functional organization of the facility equipment was effected so that top events for a representative event tree model could be determined. Building response spectra (calculated from the structural analysis), in conjunction with generic fragility data, were used to generate fragility curves for the PREPP equipment. Using these curves, failure probabilities for each top event were calculated. These probabilities were integrated into the event tree model, and accident sequences and respective probabilities were calculated through quantification. By combining the sequences failure probabilities with a transport analysis of the estimated airborne source term from a DBE, onsite and offsite consequences were calculated. The results of the comprehensive analysis substantiated the ability of the PREPP facility to withstand a DBE with negligible consequence (i.e., estimated release was within personnel and environmental dose guidelines). 57 refs., 19 figs., 20 tabs.

Lucero, V.; Meale, B.M.; Reny, D.A.; Brown, A.N.

1990-09-01T23:59:59.000Z

187

Recommended practice for fire protection for electric generating plants and high voltage direct current converter stations. 2005 ed.  

Science Conference Proceedings (OSTI)

The standard outlines fire safety recommendations for gas, oil, coal, and alternative fuel electric generating plants including high voltage direct current converter stations and combustion turbine units greater than 7500 hp used for electric generation. Provisions apply to both new and existing plants. The document provides fire prevention and fire protection recommendations for the: safety of construction and operating personnel; physical integrity of plant components; and continuity of plant operations. The 2005 edition includes revisions and new art that clarify existing provisions. 5 annexes.

NONE

2005-07-01T23:59:59.000Z

188

Solar Pilot Plant, Phase I. Preliminary design report. Volume VI. Electrical power generation; master control subsystems; balance of plant CDRL item 2  

DOE Green Energy (OSTI)

The Honeywell electrical power generation subsystem centers on a General Electric dual admission, triple extraction turbine generator sized to the output requirements of the Pilot Plant. The turbine receives steam from the receiver subsystem and/or the thermal storage subsystem and supplies those subsystems with feedwater. The turbine condensor is wet cooled. The plant control system consists of a coordinated digital master and subsystem digital/analog controls. The remainder of the plant, work spaces, maintenance areas, roads, and reception area are laid out to provide maximum convenience compatible with utility and safety. Most of the activities are housed in a complex around the base of the receiver tower. This volume contains a description of the relationship of the electrical power generation subsystem to the rest of the plant, the design methodology and evolution, the interface integration and control, and the operation and maintenance procedures.

None

1977-05-01T23:59:59.000Z

189

Electrical generation plant design practice intern experience at Power Systems Engineering, Inc.: an internship report  

E-Print Network (OSTI)

A survey of the author's internship experience with Power Systems Engineering, Inc. during the period September 1980 through August, 1981 is presented. During this onr year internship, the author was assigned to two engineering projects. One involved design of a 480 MW power plant. The other was the design of a 8.2 MW induction generator for cogeneration. The author's activities during this period can be categorized into two major areas. First, technically oriented, he designed protective relaying and SCADA systems for the projects. Secondly, he assisted the Project Manager in project management activities such as project progress and cost control. The intent of this report is to prepare a training manual for PSE young engineers. It covers both technical guidelines for power plant design and nonacademic professional codes. Although this report is primarily written for young engineers, it can also be used as a reference by older and experienced engineers.

Lee, Ting-Zern Joe, 1950-

1981-12-01T23:59:59.000Z

190

Recovery Act: Johnston Rhode Island Combined Cycle Electric Generating Plant Fueled by Waste Landfill Gas  

SciTech Connect

The primary objective of the Project was to maximize the productive use of the substantial quantities of waste landfill gas generated and collected at the Central Landfill in Johnston, Rhode Island. An extensive analysis was conducted and it was determined that utilization of the waste gas for power generation in a combustion turbine combined cycle facility was the highest and best use. The resulting project reflected a cost effective balance of the following specific sub-objectives. 1) Meet environmental and regulatory requirements, particularly the compliance obligations imposed on the landfill to collect, process and destroy landfill gas. 2) Utilize proven and reliable technology and equipment. 3) Maximize electrical efficiency. 4) Maximize electric generating capacity, consistent with the anticipated quantities of landfill gas generated and collected at the Central Landfill. 5) Maximize equipment uptime. 6) Minimize water consumption. 7) Minimize post-combustion emissions. To achieve the Project Objective the project consisted of several components. 1) The landfill gas collection system was modified and upgraded. 2) A State-of-the Art gas clean up and compression facility was constructed. 3) A high pressure pipeline was constructed to convey cleaned landfill gas from the clean-up and compression facility to the power plant. 4) A combined cycle electric generating facility was constructed consisting of combustion turbine generator sets, heat recovery steam generators and a steam turbine. 5) The voltage of the electricity produced was increased at a newly constructed transformer/substation and the electricity was delivered to the local transmission system. The Project produced a myriad of beneficial impacts. 1) The Project created 453 FTE construction and manufacturing jobs and 25 FTE permanent jobs associated with the operation and maintenance of the plant and equipment. 2) By combining state-of-the-art gas clean up systems with post combustion emissions control systems, the Project established new national standards for best available control technology (BACT). 3) The Project will annually produce 365,292 MWh?s of clean energy. 4) By destroying the methane in the landfill gas, the Project will generate CO{sub 2} equivalent reductions of 164,938 tons annually. The completed facility produces 28.3 MWnet and operates 24 hours a day, seven days a week.

Galowitz, Stephen

2013-06-30T23:59:59.000Z

191

Deaerator pressure control system for a combined cycle steam generator power plant  

Science Conference Proceedings (OSTI)

In a combined cycle steam generation power plant, until steam extraction can be used to reheat the deaerator, the economizer and/or the pegging recirculation are controlled so as to track the pressure upwards of the autocirculation reheater from the low pressure evaporator with a certain lag in pressure, and to establish pressure in the deaerator on the decreasing trend of the autocirculation reheater at a slower rate and without lowering below a minimum pressure so as to prevent the occurrence of bubbling and cavitation effect.

Martens, A.; Myers, G. A.

1985-12-03T23:59:59.000Z

192

Microbial Gas Generation Under Expected Waste Isolation Pilot Plant Repository Conditions: Final Report  

Science Conference Proceedings (OSTI)

Gas generation from the microbial degradation of the organic constituents of transuranic (TRU) waste under conditions expected in the Waste Isolation Pilot Plant (WIPP) was investigated. The biodegradation of mixed cellulosic materials and electron-beam irradiated plastic and rubber materials (polyethylene, polyvinylchloride, hypalon, leaded hypalon, and neoprene) was examined. We evaluated the effects of environmental variables such as initial atmosphere (air or nitrogen), water content (humid ({approx}70% relative humidity, RH) and brine inundated), and nutrient amendments (nitogen phosphate, yeast extract, and excess nitrate) on microbial gas generation. Total gas production was determined by pressure measurement and carbon dioxide (CO{sub 2}) and methane (CH{sub 4}) were analyzed by gas chromatography; cellulose degradation products in solution were analyzed by high-performance liquid chromatography. Microbial populations in the samples were determined by direct microscopy and molecular analysis. The results of this work are summarized.

Gillow, J.B.; Francis, A.

2011-07-01T23:59:59.000Z

193

Generator loss of field; Experience and studies for AEP's Rockport Plant  

SciTech Connect

This paper describes the performance of American Electric Power (AEP) Company's remotely-located 2600 MW Rockport Plant after loss of field (LOF) disturbances to one of its 1300 MW cross-compound units. Loss of field conditions occur rarely, but the resultant high currents and pulsating torques can damage a turbine-generator, and the electrical system near the disturbance will be impacted by abnormal levels or cyclic swings of power, VArs, and voltages. Rockport LOF computer simulations were conducted with recently developed detailed models; the level of detail was suggested by analyses of recent LOF experience at AEP and by recent developments in generator and excitation system modeling. Simulation results are presented to illustrate the torques, current levels, voltages, speeds, and potential relay actions following loss of field.

Rana, R.D.; Schulz, R.P. (Bulk Transmission Planning Div., American Electric Power Service Corp., Columbus, OH (US))

1989-01-01T23:59:59.000Z

194

Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) Volume 1: Main Report  

DOE Green Energy (OSTI)

A phenomena identification and ranking table (PIRT) process was conducted for the Next Generation Nuclear Plant (NGNP) design. This design (in the conceptual stage) is a modular high-temperature gas-cooled reactor (HTGR) that generates both electricity and process heat for hydrogen production. Expert panels identified safety-relevant phenomena, ranked their importance, and assessed the knowledge levels in the areas of accidents and thermal fluids, fission-product transport and dose, high-temperature materials, graphite, and process heat for hydrogen production. This main report summarizes and documents the process and scope of the reviews, noting the major activities and conclusions. The identified phenomena, analyses, rationales, and associated ratings of the phenomena, plus a summary of each panel's findings, are presented. Individual panel reports for these areas are provided as attached volumes to this main report and provide considerably more detail about each panel's deliberations as well as a more complete listing of the phenomena that were evaluated.

Ball, Sydney J [ORNL

2008-03-01T23:59:59.000Z

195

Carbon dioxide release from ocean thermal energy conversion (OTEC) cycles  

DOE Green Energy (OSTI)

This paper presents the results of recent measurements of CO{sub 2} release from an open-cycle ocean thermal energy conversion (OTEC) experiment. Based on these data, the rate of short-term CO{sub 2} release from future open-cycle OTEC plants is projected to be 15 to 25 times smaller than that from fossil-fueled electric power plants. OTEC system that incorporate subsurface mixed discharge are expected to result in no long-term release. OTEC plants can significantly reduce CO{sub 2} emissions when substituted for fossil-fueled power generation. 12 refs., 4 figs., 3 tabs.

Green, H.J. (Solar Energy Research Inst., Golden, CO (USA)); Guenther, P.R. (Scripps Institution of Oceanography, La Jolla, CA (USA))

1990-09-01T23:59:59.000Z

196

Field Examination and Hot Cell Post-Irradiation Examination of Fuel Channels from Monticello Nuclear Generating Plant  

Science Conference Proceedings (OSTI)

On January 20, 2007, Monticello Nuclear Generating Plant observed an unexpected no-settle condition at the 00 position in peripheral cell 42-11. Publication OE24588, "Control Rod Blade did not Move Normally at Monticello Nuclear Generating Plant," documented this event. This report gives field examination results of four symmetric channels including cell 42-11. Researchers sectioned channel coupons from two channels in cell 42-11 and sent them to Vallecitos Nuclear Center (VNC), Sunol, California for mor...

2009-04-22T23:59:59.000Z

197

Proceedings: Ninth International Conference on Cycle Chemistry in Fossil and Combined Cycle Plants with Heat Recovery Steam Generators  

Science Conference Proceedings (OSTI)

Proper selection, application, and optimization of cycle chemistry have long been recognized as integral to ensuring the highest possible levels of component availability and reliability in fossil-fired generating plant units. These proceedings of the Ninth EPRI International Conference on Cycle Chemistry in Fossil Plants address state-of-the-art practices in conventional and combined-cycle plants. The content provides a worldwide perspective on cycle chemistry practices and insight on industry issues an...

2010-01-22T23:59:59.000Z

198

Optimization of disk generator performance for base-load power plant systems applications  

SciTech Connect

Disk generators for use in base-load MHD power plants are examined for both open-cycle and closed-cycle operating modes. The OCD cases are compared with PSPEC results for a linear channel; enthalpy extractions up to 23% with 71% isentropic efficiency are achievable with generator inlet conditions similar to those used in PSPEC, thus confirming that the disk configuration is a viable alternative for base-load power generation. The evaluation of closed-cycle disks includes use of a simplified cycle model. High system efficiencies over a wide range of power levels are obtained for effective Hall coefficients in the range 2.3 to 4.9. Cases with higher turbulence (implying ..beta../sub eff/ less than or equal to 2.4) yield high system efficiencies at power levels of 100 to 500 MW/sub e/. All these CCD cases compare favorably with linear channels reported in the GE ECAS study, yielding higher isentropic efficiences for a given enthalpy extraction. Power densities in the range 70 to 170 MW/m/sup 3/ appear feasible, leading to very compact generator configurations.

Teare, J.D.; Loubsky, W.J.; Lytle, J.K.; Louis, J.F.

1980-01-01T23:59:59.000Z

199

WIPP News Releases  

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

10 News Releases December 1 State Renews WIPP Facility Permit November 18 National TRU Program Director Selected November 18 Waste Isolation Pilot Plant Receives Second EPA...

200

Table 11b. Coal Prices to Electric Generating Plants, Projected vs. Actual  

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

b. Coal Prices to Electric Generating Plants, Projected vs. Actual" b. Coal Prices to Electric Generating Plants, Projected vs. Actual" "Projected Price in Nominal Dollars" " (nominal dollars per million Btu)" ,1993,1994,1995,1996,1997,1998,1999,2000,2001,2002,2003,2004,2005,2006,2007,2008,2009,2010,2011 "AEO 1994",1.502753725,1.549729719,1.64272351,1.727259934,1.784039735,1.822135762,1.923203642,2.00781457,2.134768212,2.217425497,2.303725166,2.407715232,2.46134106,2.637086093,2.775389073,2.902293046,3.120364238,3.298013245 "AEO 1995",,1.4212343,1.462640338,1.488780998,1.545300242,1.585877053,1.619428341,1.668671498,1.7584219,1.803937198,1.890547504,1.968695652,2.048913043,2.134750403,2.205281804,2.281690821,2.375434783,2.504830918 "AEO 1996",,,1.346101641,1.350594221,1.369020126,1.391737646,1.421340737,1.458772082,1.496497523,1.561369914,1.619940033,1.674758358,1.749420803,1.800709877,1.871110564,1.924495246,2.006850327,2.048938234,2.156821499

Note: This page contains sample records for the topic "generating plants release" 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

Table 11a. Coal Prices to Electric Generating Plants, Projected vs. Actual  

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

a. Coal Prices to Electric Generating Plants, Projected vs. Actual a. Coal Prices to Electric Generating Plants, Projected vs. Actual Projected Price in Constant Dollars (constant dollars per million Btu in "dollar year" specific to each AEO) AEO Dollar Year 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 AEO 1994 1992 1.47 1.48 1.53 1.57 1.58 1.57 1.61 1.63 1.68 1.69 1.70 1.72 1.70 1.76 1.79 1.81 1.88 1.92 AEO 1995 1993 1.39 1.39 1.38 1.40 1.40 1.39 1.39 1.42 1.41 1.43 1.44 1.45 1.46 1.46 1.46 1.47 1.50 AEO 1996 1994 1.32 1.29 1.28 1.27 1.26 1.26 1.25 1.27 1.27 1.27 1.28 1.27 1.28 1.27 1.28 1.26 1.28

202

Evaluation of Next Generation Nuclear Power Plant (NGNP) Intermediate Heat Exchanger (IHX) Operating Conditions  

DOE Green Energy (OSTI)

This report summarizes results of a preliminary evaluation to determine the operating conditions for the Next Generation Nuclear Plant (NGNP) Intermediate Heat Exchanger (IHX) that will transfer heat from the reactor primary system to the demonstration hydrogen production plant(s). The Department of Energy is currently investigating two primary options for the production of hydrogen using a high temperature reactor as the power source. These options are the High Temperature Electrolysis (HTE) and Sulfur-Iodine (SI) thermochemical hydrogen production processes. However, since the SI process relies entirely on process heat from the reactor, while the HTE process relies primarily on electrical energy with only a small amount of process heat required, the design of the IHX is dictated by the SI process heat requirements. Therefore, the IHX operating conditions were defined assuming 50 MWt is available for the production of hydrogen using the SI process. Three configurations for the intermediate loop were evaluated, including configurations for both direct and indirect power conversion systems. The HYSYS process analysis software was used to perform sensitivity studies to determine the influence of reactor outlet temperatures, intermediate loop working fluids (helium and molten salt), intermediate loop pressures, and intermediate loop piping lengths on NGNP performance and IHX operating conditions. The evaluation of NGNP performance included assessments of overall electric power conversion efficiency and estimated hydrogen production efficiency. Based on these evaluations, recommended IHX operating conditions are defined.

E. A. Harvego

2006-04-01T23:59:59.000Z

203

Interim Report: Air-Cooled Condensers for Next Generation Geothermal Power Plants Improved Binary Cycle Performance  

DOE Green Energy (OSTI)

As geothermal resources that are more expensive to develop are utilized for power generation, there will be increased incentive to use more efficient power plants. This is expected to be the case with Enhanced Geothermal System (EGS) resources. These resources will likely require wells drilled to depths greater than encountered with hydrothermal resources, and will have the added costs for stimulation to create the subsurface reservoir. It is postulated that plants generating power from these resources will likely utilize the binary cycle technology where heat is rejected sensibly to the ambient. The consumptive use of a portion of the produced geothermal fluid for evaporative heat rejection in the conventional flash-steam conversion cycle is likely to preclude its use with EGS resources. This will be especially true in those areas where there is a high demand for finite supplies of water. Though they have no consumptive use of water, using air-cooling systems for heat rejection has disadvantages. These systems have higher capital costs, reduced power output (heat is rejected at the higher dry-bulb temperature), increased parasitics (fan power), and greater variability in power generation on both a diurnal and annual basis (larger variation in the dry-bulb temperature). This is an interim report for the task ‘Air-Cooled Condensers in Next- Generation Conversion Systems’. The work performed was specifically aimed at a plant that uses commercially available binary cycle technologies with an EGS resource. Concepts were evaluated that have the potential to increase performance, lower cost, or mitigate the adverse effects of off-design operation. The impact on both cost and performance were determined for the concepts considered, and the scenarios identified where a particular concept is best suited. Most, but not all, of the concepts evaluated are associated with the rejection of heat. This report specifically addresses three of the concepts evaluated: the use of recuperation, the use of turbine reheat, and the non-consumptive use of EGS make-up water to supplement heat rejection

Daniel S. Wendt; Greg L. Mines

2010-09-01T23:59:59.000Z

204

Has Restructuring Improved Operating Efficiency at U.S. Electricity Generating Plants?  

E-Print Network (OSTI)

States N Distribution Transmission Generation RestructuringStates N Distribution Transmission Generation Restructuringof generation, transmission, and distribution services, we

Fabrizio, Kira; Rose, Nancy; Wolfram, Catherine

2004-01-01T23:59:59.000Z

205

Numerical simulation of multiconstituent diffusion and helium release characteristics of the /sup 238/PuO/sub 2/ heat source used in radioisotopic thermoelectric generators  

DOE Green Energy (OSTI)

An analytical model is described that was developed to simulate multiconstituent diffusion within a heat source sphere, helium generation within a heat source sphere, and helium release from the surface of a heat source sphere into the surrounding environment. The model represents the first attempt to simulate multiconstituent mass transport using the continuum thermomechanical theory of mixtures and demonstrates that this theory is a viable alternative to irreversible thermodynamics.

McLaughlin, B.D.

1976-05-01T23:59:59.000Z

206

Steam Generator Replacement and Power Up-rating on Tihange 2 Nuclear Plant Safety Study Analyses  

SciTech Connect

The Tihange2 900 MWe 3-L PWR NPP, operated by the Belgian utility Electrabel, was first commissioned in 1982 with a design core power of 2775 MWth. Following an initial core power up-rating by 4,5% in 1995, Electrabel has since replaced the Steam Generators which has allowed a further core power increase by roughly 5% (total 10%) in 2001. For both of each projects, licensing and implementation studies were successfully performed by Tractebel Energy Engineering and Framatome ANP. The demanding new operating conditions required a complete review of the plant design basis for which advanced methods were applied and licensed through a continuous process of discussions with the client and the Belgian Safety Authorities AVN. The licensing process required flexibility in the methods application in order to meet the specific requirements of the S.A., which was achieved within the time schedule and without jeopardising the technical objectives of the utility. (authors)

Malaval, Andre; Marin-Lafleche, Pascale; Forgeot d'Arc, Myriam; Collin, Celine [Framatome ANP (France)

2002-07-01T23:59:59.000Z

207

Conceptual design and optimization of a 1-1/2 generation PFBC plant task 14. Topical report  

SciTech Connect

The economics and performance of advanced pressurized fluidized bed (PFBC) cycles developed for utility applications during the last 10 years (especially the 2nd-Generation PFBC cycle) are projected to be favorable compared to conventional pulverized coal power plants. However, the improved economics of 2nd-Generation PFBC cycles are accompanied by the perception of increased technological risk related to the pressurized carbonizer and its associated gas cleanup systems. A PFBC cycle that removed the uncertainties of the carbonizer while retaining the high efficiency and low cost of a 2nd-Generation PFBC cycle could improve the prospects for early commercialization and pave the way for the introduction of the complete 2nd-Generation PFBC cycle at some later date. One such arrangement is a PFBC cycle with natural gas topping combustion, referred to as the 1.5-Generation PFBC cycle. This cycle combines the advantages of the 2nd-Generation PFBC plant with the reduced risk associated with a gas turbine burning natural gas, and can potentially be part of a phased approach leading to the commercialization of utility 2nd-Generation PFBC cycles. The 1.5-Generation PFBC may also introduce other advantages over the more complicated 2nd-Generation PFBC system. This report describes the technical and economic evaluation of 1.5-Generation PFBC cycles for utility or industrial power generation.

White, J.S.; Witman, P.M.; Harbaugh, L.; Rubow, L.N.; Horazak, D.A.

1994-12-01T23:59:59.000Z

208

Next Generation Nuclear Plant Methods Research and Development Technical Program Plan -- PLN-2498  

Science Conference Proceedings (OSTI)

One of the great challenges of designing and licensing the Very High Temperature Reactor (VHTR) is to confirm that the intended VHTR analysis tools can be used confidently to make decisions and to assure all that the reactor systems are safe and meet the performance objectives of the Generation IV Program. The research and development (R&D) projects defined in the Next Generation Nuclear Plant (NGNP) Design Methods Development and Validation Program will ensure that the tools used to perform the required calculations and analyses can be trusted. The Methods R&D tasks are designed to ensure that the calculational envelope of the tools used to analyze the VHTR reactor systems encompasses, or is larger than, the operational and transient envelope of the VHTR itself. The Methods R&D focuses on the development of tools to assess the neutronic and thermal fluid behavior of the plant. The fuel behavior and fission product transport models are discussed in the Advanced Gas Reactor (AGR) program plan. Various stress analysis and mechanical design tools will also need to be developed and validated and will ultimately also be included in the Methods R&D Program Plan. The calculational envelope of the neutronics and thermal-fluids software tools intended to be used on the NGNP is defined by the scenarios and phenomena that these tools can calculate with confidence. The software tools can only be used confidently when the results they produce have been shown to be in reasonable agreement with first-principle results, thought-problems, and data that describe the “highly ranked” phenomena inherent in all operational conditions and important accident scenarios for the VHTR.

Richard R. Schultz; Abderrafi M. Ougouag; David W. Nigg; Hans D. Gougar; Richard W. Johnson; William K. Terry; Chang H. Oh; Donald W. McEligot; Gary W. Johnsen; Glenn E. McCreery; Woo Y. Yoon; James W. Sterbentz; J. Steve Herring; Temitope A. Taiwo; Thomas Y. C. Wei; William D. Pointer; Won S. Yang; Michael T. Farmer; Hussein S. Khalil; Madeline A. Feltus

2008-09-01T23:59:59.000Z

209

East Mesa Magmamax Power Process Geothermal Generating Plant, A Preliminary Analysis  

SciTech Connect

During recent months, Magma Power Company has been involved in the shakedown and startup of their 10 MW binary cycle power plant at East Mesa in the Imperial Valley of Southern California. This pilot plant has been designed specifically as an R & D facility, with its primary goal to explore the necessary technology improvements required to make the binary cycle an efficient, cost effective and reliable conversion process. Magma Power's exploration activities, carried out in other parts of the Western United States after the initial discovery and development at The Geyser's, gave evidence that The Geyser's type of steam reservoir was unique and that the majority of geothermal resources would be of the hydrothermal, or pressurized hot water type. Initial flow tests throughout different locations where this type of resource was discovered indicated that well bore scaling occurred at the flash point in the wells. Initial evaluations indicated that if the well fluid could be maintained under pressure as it traversed the well bore, the potential for scaling would be mitigated. Tests carried out in the late 60's at Magma's Brady Hot Springs development in Nevada indicated that scaling was mitigated with the installation of a pump in the geothermal well. Subsequently, designs were developed of a binary process, utilizing heat exchangers for power generation. Magma was able to acquire process patents associated with this and had a patent issued (Magmamax Power Process). This incorporates the concept of pumping a geothermal well and transferring the heat in the geothermal fluid to a secondary power fluid in heat exchangers. Magma's desire to demonstrate this technology was one of the prime motivations associated with the installation of the East Mesa plant.

Hinrichs, T.C.; Dambly, B.W.

1980-12-01T23:59:59.000Z

210

Site Selection & Characterization Status Report for Next Generation Nuclear Plant (NGNP)  

SciTech Connect

In the near future, the US Department of Energy (DOE) will need to make important decisions regarding design and construction of the Next Generation Nuclear Plant (NGNP). One part of making these decisions is considering the potential environmental impacts that this facility may have, if constructed here at the Idaho National Laboratory (INL). The National Environmental Policy Act (NEPA) of 1969 provides DOE decision makers with a process to systematically consider potential environmental consequences of agency decisions. In addition, the Energy Policy Act of 2005 (Title VI, Subtitel C, Section 644) states that the 'Nuclear Regulatory Commission (NRC) shall have licensing and regulatory authority for any reactor authorized under this subtitle.' This stipulates that the NRC will license the NGNP for operation. The NRC NEPA Regulations (10 CFR Part 51) require tha thte NRC prepare an Environmental Impact Statement (EIS) for a permit to construct a nuclear power plant. The applicant is required to submit an Environmental report (ER) to aid the NRC in complying with NEPA.

Mark Holbrook

2007-09-01T23:59:59.000Z

211

Research and Development Technology Development Roadmaps for the Next Generation Nuclear Plant Project  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy (DOE) has selected the high temperature gas-cooled reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for process heat, hydrogen and electricity production. The reactor will be graphite moderated with helium as the primary coolant and may be either prismatic or pebble-bed. Although, final design features have not yet been determined. Research and Development (R&D) activities are proceeding on those known plant systems to mature the technology, codify the materials for specific applications, and demonstrate the component and system viability in NGNP relevant and integrated environments. Collectively these R&D activities serve to reduce the project risk and enhance the probability of on-budget, on-schedule completion and NRC licensing. As the design progresses, in more detail, toward final design and approval for construction, selected components, which have not been used in a similar application, in a relevant environment nor integrated with other components and systems, must be tested to demonstrate viability at reduced scales and simulations prior to full scale operation. This report and its R&D TDRMs present the path forward and its significance in assuring technical readiness to perform the desired function by: Choreographing the integration between design and R&D activities; and proving selected design components in relevant applications.

Ian McKirdy

2011-07-01T23:59:59.000Z

212

Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) Volume 4: High-Temperature Materials PIRTs  

Science Conference Proceedings (OSTI)

The Phenomena Identification and Ranking Table (PIRT) technique was used to identify safety-relevant/safety-significant phenomena and assess the importance and related knowledge base of high-temperature structural materials issues for the Next Generation Nuclear Plant (NGNP), a very high temperature gas-cooled reactor (VHTR). The major aspects of materials degradation phenomena that may give rise to regulatory safety concern for the NGNP were evaluated for major structural components and the materials comprising them, including metallic and nonmetallic materials for control rods, other reactor internals, and primary circuit components; metallic alloys for very high-temperature service for heat exchangers and turbomachinery, metallic alloys for high-temperature service for the reactor pressure vessel (RPV), other pressure vessels and components in the primary and secondary circuits; and metallic alloys for secondary heat transfer circuits and the balance of plant. These materials phenomena were primarily evaluated with regard to their potential for contributing to fission product release at the site boundary under a variety of event scenarios covering normal operation, anticipated transients, and accidents. Of all the high-temperature metallic components, the one most likely to be heavily challenged in the NGNP will be the intermediate heat exchanger (IHX). Its thin, internal sections must be able to withstand the stresses associated with thermal loading and pressure drops between the primary and secondary loops under the environments and temperatures of interest. Several important materials-related phenomena related to the IHX were identified, including crack initiation and propagation; the lack of experience of primary boundary design methodology limitations for new IHX structures; and manufacturing phenomena for new designs. Specific issues were also identified for RPVs that will likely be too large for shop fabrication and transportation. Validated procedures for on-site welding, post-weld heat treatment (PWHT), and inspections will be required for the materials of construction. High-importance phenomena related to the RPV include crack initiation and subcritical crack growth; field fabrication process control; property control in heavy sections; and the maintenance of high emissivity of the RPV materials over their service lifetime to enable passive heat rejection from the reactor core. All identified phenomena related to the materials of construction for the IHX, RPV, and other components were evaluated and ranked for their potential impact on reactor safety.

Corwin, William R [ORNL; Ballinger, R. [Massachusetts Institute of Technology (MIT); Majumdar, S. [Argonne National Laboratory (ANL); Weaver, K. D. [Idaho National Laboratory (INL)

2008-03-01T23:59:59.000Z

213

Preliminary materials selection issues for the next generation nuclear plant reactor pressure vessel.  

DOE Green Energy (OSTI)

In the coming decades, the United States and the entire world will need energy supplies to meet the growing demands due to population increase and increase in consumption due to global industrialization. One of the reactor system concepts, the Very High Temperature Reactor (VHTR), with helium as the coolant, has been identified as uniquely suited for producing hydrogen without consumption of fossil fuels or the emission of greenhouse gases [Generation IV 2002]. The U.S. Department of Energy (DOE) has selected this system for the Next Generation Nuclear Plant (NGNP) Project, to demonstrate emissions-free nuclear-assisted electricity and hydrogen production within the next 15 years. The NGNP reference concepts are helium-cooled, graphite-moderated, thermal neutron spectrum reactors with a design goal outlet helium temperature of {approx}1000 C [MacDonald et al. 2004]. The reactor core could be either a prismatic graphite block type core or a pebble bed core. The use of molten salt coolant, especially for the transfer of heat to hydrogen production, is also being considered. The NGNP is expected to produce both electricity and hydrogen. The process heat for hydrogen production will be transferred to the hydrogen plant through an intermediate heat exchanger (IHX). The basic technology for the NGNP has been established in the former high temperature gas reactor (HTGR) and demonstration plants (DRAGON, Peach Bottom, AVR, Fort St. Vrain, and THTR). In addition, the technologies for the NGNP are being advanced in the Gas Turbine-Modular Helium Reactor (GT-MHR) project, and the South African state utility ESKOM-sponsored project to develop the Pebble Bed Modular Reactor (PBMR). Furthermore, the Japanese HTTR and Chinese HTR-10 test reactors are demonstrating the feasibility of some of the planned components and materials. The proposed high operating temperatures in the VHTR place significant constraints on the choice of material selected for the reactor pressure vessel for both the PBMR and prismatic design. The main focus of this report is the RPV for both design concepts with emphasis on material selection.

Natesan, K.; Majumdar, S.; Shankar, P. S.; Shah, V. N.; Nuclear Engineering Division

2007-03-21T23:59:59.000Z

214

Considerations Associated with Reactor Technology Selection for the Next Generation Nuclear Plant Project  

Science Conference Proceedings (OSTI)

At the inception of the Next Generation Nuclear Plant Project and during predecessor activities, alternative reactor technologies have been evaluated to determine the technology that best fulfills the functional and performance requirements of the targeted energy applications and market. Unlike the case of electric power generation where the reactor performance is primarily expressed in terms of economics, the targeted energy applications involve industrial applications that have specific needs in terms of acceptable heat transport fluids and the associated thermodynamic conditions. Hence, to be of interest to these industrial energy applications, the alternative reactor technologies are weighed in terms of the reactor coolant/heat transport fluid, achievable reactor outlet temperature, and practicality of operations to achieve the very high reliability demands associated with the petrochemical, petroleum, metals and related industries. These evaluations have concluded that the high temperature gas-cooled reactor (HTGR) can uniquely provide the required ranges of energy needs for these target applications, do so with promising economics, and can be commercialized with reasonable development risk in the time frames of current industry interest – i.e., within the next 10-15 years.

L.E. Demick

2010-09-01T23:59:59.000Z

215

Repowering Fossil Steam Plants with Gas Turbines and Heat Recovery Steam Generators: Design Considerations, Economics, and Lessons L earned  

Science Conference Proceedings (OSTI)

This report describes repowering fossil steam plants using gas turbines (GTs) and heat recovery steam generators (HRSGs) in combined-cycle mode. Design considerations and guidance, comparative economics, and lessons learned in the development of such projects are included. Various other methods of fossil plant repowering with GTs are also briefly discussed. The detailed results and comparisons that are provided relate specifically to a generic GT/HRSG repowering. Design parameters, limitations, schedulin...

2012-08-08T23:59:59.000Z

216

An assessment of the radiological doses resulting from accidental uranium aerosol releases and fission product releases from a postulated criticality accident at the Oak Ridge Y-12 Plant  

Science Conference Proceedings (OSTI)

A dose assessment for two separate normalized source terms was conducted for the Oak Ridge Y-12 Plant. The first source term consisted of the noble gas and iodine fission products emanating from a postulated criticality with a magnitude of 10{sup 19} fissions. The second postulated source term was 1 kg of respirable highly enriched uranium. The MELCOR Accident Consequence Code System 2 (MACCS2) (beta test) computer code was used for this assessment. Both fixed weather (e.g., constant weather assumed throughout the accident) and sampled weather cases were performed using MACCS2. The results of the analysis are summarized in terms of the effective dose equivalent as a function of distance along the downwind centerline of the plume. In addition, population doses for the workers and the public are presented. A brief code comparison between the MACCS2 and MESORAD computer codes is also presented. Modeling differences for the cloudshine and groundshine dose pathways are discussed. Finally, the dose results are summarized, and recommendations are provided that enable the reader to make quick estimates of downwind doses for different source terms that are scalable.

Fisher, S.E.; Lenox, K.E.

1995-03-01T23:59:59.000Z

217

Table 12. Coal Prices to Electric Generating Plants, Projected vs. Actual  

Gasoline and Diesel Fuel Update (EIA)

Coal Prices to Electric Generating Plants, Projected vs. Actual Coal Prices to Electric Generating Plants, Projected vs. Actual (nominal dollars per million Btu) 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 AEO 1982 2.03 2.17 2.33 2.52 2.73 2.99 AEO 1983 1.99 2.10 2.24 2.39 2.57 2.76 4.29 AEO 1984 1.90 2.01 2.13 2.28 2.44 2.61 3.79 AEO 1985 1.68 1.76 1.86 1.95 2.05 2.19 2.32 2.49 2.66 2.83 3.03 AEO 1986 1.61 1.68 1.75 1.83 1.93 2.05 2.19 2.35 2.54 2.73 2.92 3.10 3.31 3.49 3.68 AEO 1987 1.52 1.55 1.65 1.75 1.84 1.96 2.11 2.27 2.44 3.55 AEO 1989* 1.50 1.51 1.68 1.77 1.88 2.00 2.13 2.26 2.40 2.55 2.70 2.86 3.00 AEO 1990 1.46 1.53 2.07 2.76 3.7 AEO 1991 1.51 1.58 1.66 1.77 1.88 1.96 2.06 2.16 2.28 2.41 2.57 2.70 2.85 3.04 3.26 3.46 3.65 3.87 4.08 4.33 AEO 1992 1.54 1.61 1.66 1.75 1.85 1.97 2.03 2.14 2.26 2.44 2.55 2.69 2.83 3.00 3.20 3.40 3.58 3.78 4.01 AEO 1993 1.92 1.54 1.61 1.70

218

Self-cooling mono-container fuel cell generators and power plants using an array of such generators  

DOE Patents (OSTI)

A mono-container fuel cell generator (10) contains a layer of interior insulation (14), a layer of exterior insulation (16) and a single housing (20) between the insulation layers, where fuel cells, containing electrodes and electrolyte, are surrounded by the interior insulation (14) in the interior (12) of the generator, and the generator is capable of operating at temperatures over about 650.degree. C., where the combination of interior and exterior insulation layers have the ability to control the temperature in the housing (20) below the degradation temperature of the housing material. The housing can also contain integral cooling ducts, and a plurality of these generators can be positioned next to each other to provide a power block array with interior cooling.

Gillett, James E. (Greensburg, PA); Dederer, Jeffrey T. (Valencia, PA); Zafred, Paolo R. (Pittsburgh, PA)

1998-01-01T23:59:59.000Z

219

Self-cooling mono-container fuel cell generators and power plants using an array of such generators  

DOE Patents (OSTI)

A mono-container fuel cell generator contains a layer of interior insulation, a layer of exterior insulation and a single housing between the insulation layers, where fuel cells, containing electrodes and electrolyte, are surrounded by the interior insulation in the interior of the generator, and the generator is capable of operating at temperatures over about 650 C, where the combination of interior and exterior insulation layers have the ability to control the temperature in the housing below the degradation temperature of the housing material. The housing can also contain integral cooling ducts, and a plurality of these generators can be positioned next to each other to provide a power block array with interior cooling. 7 figs.

Gillett, J.E.; Dederer, J.T.; Zafred, P.R.

1998-05-12T23:59:59.000Z

220

Support and control system of the Waste Isolation Pilot Plant gas generation experiment glovebox  

SciTech Connect

A glovebox was designed and fabricated to house test containers loaded with contact handled transuranic (CH-TRU) waste. The test containers were designed to simulate the environmental characteristics of the caverns at the Waste Isolation Pilot Plant (WIPP). The support and control systems used to operate and maintain the Gas Generation Experiment (GGE) include the following: glovebox atmosphere and pressure control, test container support, glovebox operation support, and gas supply and exhaust systems. The glovebox atmosphere and pressure control systems consist of various components used to control both the pressure and quality of the argon atmosphere inside the glovebox. The glovebox pressure is maintained by three separate pressure control systems. The primary pressure control system is designed to maintain the glovebox at a negative pressure with the other two control systems serving as redundant safety backups. The quality of the argon atmosphere is controlled using a purifying bed system that removes oxygen and moisture. Glovebox atmosphere contaminants that are monitored on a continuous or periodic basis include moisture, oxygen, and nitrogen. The gas generation experiment requires the test containers to be filled with brine, leak tested, maintained at a constant temperature, and the gas head space of the test container sampled on a periodic basis. Test container support systems consisting of a brine addition system, leak test system, heating system, and gas sampling system were designed and implemented. A rupture disk system was constructed to provide pressure relief to the test containers. Operational requirements stipulated that test container temperature and pressure be monitored and collected on a continuous basis. A data acquisition system (DAS) was specifically designed to meet these requirements.

Benjamin, W.W.; Knight, C.J.; Michelbacher, J.A.; Rosenberg, K.E.

1997-09-01T23:59:59.000Z

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


221

Test container design/fabrication/function for the Waste Isolation Pilot Plant gas generation experiment glovebox  

SciTech Connect

The gas generation experiments (GGE) are being conducted at Argonne National Laboratory-West (ANL0W) with contact handled transuranic (CH-TRU) waste in support of the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. The purpose of the GGE is to determine the different quantities and types of gases that would be produced and the gas-generation rates that would develop if brine were introduced to CH-TRU waste under post-closure WIPP disposal room conditions. The experiment requires that a prescribed matrix of CH-TRU waste be placed in a 7.5 liter test container. After loaded with the CH-TRU waste, brine and inoculum mixtures (consisting of salt and microbes indigenous to the Carlsbad, New Mexico region) are added to the waste. The test will run for an anticipated time period of three to five years. The test container itself is an ASME rated pressure vessel constructed from Hastelloy C276 to eliminate corrosion that might contaminate the experimental results. The test container is required to maintain a maximum 10% head space with a maximum working pressure of 17.25 MPa (2,500 psia). The test container is designed to provide a gas sample of the head space without the removal of brine. Assembly of the test container lid and process valves is performed inside an inert atmosphere glovebox. Glovebox mockup activities were utilized from the beginning of the design phase to ensure the test container and associated process valves were designed for remote handling. In addition, test container processes (including brine addition, sparging, leak detection, and test container pressurization) are conducted inside the glovebox.

Knight, C.J.; Russell, N.E.; Benjamin, W.W.; Rosenberg, K.E.; Michelbacher, J.A.

1997-09-01T23:59:59.000Z

222

Nuclear Safeguards Infrastructure Required for the Next Generation Nuclear Plant (NGNP)  

SciTech Connect

The Next Generation Nuclear Plant (NGNP) is a Very High Temperature Gas-Cooled Reactor (VHTR) to be constructed near Idaho Falls, Idaho The NGNP is intrinsically safer than current reactors and is planned for startup ca. 2021 Safety is more prominent in the minds of the Public and Governing Officials following the nuclear reactor meltdown accidents in Fukushima, Japan The authors propose that the NGNP should be designed with International (IAEA) Safeguards in mind to support export to Non-Nuclear-Weapons States There are two variants of the NGNP design; one using integral Prismatic-shaped fuel assemblies in a fixed core; and one using recirculating fuel balls (or Pebbles) The following presents the infrastructure required to safeguard the NGNP This infrastructure is required to safeguard the Prismatic and Pebble-fueled NGNP (and other HTGR/VHTR) The infrastructure is based on current Safeguards Requirements and Practices implemented by the International Atomic Energy Agency (IAEA) for similar reactors The authors of this presentation have worked for decades in the area of International Nuclear Safeguards and are recognized experts in this field Presentation for INMM conference in July 2012.

Dr. Mark Schanfein; Philip Casey Durst

2012-07-01T23:59:59.000Z

223

Compaction Scale Up and Optimization of Cylindrical Fuel Compacts for the Next Generation Nuclear Plant  

Science Conference Proceedings (OSTI)

Multiple process approaches have been used historically to manufacture cylindrical nuclear fuel compacts. Scale-up of fuel compacting was required for the Next Generation Nuclear Plant (NGNP) project to achieve an economically viable automated production process capable of providing a minimum of 10 compacts/minute with high production yields. In addition, the scale-up effort was required to achieve matrix density equivalent to baseline historical production processes, and allow compacting at fuel packing fractions up to 46% by volume. The scale-up approach of jet milling, fluid-bed overcoating, and hot-press compacting adopted in the U.S. Advanced Gas Reactor (AGR) Fuel Development Program involves significant paradigm shifts to capitalize on distinct advantages in simplicity, yield, and elimination of mixed waste. A series of designed experiments have been completed to optimize compaction conditions of time, temperature, and forming pressure using natural uranium oxycarbide (NUCO) fuel. Results from these experiments are included. The scale-up effort is nearing completion with the process installed and operational using nuclear fuel materials. The process is being certified for manufacture of qualification test fuel compacts for the AGR-5/6/7 experiment at the Advanced Test Reactor (ATR) at the Idaho National Laboratory (INL).

Jeffrey J. Einerson; Jeffrey A. Phillips; Eric L. Shaber; Scott E. Niedzialek; W. Clay Richardson; Scott G. Nagley

2012-10-01T23:59:59.000Z

224

Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) Volume 5: Graphite PIRTs  

DOE Green Energy (OSTI)

Here we report the outcome of the application of the Nuclear Regulatory Commission (NRC) Phenomena Identification and Ranking Table (PIRT) process to the issue of nuclear-grade graphite for the moderator and structural components of a next generation nuclear plant (NGNP), considering both routine (normal operation) and postulated accident conditions for the NGNP. The NGNP is assumed to be a modular high-temperature gas-cooled reactor (HTGR), either a gas-turbine modular helium reactor (GTMHR) version [a prismatic-core modular reactor (PMR)] or a pebble-bed modular reactor (PBMR) version [a pebble bed reactor (PBR)] design, with either a direct- or indirect-cycle gas turbine (Brayton cycle) system for electric power production, and an indirect-cycle component for hydrogen production. NGNP design options with a high-pressure steam generator (Rankine cycle) in the primary loop are not considered in this PIRT. This graphite PIRT was conducted in parallel with four other NRC PIRT activities, taking advantage of the relationships and overlaps in subject matter. The graphite PIRT panel identified numerous phenomena, five of which were ranked high importance-low knowledge. A further nine were ranked with high importance and medium knowledge rank. Two phenomena were ranked with medium importance and low knowledge, and a further 14 were ranked medium importance and medium knowledge rank. The last 12 phenomena were ranked with low importance and high knowledge rank (or similar combinations suggesting they have low priority). The ranking/scoring rationale for the reported graphite phenomena is discussed. Much has been learned about the behavior of graphite in reactor environments in the 60-plus years since the first graphite rectors went into service. The extensive list of references in the Bibliography is plainly testament to this fact. Our current knowledge base is well developed. Although data are lacking for the specific grades being considered for Generation IV (Gen IV) concepts, such as the NGNP, it is fully expected that the behavior of these graphites will conform to the recognized trends for near isotropic nuclear graphite. Thus, much of the data needed is confirmatory in nature. Theories that can explain graphite behavior have been postulated and, in many cases, shown to represent experimental data well. However, these theories need to be tested against data for the new graphites and extended to higher neutron doses and temperatures pertinent to the new Gen IV reactor concepts. It is anticipated that current and planned future graphite irradiation experiments will provide the data needed to validate many of the currently accepted models, as well as providing the needed data for design confirmation.

Burchell, Timothy D [ORNL; Bratton, Rob [Idaho National Laboratory (INL); Marsden, Barry [University of Manchester, UK; Srinivasan, Makuteswara [U.S. Nuclear Regulatory Commission; Penfield, Scott [Technology Insights; Mitchell, Mark [PBMR (Pty) Ltd.; Windes, Will [Idaho National Laboratory (INL)

2008-03-01T23:59:59.000Z

225

Steam Generator Management Program: Generic Plant Qualification and Application Plan for Dispersant Use During Steam Generator Wet L ayup  

Science Conference Proceedings (OSTI)

This report summarizes the results of an Electric Power Research Institute (EPRI) effort to develop dispersant application during steam generator (SG) wet layup as an additional deposit management strategy. Based on the results of this study, the addition of dispersant during wet layup is likely to modestly increase the amount of iron removed from the SGs of nuclear PWRs prior to power ascension, benefitting the utilities by reducing the corrosion product inventory within the SGs upon startup. The inform...

2011-06-30T23:59:59.000Z

226

electricity generating capacity | OpenEI  

Open Energy Info (EERE)

generating capacity generating capacity Dataset Summary Description The New Zealand Ministry of Economic Development publishes energy data including many datasets related to electricity. Included here are three electricity generating capacity datasets: annual operational electricity generation capacity by plant type (1975 - 2009); estimated generating capacity by fuel type for North Island, South Island and New Zealand (2009); and information on generating plants (plant type, name, owner, commissioned date, and capacity), as of December 2009. Source New Zealand Ministry of Economic Development Date Released Unknown Date Updated July 03rd, 2009 (5 years ago) Keywords biomass coal Electric Capacity electricity generating capacity geothermal Hydro Natural Gas wind Data application/vnd.ms-excel icon Operational Electricity Generation Capacity by Plant Type (xls, 42.5 KiB)

227

Threatened and endangered species evaluation for 75 licensed commercial nuclear power generating plants  

SciTech Connect

The Endangered Species Act (ESA) of 1973, as amended, and related implementing regulations of the jurisdictional federal agencies, the U.S. Departments of Commerce and Interior, at 50 CFR Part 17. 1, et seq., require that federal agencies ensure that any action authorized, funded, or carried out under their jurisdiction is not likely to jeopardize the continued existence of any threatened or endangered species or result in the destruction or adverse modification of critical habitats for such species. The issuance and maintenance of a federal license, such as a construction permit or operating license issued by the U.S. Nuclear Regulatory Commission (NRC) for a commercial nuclear power generating facility is a federal action under the jurisdiction of a federal agency, and is therefore subject to the provisions of the ESA. The U.S. Department of the Interior (through the Fish and Wildlife Service), and the U.S. Department of Commerce, share responsibility for administration of the ESA. The National Marine Fisheries Service (NMFS) deals with species that inhabit marine environments and anadromous fish, while the U.S. Fish and Wildlife Service (USFWS) is responsible for terrestrial and freshwater species and migratory birds. A species (or other distinct taxonomic unit such as subspecies, variety, and for vertebrates, distinct population units) may be classified for protection as `endangered` when it is in danger of extinction within the foreseeable future throughout all or a significant portion of its range. A `threatened` classification is provided to those animals and plants likely to become endangered within the foreseeable future throughout all or a significant portion of their ranges. As of February 1997, there were about 1067 species listed under the ESA in the United States. Additionally there were approximately 125 species currently proposed for listing as threatened or endangered, and another 183 species considered to be candidates for formal listing proposals.

Sackschewsky, M.R.

1997-03-01T23:59:59.000Z

228

Dose commitments due to radioactive releases from nuclear power plant sites: Methodology and data base. Supplement 1  

Science Conference Proceedings (OSTI)

This manual describes a dose assessment system used to estimate the population or collective dose commitments received via both airborne and waterborne pathways by persons living within a 2- to 80-kilometer region of a commercial operating power reactor for a specific year of effluent releases. Computer programs, data files, and utility routines are included which can be used in conjunction with an IBM or compatible personal computer to produce the required dose commitments and their statistical distributions. In addition, maximum individual airborne and waterborne dose commitments are estimated and compared to 10 CFR Part 50, Appendix 1, design objectives. This supplement is the last report in the NUREG/CR-2850 series.

Baker, D.A. [Pacific Northwest National Lab., Richland, WA (United States)] [Pacific Northwest National Lab., Richland, WA (United States)

1996-06-01T23:59:59.000Z

229

Plenary lecture 9: generation of electrical energy with variable speed in microhydro and eolian power plant  

Science Conference Proceedings (OSTI)

The mini hydroelectric power plant are built to use the flow of the small rivers. The main disadvantage of these systems is the reduced capacity to store a high quantity of water which should ensure the long term running of the hydroelectric plants during ...

Sorin Deaconu

2009-07-01T23:59:59.000Z

230

The AL-R8 SI: The next generation staging container for plutonium pits at the USDOE Pantex Plant  

SciTech Connect

The AL-R8 SI (sealed insert) is the next generation staging container for plutonium pits at the US DOE Pantex Plant. The sealed insert is a stainless steel container that will be placed inside a modified AL-R8 container to stage pits. A pit is a hollow sphere of plutonium metal which is the primary fissionable material in nuclear weapons (warheads and bombs). It is hermetically sealed by a cladding material, which is usually stainless steel. Personnel exposures to ionizing radiation from the pits in storage are expected to decrease due to the attenuation provided by the new SI. All personnel exposures to ionizing radiation at Pantex Plant are As Low As Reasonably Achievable (ALARA). Pantex Plant secures the common defense and national security of the US by safely staging plutonium pits in a manner that protests the health and safety of employees, the public, and the environment.

Eifert, E.J.; Vickers, L.D. [DOE Pantex Plant, Amarillo, TX (United States)

1999-11-01T23:59:59.000Z

231

Preliminary issues associated with the next generation nuclear plant intermediate heat exchanger design.  

SciTech Connect

The Next Generation Nuclear Plant (NGNP), which is an advanced high temperature gas reactor (HTGR) concept with emphasis on production of both electricity and hydrogen, involves helium as the coolant and a closed-cycle gas turbine for power generation with a core outlet/gas turbine inlet temperature of 900-1000 C. In the indirect cycle system, an intermediate heat exchanger is used to transfer the heat from primary helium from the core to the secondary fluid, which can be helium, nitrogen/helium mixture, or a molten salt. The system concept for the vary high temperature reactor (VHTR) can be a reactor based on the prismatic block of the GT-MHR developed by a consortium led by General Atomics in the U.S. or based on the PBMR design developed by ESKOM of South Africa and British Nuclear Fuels of U.K. This report has made a preliminary assessment on the issues pertaining to the intermediate heat exchanger (IHX) for the NGNP. Two IHX designs namely, shell and tube and compact heat exchangers were considered in the assessment. Printed circuit heat exchanger, among various compact heat exchanger (HX) designs, was selected for the analysis. Irrespective of the design, the material considerations for the construction of the HX are essentially similar, except may be in the fabrication of the units. As a result, we have reviewed in detail the available information on material property data relevant for the construction of HX and made a preliminary assessment of several relevant factors to make a judicious selection of the material for the IHX. The assessment included four primary candidate alloys namely, Alloy 617 (UNS N06617), Alloy 230 (UNS N06230), Alloy 800H (UNS N08810), and Alloy X (UNS N06002) for the IHX. Some of the factors addressed in this report are the tensile, creep, fatigue, creep fatigue, toughness properties for the candidate alloys, thermal aging effects on the mechanical properties, American Society of Mechanical Engineers (ASME) Code compliance information, and performance of the alloys in helium containing a wide range of impurity concentrations. A detailed thermal hydraulic analysis, using a model developed at ANL, was performed to calculate heat transfer, temperature distribution, and pressure drop inside both printed circuit and shell-and-tube heat exchangers. The analysis included evaluation of the role of key process parameters, geometrical factors in HX designs, and material properties. Calculations were performed for helium-to-helium, helium-to-helium/nitrogen, and helium-to-salt HXs. The IHX being a high temperature component, probably needs to be designed using ASME Code Section III, Subsection NH, assuming that the IHX will be classified as a class 1 component. With input from thermal hydraulic calculations performed at ANL, thermal conduction and stress analyses for both compact and shell-and-tube HXs were performed.

Natesan, K.; Moisseytsev, A.; Majumdar, S.; Shankar, P. S.; Nuclear Engineering Division

2007-04-05T23:59:59.000Z

232

Plant Engineering: Storage and Use of Low-Concentration (5%) Biodiesel Blends in Nuclear Plant Emergency Diesel Generators  

Science Conference Proceedings (OSTI)

The potential for biodiesel to be found in diesel fuel for emergency diesel generators (EDGs) is greatly increased since ASTM approved the allowance of up to 5 volume percent biodiesel (B5) in commercial diesel covered by ASTM D975. Although B5 is approved for use by all major diesel engine manufacturers, little is known about possible problems that could be encountered by utilities with EDGs. This report is an addendum to previously published Electric Power Research Institute (EPRI) report 1021071. It i...

2011-03-29T23:59:59.000Z

233

Plant Support Engineering: Storage and Use of Low Concentration (5%) Biodiesel Blends in Nuclear Plant Emergency Diesel Generators  

Science Conference Proceedings (OSTI)

The potential for biodiesel to be found in diesel fuel for emergency diesel generators (EDGs) is greatly increased since the American Society for Testing and Materials (ASTM) approved the allowance of up to 5 volume percent (vol%) biodiesel (B5) in commercial diesel covered by ASTM D975. While B5 is approved for use by all major diesel engine manufacturers, little is known about possible problems that could be encountered by utilities with EDGs. This report contains the findings from an extensive literat...

2010-12-03T23:59:59.000Z

234

JGI - News Releases  

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

News Releases News Releases December 20, 2013 A gluttonous plant reveals how its cellular power plant devours foreign DNA. Amborella trichopoda, a sprawling shrub that grows on just a single island in the remote South Pacific, is the only plant in its family and genus. It is also one of the oldest flowering plants, having branched off from others about 200 million years ago. November 25, 2013 How Scavenging Fungi Became a Plant's Best Friend. Glomeromycota is an ancient lineage of fungi that has a symbiotic relationship with roots that goes back nearly 420 million years to the earliest plants. More than two thirds of the world's plants depend on this soil-dwelling symbiotic fungus to survive, including critical agricultural crops such as wheat, cassava, and rice. November 22, 2013

235

Has Restructuring Improved Operating Efficiency at U.S. Electricity Generating Plants?  

E-Print Network (OSTI)

Regulatory Commission (FERC) collects data for investor-utility plants annually in the FERC Form 1, and the Energydata were reported to FERC or EIA over the 1981 through 1999

Fabrizio, Kira; Rose, Nancy; Wolfram, Catherine

2004-01-01T23:59:59.000Z

236

The Need for Deployment of the Next Generation Nuclear Plant Project Position Statement  

E-Print Network (OSTI)

research, development, design, construction, and operation of a prototype nuclear reactor to produce electricity and hydrogen. The NGNP is intended to be a collaborative effort among the U.S. Department of Energy, the Idaho National Laboratory, and appropriate industrial partners. It is also intended to include international technology exchanges. The NGNP will utilize what is commonly referred to as a Generation IV design. Generation III designs are the latest reactor designs licensed or certified by the U.S. Nuclear Regulatory Commission (NRC). Generation III+ includes the new designs currently under review by the NRC and anticipated to begin operation during the next 10 to 20 years. Generation IV designs are more advanced and are expected to be ready for commercial construction after 2020. The Generation IV designs may include new or additional features such as the following: • capability for hydrogen production 2 • use of recycled fuel • use of plutonium and other fission by-products • a more efficient fuel cycle with lower generation of waste products • higher safety and physical protection levels • higher reliability • better economic performance. The ANS also supports the federal government efforts in support of a robust Generation IV development program in parallel with current Generation III+ efforts. 3 Sequential utilization of new or different designs and technologies will ensure ever-increasing safety levels and will help nuclear energy fulfill its vital role in worldwide electricity generation.

unknown authors

2005-01-01T23:59:59.000Z

237

Combined cycle electric power plant having a control system which enables dry steam generator operation during gas turbine operation  

SciTech Connect

A control system for a combined cycle electric power plant is described. It contains: at least one gas turbine including an exit through which heated exhaust gases pass; means for generating steam coupled to said gas turbine exit for transferring heat from the exhaust gases to a fluid passing through the steam generator; a steam turbine coupled to the steam generator and driven by the steam supplied thereby; means for generating electric power by the driving power of the turbines; condenser means for receiving and converting the spent steam from the steam turbine into condensate; and steam generating means comprising a low pressure storage tank, a first heat exchange tube, a boiler feedwater pump for directing fluid from a low pressure storage tank through the first heat exchange tube, a main storage drum, a second heat exchange tube, and a high pressure recirculation pump for directing fluid from the main storage pump through the second heat exchange tube. The control system monitors the temperature of the exhaust gas turbine gases as directed to the steam generator and deactuates the steam turbine when a predetermined temperature is exceeded.

Martz, L.F.; Plotnick, R.J.

1974-08-08T23:59:59.000Z

238

Power conversion unit studies for the next generation nuclear plant coupled to a high-temperature steam electrolysis facility  

E-Print Network (OSTI)

The Department of Energy and the Idaho National Laboratory are developing a Next Generation Nuclear Plant (NGNP) to serve as a demonstration of state-of-the-art nuclear technology. The purpose of the demonstration is two fold: 1) efficient low cost energy generation and 2) hydrogen production. Although a next generation plant could be developed as a single-purpose facility, early designs are expected to be dual-purpose. While hydrogen production and advanced energy cycles are still in their early stages of development, research towards coupling a high temperature reactor, electrical generation and hydrogen production is under way. Many aspects of the NGNP must be researched and developed to make recommendations on the final design of the plant. Parameters such as working conditions, cycle components, working fluids, and power conversion unit configurations must be understood. Three configurations of the power conversion unit were modeled using the process code HYSYS; a three-shaft design with 3 turbines and 4 compressors, a combined cycle with a Brayton top cycle and a Rankine bottoming cycle, and a reheated cycle with 3 stages of reheat were investigated. A high temperature steam electrolysis hydrogen production plant was coupled to the reactor and power conversion unit by means of an intermediate heat transport loop. Helium, CO2, and an 80% nitrogen, 20% helium mixture (by weight) were studied to determine the best working fluid in terms cycle efficiency and development cost. In each of these configurations the relative heat exchanger size and turbomachinery work were estimated for the different working fluids. Parametric studies away from the baseline values of the three-shaft and combined cycles were performed to determine the effect of varying conditions in the cycle. Recommendations on the optimal working fluid for each configuration were made. The helium working fluid produced the highest overall plant efficiency for the three-shaft and reheat cycle; however, the nitrogen-helium mixture produced similar efficiency with smaller component sizes. The CO2 working fluid is recommend in the combined cycle configuration.

Barner, Robert Buckner

2006-12-01T23:59:59.000Z

239

Cycling Operation of Fossil Plants: Volume 3: Cycling Evaluation of Pepco's Potomac River Generating Station  

Science Conference Proceedings (OSTI)

This report presents a methodology for examining the economic feasibility of converting fossil power plants from baseload to cycling service. It employs this approach to examine a proposed change of Pepco's Potomac River units 3, 4, and 5 from baseload operation to two-shift cycling.

1991-06-01T23:59:59.000Z

240

Thinking about Generation Diversity: Electric Power Plant Asset Portfolio Valuation and Risk  

Science Conference Proceedings (OSTI)

In recent years, large amounts of natural gas-fired power generation capacity have been added to the nation’s portfolio of power generation assets. In addition, a variety of analyses and market projections imply this trend will continue for a variety of reasons, including large and growing supplies of natural gas due to the “shale boom,” and commensurate low natural gas prices, and imposition of increasingly stringent environmental regulations associated with coal-fired ...

2013-12-16T23:59:59.000Z

Note: This page contains sample records for the topic "generating plants release" 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

Marginal cost of electricity 1980-1995: an approximation based on the cost of new coal and nuclear generating plants  

SciTech Connect

This report presents estimates of the costs of new coal and nuclear base-load generating capacity which is either currently under construction or planned by utilities to meet their load-growth expectations during the period from 1980 to 1995. These capacity cost estimates are used in conjunction with announced plant capacities and commercial-operation dates to develop state-level estimates of busbar costs of electricity. From these projected busbar costs, aggregated estimates of electricity costs at the retail level are developed for DOE Regions. The introductory chapter explains the rationale for using the cost of electricity from base-load plants to approximate the marginal cost of electricity. The next major section of the report outlines the methodology and major assumptions used. This is followed by a detailed description of the empirical analysis, including the equations used for each of the cost components. The fourth section presents the resultant marginal cost estimates.

Nieves, L.A.; Patton, W.P.; Harrer, B.J.; Emery, J.C.

1980-07-01T23:59:59.000Z

242

Central receiver solar thermal power system, Phase 1. CDRL item 2. Pilot plant preliminary design report. Volume VI. Electrical power generation and master control subsystems and balance of plant  

DOE Green Energy (OSTI)

The requirements, performance, and subsystem configuration for both the Commercial and Pilot Plant electrical power generation subsystems (EPGS) and balance of plants are presented. The EPGS for both the Commercial Plant and Pilot Plant make use of conventional, proven equipment consistent with good power plant design practices in order to minimize risk and maximize reliability. The basic EPGS cycle selected is a regenerative cycle that uses a single automatic admission, condensing, tandem-compound double-flow turbine. Specifications, performance data, drawings, and schematics are included. (WHK)

Hallet, Jr., R. W.; Gervais, R. L.

1977-10-01T23:59:59.000Z

243

Management Activities for Retrieved and Newly Generated Transuranic Wastes Savannah River Plant  

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

8 WL 253648 (F.R.) 8 WL 253648 (F.R.) NOTICES DEPARTMENT OF ENERGY Finding of No Significant Impact; Transuranic Waste Management Activities at the Savannah River Plant, Aiken, SC Tuesday, August 30, 1988 *33172 AGENCY: Department of Energy. ACTION: Finding of No Significant Impact. SUMMARY: The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA -0315, for transuranic (TRU) waste management activities at DOE's Savannah River Plant (SRP), including the construction and operation of a new TRU Waste Processing Facility. Based on analyses in the EA, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment, within the meaning of the National Environmental Policy Act (NEPA) of 1969. Therefore, the preparation of an environmental impact

244

Generation Maintenance Application Center: Fuel Gas System for Combustion Turbine Combined Cycle Plant Maintenance Guide  

Science Conference Proceedings (OSTI)

This guide provides information to assist personnel involved with the maintenance of the fuel gas system at a gas turbine combined cycle facility, including good maintenance practices, preventive maintenance techniques and troubleshooting guidance. BackgroundCombustion turbine combined cycle (CTCC) facilities utilize various components that can be unique to this particular type of power plant. As such, owners and operators of CTCC facilities may find ...

2013-05-15T23:59:59.000Z

245

New technology for purging the steam generators of nuclear power plants  

Science Conference Proceedings (OSTI)

A technology for removal of undissolved impurities from a horizontal steam generator using purge water is developed on the basis of a theoretical analysis. A purge with a maximal flow rate is drawn off from the zone with the highest accumulation of sludge in the lower part of the steam generator after the main circulation pump of the corresponding loop is shut off and the temperatures of the heat transfer medium at the inlet and outlet of the steam generator have equilibrated. An improved purge configuration is used for this technology; it employs shutoff and regulator valves, periodic purge lines separated by a cutoff fixture, and a D{sub y} 100 drain union as a connector for the periodic purge. Field tests show that the efficiency of this technology for sludge removal by purge water is several times that for the standard method.

Budko, I. O.; Kutdjusov, Yu. F.; Gorburov, V. I. [Scientific-Research Center for Energy Technology 'NICE Centrenergo' (Russian Federation); Rjasnyj, S. I. [JSC 'The All-Rissia Nuklear Power Engineering Research and Development Institute' (VNIIAM) (Russian Federation)

2011-07-15T23:59:59.000Z

246

Doubly Fed Induction Generator in an Offshore Wind Power Plant Operated at Rated V/Hz: Preprint  

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

Doubly Fed Induction Generator Doubly Fed Induction Generator in an Offshore Wind Power Plant Operated at Rated V/Hz Preprint Eduard Muljadi, Mohit Singh, and Vahan Gevorgian To be presented at the IEEE Energy Conversion Congress and Exhibition Raleigh, North Carolina September 15-20, 2012 Conference Paper NREL/CP-5500-55573 June 2012 NOTICE The submitted manuscript has been offered by an employee of the Alliance for Sustainable Energy, LLC (Alliance), a contractor of the US Government under Contract No. DE-AC36-08GO28308. Accordingly, the US Government and Alliance retain a nonexclusive royalty-free license to publish or reproduce the published form of this contribution, or allow others to do so, for US Government purposes. This report was prepared as an account of work sponsored by an agency of the United States government.

247

Establishing a Groundwater Protection Program for New Nuclear Generating Units: Appendix to the EPRI Groundwater Protection Guidelines for Nuclear Power Plants  

Science Conference Proceedings (OSTI)

New nuclear power plants should plan for groundwater protection early in the planning process. The construction project team should be made aware of the need to establish the groundwater protection program prior to the construction planning process. This document provides guidance for establishing Groundwater Protection Programs for new nuclear generating units. It applies to new nuclear generating units on both new and existing nuclear power plant ...

2013-03-27T23:59:59.000Z

248

Combined cycle electric power plant and heat recovery steam generator having improved multi-loop temperature control of the steam generated  

SciTech Connect

A combined cycle electric power plant is described that includes gas and steam turbines and a steam generator for recovering the heat in the exhaust gases exited from the gas turbine and for using the recovered heat to produce and supply steam to the steam turbine. The steam generator includes a superheater tube and a steam drum from which heated steam is directed through the superheater to be additionally heated into superheated steam by the exhaust gas turbine gases. An afterburner serves to further heat the exhaust gas turbine gases passed to the superheater tube and a bypass conduit is disposed about the superheater tube whereby a variable steam flow determined by a bypass valve disposed in the bypass conduit may be directed about the superheater tube to be mixed with the superheated steam therefrom, whereby the temperature of the superheated steam supplied to the steam turbine may be accurately controlled. Steam temperature control means includes a first control loop responsive to the superheated steam temperature for regulating the position of the bypass valve with respect to a first setpoint, and a second control loop responsive to the superheated steam temperature for controlling the fuel supply to the afterburner with respect to a second setpoint varying in accordance with the bypass valve position. In particular, as the bypass valve position increases, the second setpoint, originally higher, is lowered toward a value substantially equal to that of the first setpoint.

Martz, L.F.; Plotnick, R.J.

1976-08-17T23:59:59.000Z

249

Estimating Spore Release Rates Using a Lagrangian Stochastic Simulation Model  

Science Conference Proceedings (OSTI)

Practical problems in predicting the spread of plant diseases within and between fields require knowledge of the rate of release Q of pathogenic spores into the air. Many plant pathogenic fungus spores are released into the air from plant ...

Donald E. Aylor; Thomas K. Flesch

2001-07-01T23:59:59.000Z

250

Proceedings: Eighth International Conference on Cycle Chemistry in Fossil and Combined Cycle Plants with Heat Recovery Steam Generators, June 20-22, 2006, Calgary, Alberta Canada  

Science Conference Proceedings (OSTI)

Proper selection, application, and optimization of the cycle chemistry have long been recognized as integral to ensuring the highest possible levels of component availability and reliability in fossil-fired generating plant units. These proceedings of the Eighth EPRI International Conference on Cycle Chemistry in Fossil Plants address state-of-the-art practices in conventional and combined cycle plants. The content provides a worldwide perspective on cycle chemistry practices, and insight as to industry ...

2007-03-20T23:59:59.000Z

251

Review of CO2 Capture Development Activities for Coal-Fired Power Generation Plants  

Science Conference Proceedings (OSTI)

If CO2 capture and storage (CCS) is to be implemented and play a role in keeping electricity prices affordable under proposed emission restrictions, its rate of progress needs to be accelerated. Demonstration plants need to be deployed in the short-term to allow the technology to evolve and become more efficient and cost–effective. Achieving this objective is the primary objective of EPRI's CoalFleet for Tomorrow Program. This report provides an up-to-date review of the progress being made in pilot and d...

2009-03-30T23:59:59.000Z

252

Hanford waste vitrification plant hydrogen generation study: Preliminary evaluation of alternatives to formic acid  

DOE Green Energy (OSTI)

Oxalic, glyoxylic, glycolic, malonic, pyruvic, lactic, levulinic, and citric acids as well as glycine have been evaluated as possible substitutes for formic acid in the preparation of feed for the Hanford waste vitrification plant using a non-radioactive feed stimulant UGA-12M1 containing substantial amounts of aluminum and iron oxides as well as nitrate and nitrite at 90C in the presence of hydrated rhodium trichloride. Unlike formic acid none of these carboxylic acids liberate hydrogen under these conditions and only malonic and citric acids form ammonia. Glyoxylic, glycolic, malonic, pyruvic, lactic, levulinic, and citric acids all appear to have significant reducing properties under the reaction conditions of interest as indicated by the observation of appreciable amounts of N{sub 2}O as a reduction product of,nitrite or, less likely, nitrate at 90C. Glyoxylic, pyruvic, and malonic acids all appear to be unstable towards decarboxylation at 90C in the presence of Al(OH){sub 3}. Among the carboxylic acids investigated in this study the {alpha}-hydroxycarboxylic acids glycolic and lactic acids appear to be the most interesting potential substitutes for formic acid in the feed preparation for the vitrification plant because of their failure to produce hydrogen or ammonia or to undergo decarboxylation under the reaction conditions although they exhibit some reducing properties in feed stimulant experiments.

King, R.B.; Bhattacharyya, N.K.; Kumar, V.

1996-02-01T23:59:59.000Z

253

Next-generation online MC and A technologies for reprocessing plants  

SciTech Connect

As power-production nuclear fuel cycles propagate across the globe, a new generation of measurement technologies is needed to support safeguards monitoring of fuel reprocessing facilities. This paper describes the simulation and analysis of two potential technologies for meeting the challenges of 1) direct measurement of fissile isotopic content in irradiated fuel to detect partial defects, and 2) near-real-time monitoring of process chemistry to detect protracted diversion scenarios. Lead slowing-down spectroscopy is the core of the spent fuel assay technology and multi-isotope indicators via high-resolution gamma ray spectroscopy are the foundation of the process chemistry verification approach. The safeguards context and methods for each technology are described and the results of preliminary performance studies are presented. The quantitative results for both studies are promising but more comprehensive analysis and empirical validation is needed to adequately assess their potential value as next generation online materials control and accountability measures. (authors)

Smith, L.E.; Schwantes, J.M.; Ressler, J.J.; Douglas, M.; Anderson, K.A.; Fraga, C.G.; Durst, C. [Pacific Northwest National Laboratory, PO Box 999, Richland, WA, 99352 (United States); Orton, C.; Christensen, R. [Nuclear Engineering Program, Mechanical Engineering Department, Ohio State University, Columbus, OH, 43210 (United States)

2007-07-01T23:59:59.000Z

254

Next-Generation Online MC&A Technologies for Reprocessing Plants  

Science Conference Proceedings (OSTI)

As power-production nuclear fuel cycles propagate across the globe, a new generation of measurement technologies is needed to support safeguards monitoring of fuel reprocessing facilities. This paper describes the simulation and analysis of two potential technologies for meeting the challenges of 1) direct measurement of fissile isotopic content in irradiated fuel to detect partial defects, and 2) near-real-time monitoring of process chemistry to detect protracted diversion scenarios. Lead slowing-down spectroscopy is the core of the spent fuel assay technology and multi-isotope indicators via high-resolution gamma-ray spectroscopy is the foundation of the process chemistry verification approach. The safeguards context and methods for each technology are described and the results of preliminary performance studies are presented. The quantitative results for both studies are promising but more comprehensive analysis and empirical validation is needed to adequately assess their potential value as next-generation online materials control and accountability measures.

Smith, Leon E.; Schwantes, Jon M.; Ressler, Jennifer J.; Douglas, Matt; Anderson, Kevin K.; Fraga, Carlos G.; Durst, Casey; Orton, Chris; Christensen, Robert P.

2007-08-03T23:59:59.000Z

255

Alloys for 1000 degree C service in the Next Generation Nuclear Plant NERI 05-0191  

SciTech Connect

The objective of the proposed research is to define strategies for the improvement of alloys for structural components, such as the intermediate heat exchanger and primary-to-secondary piping, for service at 1000 degree C in the He environment of the NGNP. Specifically, we will investigate the oxidation/carburization behavior and microstructure stability and how these processes affect creep. While generating this data, the project will also develop a fundamental understanding of how impurities in the He environment affect these degradation processes and how this understanding can be used to develop more useful life prediction methodologies.

Gary S. Was; J.W. Jones; T. Pollock

2009-01-15T23:59:59.000Z

256

RESTRUCTURING RELAP5-3D FOR NEXT GENERATION NUCLEAR PLANT ANALYSIS  

Science Conference Proceedings (OSTI)

RELAP5-3D is used worldwide for analyzing nuclear reactors under both operational transients and postulated accident conditions. Development of the RELAP code series began in 1975 and since that time the code has been continuously improved, enhanced, verified and validated [1]. Since RELAP5-3D will continue to be the premier thermal hydraulics tool well into the future, it is necessary to modernize the code to accommodate the incorporation of additional capabilities to support the development of the next generation of nuclear reactors [2]. This paper discusses the reengineering of RELAP5-3D into structured code.

Donna Post Guillen; George L. Mesina; Joshua M. Hykes

2006-06-01T23:59:59.000Z

257

Review of CO2-Capture Development Activities for Coal-Fired Power Generation Plants  

Science Conference Proceedings (OSTI)

Coal is used to produce a large proportion of the power generated in the US and around the world and is likely to continue doing so well into the future. Nevertheless, it faces a huge challenge in reducing its emissions of CO2 in response to concerns over global warming. One solution is to capture the CO2 and store it in geological strata beneath the surface of the earth. Research investigating this approach is being carried out worldwide, reflecting the global nature of the issue. The two most favored c...

2007-03-28T23:59:59.000Z

258

Melting characteristics of the stainless steel generated from the uranium conversion plant  

Science Conference Proceedings (OSTI)

The partition ratio of cerium (Ce) and uranium (U) in the ingot, slag and dust phases has been investigated for the effect of the slag type, slag concentration and basicity in an electric arc melting process. An electric arc furnace (EAF) was used to melt the stainless steel wastes, simulated by uranium oxide and the real wastes from the uranium conversion plant in Korea Atomic Energy Research Institute (KAERI). The composition of the slag former used to capture the contaminants such as uranium, cerium, and cesium during the melt decontamination process generally consisted of silica (SiO{sub 2}), calcium oxide (CaO) and aluminum oxide (Al{sub 2}O{sub 3}). Also, Calcium fluoride (CaF{sub 2} ), nickel oxide (NiO), and ferric oxide (Fe{sub 2}O{sub 3}) were added to provide an increase in the slag fluidity and oxidative potential. Cerium was used as a surrogate for the uranium because the thermochemical and physical properties of cerium are very similar to those of uranium. Cerium was removed from the ingot phase to slag phase by up to 99% in this study. The absorption ratio of cerium was increased with an increase of the amount of the slag former. And the maximum removal of cerium occurred when the basicity index of the slag former was 0.82. The natural uranium (UO{sub 2}) was partitioned from the ingot phase to the slag phase by up to 95%. The absorption of the natural uranium was considerably dependent on the basicity index of the slag former and the composition of the slag former. The optimum condition for the removal of the uranium was about 1.5 for the basicity index and 15 wt% of the slag former. According to the increase of the amount of slag former, the absorption of uranium oxide in the slag phase was linearly increased due to an increase of its capacity to capture uranium oxide within the slag phase. Through experiments with various slag formers, we verified that the slag formers containing calcium fluoride (CaF{sub 2}) and a high amount of silica were more effective for a melt decontamination of stainless steel wastes contaminated with uranium. During the melting tests with stainless steel wastes from the uranium conversion plant(UCP ) in KAERI, we found that the results of the uranium decontamination were very similar to those of the uranium oxide from the melting of stimulated metal wastes. (authors)

Choi, W.K.; Song, P.S.; Oh, W.Z.; Jung, C.H. [Korea Atomic Energy Research Institute (Korea, Republic of); Min, B.Y. [Chungnam National University, 220 Gung-Dong, Yusung-Gu Taejon 305-764 (Korea, Republic of)

2007-07-01T23:59:59.000Z

259

High Temperature Gas-Cooled Reactors Lessons Learned Applicable to the Next Generation Nuclear Plant  

SciTech Connect

The purpose of this report is to identify possible issues highlighted by these lessons learned that could apply to the NGNP in reducing technical risks commensurate with the current phase of design. Some of the lessons learned have been applied to the NGNP and documented in the Preconceptual Design Report. These are addressed in the background section of this document and include, for example, the decision to use TRISO fuel rather than BISO fuel used in the Peach Bottom reactor; the use of a reactor pressure vessel rather than prestressed concrete found in Fort St. Vrain; and the use of helium as a primary coolant rather than CO2. Other lessons learned, 68 in total, are documented in Sections 2 through 6 and will be applied, as appropriate, in advancing phases of design. The lessons learned are derived from both negative and positive outcomes from prior HTGR experiences. Lessons learned are grouped according to the plant, areas, systems, subsystems, and components defined in the NGNP Preconceptual Design Report, and subsequent NGNP project documents.

J. M. Beck; L. F. Pincock

2011-04-01T23:59:59.000Z

260

EDDY CURRENT EXAMINATION OF STEAM GENERATOR TUBES FROM PHWR POWER PLANTS USING ROTATING MAGNETIC FIELD TRANSDUCER  

E-Print Network (OSTI)

Abstract. This paper present the results obtained at examination of steam generator tubes samples made from Incoloy 800, using eddy current transducer with rotating magnetic field. The emission part creates a magnetic rotating field which induces eddy currents in the walls of tubes, the reception being made with an array of sensors. The method presents the advantages of a complete inspection of tube’s surface at one passing. To increase the precision of discontinuity localization, a super resolution algorithm is used. The results are comparables with those obtained at the inspection with rotating probe, being obtained a good correlation, the speed of control being superior in the case of transducer with rotating magnetic field. 1.

Raimond Grimberg; Lalita Udpa; Alina Bruma; Rozina Steigmann; Adriana Savin; Satish S. Udpa

2007-01-01T23:59:59.000Z

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


261

Analysis and optimization of the Graz cycle : a coal fired power generation scheme with near-zero carbon dioxide emissions  

E-Print Network (OSTI)

Humans are releasing record amounts of carbon dioxide into the atmosphere through the combustion of fossil fuels in power generation plants. With mounting evidence that this carbon dioxide is a leading cause of global ...

Alexander, Brentan R

2007-01-01T23:59:59.000Z

262

High-potential Working Fluids for Next Generation Binary Cycle Geothermal Power Plants  

SciTech Connect

A thermo-economic model has been built and validated for prediction of project economics of Enhanced Geothermal Projects. The thermo-economic model calculates and iteratively optimizes the LCOE (levelized cost of electricity) for a prospective EGS (Enhanced Geothermal) site. It takes into account the local subsurface temperature gradient, the cost of drilling and reservoir creation, stimulation and power plant configuration. It calculates and optimizes the power plant configuration vs. well depth. Thus outputs from the model include optimal well depth and power plant configuration for the lowest LCOE. The main focus of this final report was to experimentally validate the thermodynamic properties that formed the basis of the thermo-economic model built in Phase 2, and thus build confidence that the predictions of the model could be used reliably for process downselection and preliminary design at a given set of geothermal (and/or waste heat) boundary conditions. The fluid and cycle downselected was based on a new proprietary fluid from a vendor in a supercritical ORC cycle at a resource condition of 200?C inlet temperature. The team devised and executed a series of experiments to prove the suitability of the new fluid in realistic ORC cycle conditions. Furthermore, the team performed a preliminary design study for a MW-scale turbo expander that would be used for a supercritical ORC cycle with this new fluid. The following summarizes the main findings in the investigative campaign that was undertaken: 1. Chemical compatibility of the new fluid with common seal/gasket/Oring materials was found to be problematic. Neoprene, Viton, and silicone materials were found to be incompatible, suffering chemical decomposition, swelling and/or compression set issues. Of the materials tested, only TEFLON was found to be compatible under actual ORC temperature and pressure conditions. 2. Thermal stability of the new fluid at 200?C and 40 bar was found to be acceptable after 399 hours of exposure?only 3% of the initial charge degraded into by products. The main degradation products being an isomer and a dimer. 3. In a comparative experiment between R245fa and the new fluid under subcritical conditions, it was found that the new fluid operated at 1 bar lower than R245fa for the same power output, which was also predicted in the Aspen HSYSY model. As a drop-in replacement fluid for R245fa, this new fluid was found to be at least as good as R245fa in terms of performance and stability. Further optimization of the subcritical cycle may lead to a significant improvement in performance for the new fluid. 4. For supercritical conditions, the experiment found a good match between the measured and model predicted state point property data and duties from the energy balance. The largest percent differences occurred with densities and evaporator duty (see Figure 78). It is therefore reasonable to conclude that the state point model was experimentally validated with a realistic ORC system. 5. The team also undertook a preliminary turbo-expander design study for a supercritical ORC cycle with the new working fluid. Variants of radial and axial turbo expander geometries went through preliminary design and rough costing. It was found that at 15MWe or higher power rating, a multi-stage axial turbine is most suitable providing the best performance and cost. However, at lower power ratings in the 5MWe range, the expander technology to be chosen depends on the application of the power block. For EGS power blocks, it is most optimal to use multi-stage axial machines. In conclusion, the predictions of the LCOE model that showed a supercritical cycle based on the new fluid to be most advantageous for geothermal power production at a resource temperature of ~ 200C have been experimentally validated. It was found that the cycle based on the new fluid is lower in LCOE and higher in net power output (for the same boundary conditions). The project, therefore has found a new optimal configuration for low temperature geothermal power production in the form of a su

Zia, Jalal [GE Global Research; Sevincer, Edip; Chen, Huijuan; Hardy, Ajilli; Wickersham, Paul; Kalra, Chiranjeev; Laursen, Anna Lis; Vandeputte, Thomas

2013-06-29T23:59:59.000Z

263

2017 Levelized Costs AEO 2012 Early Release  

Gasoline and Diesel Fuel Update (EIA)

2018 Levelized Costs AEO 2013 1 2018 Levelized Costs AEO 2013 1 January 2013 Levelized Cost of New Generation Resources in the Annual Energy Outlook 2013 This paper presents average levelized costs for generating technologies that are brought on line in 2018 1 as represented in the National Energy Modeling System (NEMS) for the Annual Energy Outlook 2013 (AEO2013) Early Release Reference case. 2 Both national values and the minimum and maximum values across the 22 U.S. regions of the NEMS electricity market module are presented. Levelized cost is often cited as a convenient summary measure of the overall competiveness of different generating technologies. It represents the per-kilowatthour cost (in real dollars) of building and operating a generating plant over an assumed financial life and duty cycle. Key

264

NETL: News Release - Energy Department Seeks Projects to Improve...  

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

DOE Publications News Release Release Date: February 6, 2001 Energy Department Seeks Projects To Improve Coal-Fired Power Plants Abraham Says Initiative Part of a Balanced And...

265

NETL: News Release - Updated Report Consolidates Information about Nation's  

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

16, 2007 16, 2007 Updated Report Consolidates Information about Nation's Existing Fleet of Coal-Fired Power Plants MORE INFO Link to NETL's 2007 Coal Power Plant Database Washington, DC - The Office of Fossil Energy's National Energy Technology Laboratory (NETL) has released its 2007 Coal Power Plant Database, a new, updated version which contains the most current and comprehensive collection of coal-fired power plant data in the United States. The database consolidates large quantities of information on the nation's existing coal-fired power plants in a single location. It covers 191 fields and provides information on more than 1,700 boilers and associated units. Emissions, generation, location, and firing data for all U.S. coal-power plants are located in the database, which supports DOE's Office of Fossil

266

Combined cycle electric power plant and a heat recovery steam generator having improved boiler feed pump flow control  

SciTech Connect

A combined cycle electric power plant is described that includes gas and steam turbines and a steam generator for recovering the heat in the exhaust gases exited from the gas turbine and for using the recovered heat to produce and supply steam to the steam turbine. The steam generator includes an economizer tube and a high pressure evaporator tube and a boiler feed pump for directing the heat exchange fluid serially through the aforementioned tubes. A condenser is associated with the steam turbine for converting the spent steam into condensate water to be supplied to a deaerator for removing undesired air and for preliminarily heating the water condensate before being pumped to the economizer tube. Condensate flow through the economizer tube is maintained substantially constant by maintaining the boiler feed pump at a predetermined, substantially constant rate. A bypass conduit is provided to feed back a portion of the flow heated in the economizer tube to the deaerator; the portion being equal to the difference between the constant flow through the economizer tube and the flow to be directed through the high pressure evaporator tube as required by the steam turbine for its present load.

Martz, L.F.; Plotnick, R.J.

1976-06-29T23:59:59.000Z

267

Design of the Next Generation Nuclear Plant Graphite Creep Experiments for Irradiation in the Advanced Test Reactor  

SciTech Connect

The United States Department of Energy’s Next Generation Nuclear Plant (NGNP) Program will be irradiating six gas reactor graphite creep experiments in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). The ATR has a long history of irradiation testing in support of reactor development and the INL has been designated as the new United States Department of Energy’s lead laboratory for nuclear energy development. The ATR is one of the world’s premiere test reactors for performing long term, high flux, and/or large volume irradiation test programs. These graphite irradiations are being accomplished to support development of the next generation reactors in the United States. The graphite experiments will be irradiated over the next six to eight years to support development of a graphite irradiation performance data base on the new nuclear grade graphites now available for use in high temperature gas reactors. The goals of the irradiation experiments are to obtain irradiation performance data at different temperatures and loading conditions to support design of the Next Generation Nuclear Plant Very High Temperature Gas Reactor, as well as other future gas reactors. The experiments will each consist of a single capsule that will contain seven separate stacks of graphite specimens. Six of the specimen stacks will have half of their graphite specimens under a compressive load, while the other half of the specimens will not be subjected to a compressive load during irradiation. The six stacks will be organized into pairs with a different compressive load being applied to the top half of each pair of specimen stacks. The seventh stack will not have a compressive load on the graphite specimens during irradiation. The specimens will be irradiated in an inert sweep gas atmosphere with on-line temperature and compressive load monitoring and control. There will also be the capability of sampling the sweep gas effluent to determine if any oxidation or off-gassing of the specimens occurs during initial start-up of the experiment. The final design phase for the first experiment was completed in September 2008, and the fabrication and assembly of the experiment test train as well as installation and testing of the control and support systems that will monitor and control the experiment during irradiation are being completed in early calendar 2009. The first experiment is scheduled to be ready for insertion in the ATR by April 30, 2009. This paper will discuss the design of the experiment including the test train and the temperature and compressive load monitoring, control, and data collection systems.

S. Blaine Grover

2009-05-01T23:59:59.000Z

268

Addendum to the User's Guide for RIVRISK Version 5.0: A Model to Assess Potential Human Health and Ecological Risks from Power Plant and Industrial Facility Releases to Rivers  

Science Conference Proceedings (OSTI)

This is an addendum to the User's Guide for EPRI's RIVRISK analytic framework, Version 5.0. RIVRISK can be used to assess human health and ecological risks associated with industrial and power plant chemical and thermal releases to rivers. Some minor inconsistencies between the original User's Guide (EPRI Report 1000733) and the model examples were discovered during model applications. This addendum provides modified pages of the User's Guide that correct those inconsistencies. Those planning to use RIVR...

2001-05-04T23:59:59.000Z

269

WIPP News Release Archives Index  

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

WIPP News Release Archives 2006 News Releases 2005 News Releases 2004 News Releases 2003 News Releases 2002 News Releases 2001 News Releases 2000 News Releases 1999 News Releases...

270

Final Green Zia Award Release  

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

Plant P.O. Box 3090 Carlsbad, New Mexico 88221 For Immediate Release WIPP Receives Green Zia Award for Environmental Excellence CARLSBAD, N.M., August 16, 2012- The Waste...

271

EPRI Ergonomics Handbook for the Electric Power Industry: Ergonomic Interventions for Plant Operators and Mechanics in Fossil-Fueled Generating Stations  

Science Conference Proceedings (OSTI)

The EPRI Occupational Health and Safety (OHS) Committee Research Program has provided ergonomic information to the electric energy industry workforce since 1999. This is the sixth EPRI ergonomics handbook; it specifically focuses on tasks performed by plant operators and mechanics working in fossil-fueled generating stations and also addresses some tasks performed by steam services technicians. Fossil-fueled generating station operational and mechanical work is physically strenuous and can expose workers...

2008-12-15T23:59:59.000Z

272

On-Line Monitoring and Diagnostics of the Integrity of Nuclear Plant Steam Generators and Heat Exchangers.  

SciTech Connect

The overall purpose of this Nuclear Engineering Education Research (NEER) project was to integrate new, innovative, and existing technologies to develop a fault diagnostics and characterization system for nuclear plant steam generators (SG) and heat exchangers (HX). Issues related to system level degradation of SG and HX tubing, including tube fouling, performance under reduced heat transfer area, and the damage caused by stress corrosion cracking, are the important factors that influence overall plant operation, maintenance, and economic viability of nuclear power systems. The research at The University of Tennessee focused on the development of techniques for monitoring process and structural integrity of steam generators and heat exchangers. The objectives of the project were accomplished by the completion of the following tasks. All the objectives were accomplished during the project period. This report summarizes the research and development activities, results, and accomplishments during June 2001-September 2004. (1) Development and testing of a high-fidelity nodal model of a U-tube steam generator (UTSG) to simulate the effects of fouling and to generate a database representing normal and degraded process conditions. Application of the group method of data handling (GMDH) method for process variable prediction. (2) Development of a laboratory test module to simulate particulate fouling of HX tubes and its effect on overall thermal resistance. Application of the GMDH technique to predict HX fluid temperatures, and to compare with the calculated thermal resistance. (3) Development of a hybrid modeling technique for process diagnosis and its evaluation using laboratory heat exchanger test data. (4) Development and testing of a sensor suite using piezo-electric devices for monitoring structural integrity of both flat plates (beams) and tubing. Experiments were performed in air, and in water with and without bubbly flow. (5) Development of advanced signal processing methods using wavelet transforms and image processing techniques for isolating flaw types. (6) Development and implementation of a new nonlinear and non-stationary signal processing method, called the Hilbert-Huang transform (HHT), for flaw detection and location. This is a more robust and adaptive approach compared to the wavelet transform. (7) Implementation of a moving-window technique in the time domain for detecting and quantifying flaw types in tubular structures. A window zooming technique was also developed for flaw location in tubes. (8) Theoretical study of elastic wave propagation (longitudinal and shear waves) in metallic flat plates and tubing with and without flaws. (9) Simulation of the Lamb wave propagation using the finite-element code ABAQUS. This enabled the verification of the experimental results. The research tasks included both analytical research and experimental studies. The experimental results helped to enhance the robustness of fault monitoring methods and to provide a systematic verification of the analytical results. The results of this research were disseminated in scientific meetings. A journal manuscript was submitted for publication. The new findings of this research have potential applications in aerospace and civil structures. The report contains a complete bibliography that was developed during the course of the project.

Belle R. Upadhyaya; J. Wesley Hines

2004-09-27T23:59:59.000Z

273

DOE Releases Filing Instructions for Federal Risk Insurance for...  

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

Filing Instructions for Federal Risk Insurance for New Nuclear Power Plants DOE Releases Filing Instructions for Federal Risk Insurance for New Nuclear Power Plants December 21,...

274

Media Release Media Contact FOR IMMEDIATE RELEASE Heather Rasmussen  

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

Release Media Contact Release Media Contact FOR IMMEDIATE RELEASE Heather Rasmussen September 22, 2011 Communication Specialist (801) 819-7623 hrasmussen@wecc.biz WECC releases its first-ever transmission plan for the Western Interconnection The Western Electricity Coordinating Council (WECC) announced the release of its first 10-Year Regional Transmission Plan (Plan) for the Western Interconnection. Looking ahead to 2020, the Plan focuses on how to meet the Western Interconnection's transmission requirements; including transmission expansion, new generation development, adapting to local, state/provincial, and federal policy changes, and their associated financial and environmental costs.

275

Advanced techniques for safety analysis applied to the gas turbine control system of ICARO co-generative plant  

E-Print Network (OSTI)

The paper describes two complementary and integrable approaches, a probabilistic one and a deterministic one, based on classic and advanced modelling techniques for safety analysis of complex computer based systems. The probabilistic approach is based on classical and innovative probabilistic analysis methods. The deterministic approach is based on formal verification methods. Such approaches are applied to the gas turbine control system of ICARO co generative plant, in operation at ENEA CR Casaccia. The main difference between the two approaches, behind the underlining different theories, is that the probabilistic one addresses the control system by itself, as the set of sensors, processing units and actuators, while the deterministic one also includes the behaviour of the equipment under control which interacts with the control system. The final aim of the research, documented in this paper, is to explore an innovative method which put the probabilistic and deterministic approaches in a strong relation to overcome the drawbacks of their isolated, selective and fragmented use which can lead to inconsistencies in the evaluation results. 1.

Ro Bologna; Ester Ciancamerla; Piero Incalcaterra; Michele Minichino; Andrea Bobbio; Università Del Piemonte Orientale; Enrico Tronci

2001-01-01T23:59:59.000Z

276

Modeling a Printed Circuit Heat Exchanger with RELAP5-3D for the Next Generation Nuclear Plant  

Science Conference Proceedings (OSTI)

The main purpose of this report is to design a printed circuit heat exchanger (PCHE) for the Next Generation Nuclear Plant and carry out Loss of Coolant Accident (LOCA) simulation using RELAP5-3D. Helium was chosen as the coolant in the primary and secondary sides of the heat exchanger. The design of PCHE is critical for the LOCA simulations. For purposes of simplicity, a straight channel configuration was assumed. A parallel intermediate heat exchanger configuration was assumed for the RELAP5 model design. The RELAP5 modeling also required the semicircular channels in the heat exchanger to be mapped to rectangular channels. The initial RELAP5 run outputs steady state conditions which were then compared to the heat exchanger performance theory to ensure accurate design is being simulated. An exponential loss of pressure transient was simulated. This LOCA describes a loss of coolant pressure in the primary side over a 20 second time period. The results for the simulation indicate that heat is initially transferred from the primary loop to the secondary loop, but after the loss of pressure occurs, heat transfers from the secondary loop to the primary loop.

Not Available

2010-12-01T23:59:59.000Z

277

The Next Generation Nuclear Plant/Advanced Gas Reactor Fuel Irradiation Experiments in the Advanced Test Reactor  

SciTech Connect

The United States Department of Energy’s Next Generation Nuclear Plant (NGNP) Program will be irradiating eight separate low enriched uranium (LEU) tri-isotopic (TRISO) particle fuel (in compact form) experiments in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). The ATR has a long history of irradiation testing in support of reactor development and the INL has been designated as the new United States Department of Energy’s lead laboratory for nuclear energy development. The ATR is one of the world’s premiere test reactors for performing long term, high flux, and/or large volume irradiation test programs. These irradiations and fuel development are being accomplished to support development of the next generation reactors in the United States, and will be irradiated over the next ten years to demonstrate and qualify new particle fuel for use in high temperature gas reactors. The goals of the irradiation experiments are to provide irradiation performance data to support fuel process development, to qualify fuel for normal operating conditions, to support development and validation of fuel performance and fission product transport models and codes, and to provide irradiated fuel and materials for post irradiation examination (PIE) and safety testing. The experiments, which will each consist of at least six separate capsules, will be irradiated in an inert sweep gas atmosphere with individual on-line temperature monitoring and control of each capsule. The sweep gas will also have on-line fission product monitoring on its effluent to track performance of the fuel in each individual capsule during irradiation. The first experiment (designated AGR-1) started irradiation in December 2006, and the second experiment (AGR-2) is currently in the design phase. The design of test trains, as well as the support systems and fission product monitoring system that will monitor and control the experiment during irradiation will be discussed. In addition, the purpose and differences between the two experiments will be compared and the irradiation results to date on the first experiment will be presented.

S. Blaine Grover

2009-09-01T23:59:59.000Z

278

NREL: News - Release Archives 2005  

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

Solar Thermal Electric Generating Plant in Boulder City, Nev. September 29, 2005 NREL, Xcel Energy Sign Photovoltaic Development Agreement The U.S. Department of Energy's (DOE)...

279

Generating capacity of the united power system of Russia and conditions of fuel supply to electric power plants for the period up to 2020  

SciTech Connect

Prospects of development of the energy economy in Russia are considered up to 2020. The proportion of thermal power plants (TPP) in the structure of the generating capacity of Russia amounts to about 70% (147 mln kW). The proportion of gas in the structure of fuel consumed by TPP amounts to 64%. It is predicted that the fraction of high-quality kinds of fuel (gas and fuel oil) will decrease in the considered period due to maximum involvement of coal in the fuel balance and wider use of combined-cycle and gas-turbine technologies that provide a lower specific consumption of fuel. It is planned to resort to advanced technologies both for reconstructing existing plants and erecting new ones. This paper deals with problems of fuel supply of fossil-fuel-fired thermal power plants in the light of the evolution of the energy economy of Russia. The demand of TPP for different kinds of fossil fuel, i.e., gas, coal, and fuel oil, is estimated for the whole of the country and for its regions according to two variants of development of the generating capacity with planned commissioning of combined-cycle plants with a total output of 32 mln kW and gas-turbine plants with a total output of 61 mln kW in the period of up to 2020. The tasks of the fuel policy to be solved in the considered period are presented.

V.I. Chemodanov; N.V. Bobyleva; N.G. Chelnokova; N.Yu. Sokolova [Energoset'proekt Institute, Moscow (Russian Federation)

2002-05-15T23:59:59.000Z

280

Techno-economic analysis of using corn stover to supply heat and power to a corn ethanol plant - Part 2: Cost of heat and power generation systems  

Science Conference Proceedings (OSTI)

This paper presents a techno-economic analysis of corn stover fired process heating (PH) and the combined heat and power (CHP) generation systems for a typical corn ethanol plant (ethanol production capacity of 170 dam3). Discounted cash flow method was used to estimate both the capital and operating costs of each system and compared with the existing natural gas fired heating system. Environmental impact assessment of using corn stover, coal and natural gas in the heat and/or power generation systems was also evaluated. Coal fired process heating (PH) system had the lowest annual operating cost due to the low fuel cost, but had the highest environmental and human toxicity impacts. The proposed combined heat and power (CHP) generation system required about 137 Gg of corn stover to generate 9.5 MW of electricity and 52.3 MW of process heat with an overall CHP efficiency of 83.3%. Stover fired CHP system would generate an annual savings of 3.6 M$ with an payback period of 6 y. Economics of the coal fired CHP system was very attractive compared to the stover fired CHP system due to lower fuel cost. But the greenhouse gas emissions per Mg of fuel for the coal fired CHP system was 32 times higher than that of stover fired CHP system. Corn stover fired heat and power generation system for a corn ethanol plant can improve the net energy balance and add environmental benefits to the corn to ethanol biorefinery.

Mani, Sudhagar [University of Georgia; Sokhansanj, Shahabaddine [ORNL; Togore, Sam [U.S. Department of Energy; Turhollow Jr, Anthony F [ORNL

2010-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "generating plants release" 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

Press release For Immediate Release Seattle, USA. June 6, 2008  

E-Print Network (OSTI)

Press release ­ For Immediate Release Seattle, USA. June 6, 2008 Global trade of woody biomass has almost doubled in five years With the increasing demand for woody biomass, global trade of particularly fiber source for energy generation but because of higher demand for renewable energy and increasing

282

Voltage security assessment with high penetration levels of utility-scale doubly fed induction generator wind plants.  

E-Print Network (OSTI)

??The interconnection requirements set forth by FERC in order 661-A mandate the operation of wind plants within a power factor range of 0.95 leading /… (more)

Konopinski, Ryan

2009-01-01T23:59:59.000Z

283

--PRESS RELEASE--  

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

NEWS RELEASE NEWS RELEASE Global Energy, Inc. For Immediate Release GLOBAL ENERGY INC. AND WABASH VALLEY POWER RELAUNCH WABASH GASIFICATION FACILITY AS SG SOLUTIONS LLC Cincinnati and Indianapolis, February 7, 2005 - Global Energy Inc. and Wabash Valley Power Association announced today that they have formed SG Solutions LLC to move the Wabash Gasification Facility forward to achieve base load operations and future growth. SG Solutions LLC (SGS) is owned 50/50 by Wabash Valley Power Association and Wabash River Energy, a unit of Global Energy Inc. In recent years the Wabash Gasification Facility has operated under a demanding market-based contract which challenged the operation to make very low cost synthetic gas. As a result, Wabash has consistently produced synthetic gas with a

284

The analysis and specification of large high-pressure, high-temperature valves for combustion turbine protection in second-generation PFB power plants: Topical report  

SciTech Connect

The purpose of this study was to provide a specification for the high-pressure/high-temperature valves for turbine overspeed protection in a commercial-scale second-generation pressurized fluidized bed combustion (PFBC) power plant. In the event of a loss of external (generator) load, the gas turbine rapidly accelerates from its normal operating speed. Protection from excessive overspeed can be maintained by actuation of fuel isolation and air bypass valves. A design specification for these valves was developed by analyses of the turbine/compressor interaction during a loss of load and analyses of pressure and flow transients during operation of the overspeed protection valves. The basis for these analyses was the Phase 1 plant conceptual design prepared in 1987.

1994-08-01T23:59:59.000Z

285

CO2 Capture from Coal-Fired Utility Generation Plant Exhausts and Sequestration by a Biomimetic Route Based on Enzymatic Catalysts-Current Status  

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

from Coal-Fired Utility Generation Plant Exhausts, and from Coal-Fired Utility Generation Plant Exhausts, and Sequestration by a Biomimetic Route Based on Enzymatic Catalysis - Current Status Gillian M. Bond (gbond@nmt.edu; 505-835-5653) Margaret-Gail Medina (magail@nmt.edu; 505-835-5229) New Mexico Tech 801 Leroy Socorro, NM 87801 John Stringer (jstringe@epri.com; 650-855-2472) Electric Power Research Institute 3412 Hillview Avenue Palo Alto, CA 94304 F. Arzum Simsek-Ege (fatma.a.simsek-egel@intel.com; 505-893-8694) Intel Corporation Albuquerque, New Mexico Introduction A range of carbon management strategies will have to be implemented if meaningful reductions in CO 2 emissions are to be achieved in response to concerns about global climate change. It is becoming increasingly clear that some form or forms of carbon

286

Economic Evaluation of By-Product Power/Co-Generation Systems for Industrial Plants with Fluidized-Bed Coal Burning Facilities  

E-Print Network (OSTI)

Economic analysis of the construction and operation of by-product electric power and steam/power cogeneration systems in coal fired fluidized-bed steam cycles, located at individual industrial sites analyzed by the author, is being presented. The plants analyzed employ fluidized bed boilers for generation of steam for process and building/heating/cooling demands, in conjunction with electric power co-generation. Results of the analysis are presented, using life cycle costs and investment payback periods, pinpointing the areas, type and magnitude of costs which should be considered in the selection of combustors or systems. Capital and operating costs, and recognized technical and economic barriers are also presented and their effects indicated. Life cycle cost of each of the alternatives analyzed are compared and the expected payback periods for the different size FBC plants and for different annual average production levels are discussed.

Mesko, J. E.

1980-01-01T23:59:59.000Z

287

Maintaining a Technology-Neutral Approach to Hydrogen Production Process Development through Conceptual Design of the Next Generation Nuclear Plant  

DOE Green Energy (OSTI)

The Next Generation Nuclear Plant (NGNP) project was authorized in the Energy Policy Act of 2005 (EPAct), tasking the U.S. Department of Energy (DOE) with demonstrating High Temperature Gas-Cooled Reactor (HTGR) technology. The demonstration is to include the technical, licensing, operational, and commercial viability of HTGR technology for the production of electricity and hydrogen. The Nuclear Hydrogen Initiative (NHI), a component of the DOE Hydrogen Program managed by the Office of Nuclear Energy, is also investigating multiple approaches to cost effective hydrogen production from nuclear energy. The objective of NHI is development of the technology and information basis for a future decision on commercial viability. The initiatives are clearly intertwined. While the objectives of NGNP and NHI are generally consistent, NGNP has progressed to the project definition phase and the project plan has matured. Multiple process applications for the NGNP require process heat, electricity and hydrogen in varied combinations and sizes. Coupling these processes to the reactor in multiple configurations adds complexity to the design, licensing and demonstration of both the reactor and the hydrogen production process. Commercial viability of hydrogen production may depend on the specific application and heat transport configuration. A component test facility (CTF) is planned by the NGNP to support testing and demonstration of NGNP systems, including those for hydrogen production, in multiple configurations. Engineering-scale demonstrations in the CTF are expected to start in 2012 to support scheduled design and licensing activities leading to subsequent construction and operation. Engineering-scale demonstrations planned by NHI are expected to start at least two years later. Reconciliation of these schedules is recommended to successfully complete both initiatives. Hence, closer and earlier integration of hydrogen process development and heat transport systems is sensible. For integration purposes, an analysis comparing the design, cost and schedule impact of maintaining a technology neutral approach through conceptual design or making an early hydrogen process technology selection was performed. Early selection does not specifically eliminate a technology, but rather selects the first hydrogen technology for demonstration. A systems-engineering approach was taken to define decision-making criteria for selecting a hydrogen technology. The relative technical, cost and schedule risks of each approach were analyzed and risk mitigation strategies were recommended, including provisions to maintain close collaboration with the NHI. The results of these analyses are presented here.

Michael W. Patterson

2008-05-01T23:59:59.000Z

288

Illinois Nuclear Profile - Dresden Generating Station  

U.S. Energy Information Administration (EIA)

Nuclear Power Plant Data for Dresden Generating Station Author: DOE/EIA Keywords: Dresden Generating Station, Illinois, Nuclear, Plant, Reactor, Generation, Capacity

289

Press Release  

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

Press Release Press Release LLNL garners 'Best in Class' award from NNSA April 30, 2012 WASHINGTON, D.C. - The National Nuclear Security Administration (NNSA) today congratulated its national laboratories and sites for achievements in environmental stewardship, awarding a total of 24 Pollution Prevention (P2) Awards for innovative initiatives across the enterprise. The P2 Awards recognize performance in integrating environmental stewardship practices that helps to reduce risk, protect natural resources and enhance site operations. "I applaud the work done at NNSA's sites in finding creative ways to reduce the environmental impact of our work," said NNSA's Deputy Administrator for

290

Protection from ground faults in the stator winding of generators at power plants in the Siberian networks  

SciTech Connect

The experience of many years of experience in developing and utilization of ground fault protection in the stator winding of generators in the Siberian networks is generalized. The main method of protection is to apply a direct current or an alternating current with a frequency of 25 Hz to the primary circuits of the stator. A direct current is applied to turbo generators operating in a unit with a transformer without a resistive coupling to the external grid or to other generators. Applying a 25 Hz control current is appropriate for power generation systems with compensation of a capacitive short circuit current to ground. This method forms the basis for protection of generators operating on busbars, hydroelectric generators with a neutral grounded through an arc-suppression reactor, including in consolidated units with generators operating in parallel on a single low-voltage transformer winding.

Vainshtein, R. A., E-mail: vra@tpu.ru [Tomsk Polytechnical University (Russian Federation); Lapin, V. I. [ODU Sibiri (Integrated Dispatcher Control for Siberia), branch of JSC 'SO EES' (Russian Federation); Naumov, A. M.; Doronin, A. V. [JSC NPP 'EKRA' (Russian Federation); Yudin, S. M. [Tomsk Polytechnical University (Russian Federation)

2010-05-15T23:59:59.000Z

291

Conceptual design and cost evaluation of organic Rankine cycle electric generating plant powered by medium temperature geothermal water  

DOE Green Energy (OSTI)

The economic production of electrical power from high temperature steam and liquid dominated geothermal resources has been demonstrated. Large quantities of geothermal energy are considered to exist at moderate temperatures, however, the economics of converting this energy into electricity has not been established. This paper presents the design concept of a dual boiler isobutane cycle selected for use with the moderate temperature hydrothermal resource and presents a cost estimate for a 10 and 50 MW power plant. Cost of electrical power from these plants is estimated and compared with that from coal, oil and nuclear plants. The impact of selling a portion of the residual heat in the geothermal effluent is assessed. (auth)

Dart, R.H.; Neill, D.T.; Whitbeck, J.F.

1975-12-01T23:59:59.000Z

292

The environmental behavior of transuranic nuclides released from water cooled nuclear power plants. Final report, 1 August 1977-31 December 1978  

Science Conference Proceedings (OSTI)

Release data are reported for three coastal water-cooled nuclear reactors: Millstone Point No. 1 and No. 2 (for the period January 1977 through April 1978), and Maine Yankee (for the period 20 June 1977 through 25 March 1978); release samples were analyzed for (55)Fe, (60)Co, (134)Cs, (137)Cs, (238)Pu, (239), (240)Pu, (241)Am, (242)Cm and (244)Cm, but not all nuclides on every sample. Radioiron is a major component of the releases measured; the transuranium nuclides are less significant components than was expected, but levels have occasionally reached microcuries per month. Pulses of this size are adequate for tracer studies. Environmental samples (water, sediments, and biota) have been analyzed from about the two reactor sites noted, and that of the Pilgrim No. 1 reactor. No water samples remote from reactor outflows have unequivocally shown reactor contamination. No sediment samples from near Millstone Point or Pilgrim 1 have shown reactor contamination; this has been clearly evident in several sediment collections from near Main Yankee.

Bowen, V.T.

1981-03-01T23:59:59.000Z

293

Unlimited Release  

E-Print Network (OSTI)

Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U. S. Department of Energy’s National Nuclear Security Administration under Contract DE-AC04-94AL85000. Approved for public release; further dissemination unlimited. SAND2012-7341P

unknown authors

2012-01-01T23:59:59.000Z

294

Unlimited Release  

E-Print Network (OSTI)

Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U. S. Department of Energy’s National Nuclear Security Administration under Contract DE-AC04-94AL85000. Approved for public release; further dissemination unlimited. SAND2012-7340P

unknown authors

2012-01-01T23:59:59.000Z

295

EIA - Distributed Generation in Buildings  

U.S. Energy Information Administration (EIA)

Modeling Distributed Generation in the Buildings Sectors . Supplement to the Annual Energy Outlook 2013 — Release date: August 29, 2013

296

EIA - Annual Energy Outlook 2013 Early Release  

U.S. Energy Information Administration (EIA)

Electricity generation from nuclear power plants grows by 14 percent in the AEO2013 Reference case, ... Electricity Trade : View More ...

297

EIA - Annual Energy Outlook 2013 Early Release  

U.S. Energy Information Administration (EIA)

Energy intensity; Energy production and imports; Electricity generation; Energy-related CO 2 emissions; ... Capital cost for electricity plants; ...

298

Steam Generator Management Program: Effects of Different pH Control Agents on Pressurized Water Reactor Plant Systems and Components  

Science Conference Proceedings (OSTI)

Corrosion of materials in the condensate, feedwater, and drain systems of PWRs generates a significant amount of corrosion products in the secondary cycle. These corrosion products are generally transported into the steam generators and deposit on tubing surfaces, tubesheets, and tube support plates. Increased corrosion results in elevated levels of undesired corrosion products being deposited into the steam generators. To minimize corrosion of the secondary system components, control of pH in the second...

2009-12-04T23:59:59.000Z

299

Preliminary Release: March 28, 2011",,,,,,,,,,,,"Released: April 2013","Released  

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

,,,,,,,,,,,,"Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013"

300

Probabilistic safety assessment and reliability based maintenance policies: application to the emergency diesel generators of a nuclear power plant  

Science Conference Proceedings (OSTI)

This study is performed on the four 2.5 MWe emergency diesel generator (EDG) sets of Hydro-Quebec Gentilly-2 Nuclear Power Station. EDGs are safety related systems for the case of the loss of off-site power. This study establishes the basis of an enhanced ... Keywords: emergency diesel generator, maintenance policy, probabilistic safety assessment

Georges Abdul-Nour; Michel Demers; Raynald Vaillancourt

2002-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "generating plants release" 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

Unlimited Release  

Office of Scientific and Technical Information (OSTI)

Unlimited Release Unlimited Release Printed November 1987 Proceedings of The Wellbore Sampling Workshop Richard K. Traeger, Barry W. Harding Prepared by Sandia National Laboratories Albuquerque, New Mexico 87185 and Livermore, California 9 4 5 5 0 f o r the United States Department of Energy . under Contract DE-AC04-76DP00789 DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency Thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately

302

Georgia Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

303

Arkansas Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

304

Iowa Nuclear Profile - Power Plants  

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

Iowa nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

305

Ohio Nuclear Profile - Power Plants  

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

Ohio nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

306

Vermont Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

307

Florida Nuclear Profile - Power Plants  

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

Florida nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

308

Virginia Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

309

Washington Nuclear Profile - Power Plants  

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

Washington nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State...

310

Missouri Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

311

Nebraska Nuclear Profile - Power Plants  

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

Nebraska nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

312

Tennessee Nuclear Profile - Power Plants  

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

Tennessee nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

313

Connecticut Nuclear Profile - Power Plants  

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

Connecticut nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State...

314

Minnesota Nuclear Profile - Power Plants  

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

Minnesota nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

315

California Nuclear Profile - Power Plants  

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

California nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State...

316

Arizona Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

317

Massachusetts Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

318

Kansas Nuclear Profile - Power Plants  

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

Kansas nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

319

Alabama Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

320

Wisconsin Nuclear Profile - Power Plants  

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

Wisconsin nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

Note: This page contains sample records for the topic "generating plants release" 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

Texas Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

322

Michigan Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

323

Mississippi Nuclear Profile - Power Plants  

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

Mississippi nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State...

324

Carbon-14 Background, Pathway, and Dose Calculation Analysis for Nuclear Power Plants: A Sourcebook for Accurate Carbon-14 Dose Calculations  

Science Conference Proceedings (OSTI)

Commercial nuclear power plants (NPPs) generate carbon-14 during operation, and release it in power plant effluents. This report explores the current state of carbon and carbon-14 science and understanding to identify and recommend any enhancements to carbon-14 dose calculation methodologies.BackgroundWhile the amount of carbon-14 released by NPPs is small compared to natural and other anthropogenic sources, it is important to accurately document it, along ...

2013-12-11T23:59:59.000Z

325

Doubly Fed Induction Generator in an Offshore Wind Power Plant Operated at Rated V/Hz: Preprint  

DOE Green Energy (OSTI)

This paper introduces the concept of constant Volt/Hz operation of offshore wind power plants. The deployment of offshore WPPs requires power transmission from the plant to the load center inland. Since this power transmission requires submarine cables, there is a need to use High-Voltage Direct Current transmission, which is economical for transmission distances longer than 50 kilometers. In the concept presented here, the onshore substation is operated at 60 Hz synced with the grid, and the offshore substation is operated at variable frequency and voltage, thus allowing the WPP to be operated at constant Volt/Hz.

Muljadi, E.; Singh, M.; Gevorgian, V.

2012-06-01T23:59:59.000Z

326

IMPROVEMENTS IN STEAM GENERATING AND SUPERHEATING PLANT AND AN IMPROVED METHOD OF PRODUCING LOW PRESSURE SUPERHEATED STEAM  

SciTech Connect

A steam supply arrangement is described which generates high-pressure steam and superheats steam from a low-pressure source. Inus, in operations cteam at 350 to 600 psi from a nuciear reactor is superheated in a heat exehanger anu later in gas-heated equipment to 1100 F and passed to a stage of a pluralstage steam turbine. When the reactor ls shut downs steam generated in the steam generator section may be passed directly to the gas-fired superheater. (T.R.H.)

1959-02-18T23:59:59.000Z

327

Hometown News Releases  

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

Publications Hometown News Releases News Releases issued in: 2011, 2010, 2009, 2008 October 18, 2013 NETL Researcher Honored with 2013 Federal Laboratory Consortium Award Morgantown, W.Va. - Dr. Stephen E. Zitney of the National Energy Technology Laboratory (NETL) has been awarded a Mid-Atlantic region Federal Laboratory Consortium (FLC) award for Excellence in Technology Transfer for his work on the 3D Virtual Energy Plant Simulator and Immersive Training System. October 18, 2013 NETL Researcher Honored with 2013 Federal Laboratory Consortium Award Albany, Ore. - Jeffrey Hawk of the National Energy Technology Laboratory (NETL) has been awarded a Far West region Federal Laboratory Consortium (FLC) award for Outstanding Technology Development for his work on Superior Heat Resistant Alloys through Controlled Homogenization.

328

Power Plant Profitability and Investment in the Central United States: Impact of New Gas Capacity on Generation and Repowering Economics  

Science Conference Proceedings (OSTI)

Over the past 12 months, announcements of capacity additions by 2005 in the midwest have jumped from 20,000 to 60,000 MW. This report examines how just a portion of this capacity, if built, could affect the profitability of new and existing power plants.

2000-12-11T23:59:59.000Z

329

Application of Data Stream Outlier Mining Techniques in Steam Generator Safety Early Warning System of Nuclear Power Plant  

Science Conference Proceedings (OSTI)

Mining outliers in data streams is a popular research issue in data mining field, which can help to find outliers under abnormal condition and then corresponding measures can be taken. The security guarantee of nuclear power plant is the center topic ... Keywords: safety early warning system, data stream, outlier mining, NPP

Liu Dingping, Zheng Kaitao, Yan Qiqi

2013-01-01T23:59:59.000Z

330

Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) Volume 3: Fission-Product Transport and Dose PIRTs  

SciTech Connect

This Fission Product Transport (FPT) Phenomena Identification and Ranking Technique (PIRT) report briefly reviews the high-temperature gas-cooled reactor (HTGR) FPT mechanisms and then documents the step-by-step PIRT process for FPT. The panel examined three FPT modes of operation: (1) Normal operation which, for the purposes of the FPT PIRT, established the fission product circuit loading and distribution for the accident phase. (2) Anticipated transients which were of less importance to the panel because a break in the pressure circuit boundary is generally necessary for the release of fission products. The transients can change the fission product distribution within the circuit, however, because temperature changes, flow perturbations, and mechanical vibrations or shocks can result in fission product movement. (3) Postulated accidents drew the majority of the panel's time because a breach in the pressure boundary is necessary to release fission products to the confinement. The accidents of interest involved a vessel or pipe break, a safety valve opening with or without sticking, or leak of some kind. Two generic scenarios were selected as postulated accidents: (1) the pressurized loss-of-forced circulation (P-LOFC) accident, and (2) the depressurized loss-of-forced circulation (D-LOFC) accidents. FPT is not an accident driver; it is the result of an accident, and the PIRT was broken down into a two-part task. First, normal operation was seen as the initial starting point for the analysis. Fission products will be released by the fuel and distributed throughout the reactor circuit in some fashion. Second, a primary circuit breach can then lead to their release. It is the magnitude of the release into and out of the confinement that is of interest. Depending on the design of a confinement or containment, the impact of a pressure boundary breach can be minimized if a modest, but not excessively large, fission product attenuation factor can be introduced into the release path. This exercise has identified a host of material properties, thermofluid states, and physics models that must be collected, defined, and understood to evaluate this attenuation factor. The assembled PIRT table underwent two iterations with extensive reorganization between meetings. Generally, convergence was obtained on most issues, but different approaches to the specific physics and transport paths shade the answers accordingly. The reader should be cautioned that merely selecting phenomena based on high importance and low knowledge may not capture the true uncertainty of the situation. This is because a transport path is composed of several serial linkages, each with its own uncertainty. The propagation of a chain of modest uncertainties can lead to a very large uncertainty at the end of a long path, resulting in a situation that is of little regulatory guidance.

Morris, Robert Noel [ORNL

2008-03-01T23:59:59.000Z

331

Plant power : the cost of using biomass for power generation and potential for decreased greenhouse gas emissions  

E-Print Network (OSTI)

To date, biomass has not been a large source of power generation in the United States, despite the potential for greenhouse gas (GHG) benefits from displacing coal with carbon neutral biomass. In this thesis, the fuel cycle ...

Cuellar, Amanda Dulcinea

2012-01-01T23:59:59.000Z

332

Final report of the TWRS Plant Implementation Team to review potential reactive component in tank 241-T-111 and methane in tank 241-SY-101 gas release event  

SciTech Connect

This is the final report of the results of a Tank Waste Remediation Systems Plant Implementation Team chartered by TWRS Operations, in response to a potential Unreviewed Safety Question (USQ) due to the discovery of a reactive component in waste tank 241-T-111 (T-111). Tank T-111, a non-Watch List single-shell tank, has no historical evidence of any potential safety problems. Core samples from tank T-111 were taken in 1991 and analyzed in 1992. The presence of uncharacterized exotherms was identified in the first three segments of two cores and reported to tank farm management in November 1993.

Engelman, D.B.

1994-02-01T23:59:59.000Z

333

Proposal for the Award of a Contract for the Supply and Installation of a gas Turbine for Combined Generation of Electricity and Heat in the Heating Plant on the Meyrin Site  

E-Print Network (OSTI)

Proposal for the Award of a Contract for the Supply and Installation of a gas Turbine for Combined Generation of Electricity and Heat in the Heating Plant on the Meyrin Site

1994-01-01T23:59:59.000Z

334

POWER PLANT RELIABILITY-AVAILABILITY AND STATE REGULATION. VOLUME 7 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

which steam is raised. nuclear fuel generates heat that isattention to nuclear and fossil-fuel plants, and these areFor all the fossil-fuel and nuclear (However, categories,

Nero, A.V.

2010-01-01T23:59:59.000Z

335

Plant Support Engineering: Guidance for Managing the Impact of Procured Item Quality Issues on Generating Asset Economic Performance  

Science Conference Proceedings (OSTI)

In 2007, EPRI Plant Support Engineering (PSE) published Technical Update 1015171, Procured Item Quality Initiative, Initial Findings, as the initial output from the Technical Advisory Group (TAG) for the EPRI Procured Item Quality Initiative. The update categorized data about procured item quality issues provided by TAG members, summarized the analysis performed, and provided initial conclusions. In addition, the update identified types of items for which quality concerns exist and summarized potential c...

2008-07-08T23:59:59.000Z

336

CHANGING RELEASE CRITERIA FROM PAST TO PRESENT  

SciTech Connect

Beginning with the decommissioning of nuclear power plants the release, criteria for radioactive materials has gained importance significantly. After decommissioning and dismantling, most of the residues need not be treated as radioactive waste, since they contain only small amounts of radioactivity. The Karlsruhe Research Center already dismantled two research reactors completely (the Karlstein Super Heated Steam Reactor and the Niederaichbach Nuclear Power Plant), while several additional decommissioning projects are currently in progress. About 70 % of the total waste mass within each project can be released from the area of atomic regulations and licenses. At the Niederaichbach and Karlstein sites the release procedures and the release criteria were determined in the decommissioning license, where issues such as controlling and release values were fixed. Additionally, each step of the release process has to be coordinated with the regulator. Today the general release criteria are contained in the atomic act. Depending on the nature of the material to be released (e.g. building structures or metallic waste), and depending on the further use of the material, such as unrestricted reuse or waste disposal, release values for each nuclide are established. To prepare the release of materials, a release plan including the release measurement results is sent to the regulator, who has to officially approve the concept.

Graf, A.; Valencia, L.

2003-02-27T23:59:59.000Z

337

Press Pass - Press Releases  

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

to the Fermilab press release mailing list. Press Releases Recent Releases Discovery of rare decay narrows space for new physics - 071913 Giant electromagnet to conclude its...

338

Biomass Allocation Data Set Released February 19, 2004  

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

Set Released February 19, 2004 The ORNL DAAC announces the release of the data set "Biomass Allocation and Growth Data of Seeded Plants." This data set of leaf, stem, and root...

339

Tests of Types 51A and 51M Steam Generators at Bugey 4 and Tricastin 1 Nuclear Power Plants  

Science Conference Proceedings (OSTI)

This report presents thermal-hydraulic and chemical sampling data obtained at various power levels from special instrumentation on Electricite de France's operating steam generators at Bugey-4 and Tricastin-1. The data include downcomer flow rates, shell temperatures, and temperatures and chemical concentrations near the secondary surface of tubesheets. These data are useful for qualifying thermal-hydraulic computer codes.

1982-10-01T23:59:59.000Z

340

Virtually simulating the next generation of clean energy technologies: NETL's AVESTAR Center is dedicated to the safe, reliable and efficient operation of advanced energy plants with carbon capture  

SciTech Connect

Imagine using a real-time virtual simulator to learn to fly a space shuttle or rebuild your car's transmission without touching a piece of equipment or getting your hands dirty. Now, apply this concept to learning how to operate and control a state-of-the-art, electricity-producing power plant capable of carbon dioxide (CO{sub 2}) capture. That's what the National Energy Technology Laboratory's (NETL) Advanced Virtual Energy Simulation Training and Research (AVESTAR) Center (www.netl.doe.gov/avestar) is designed to do. Established as part of the Department of Energy's (DOE) initiative to advance new clean energy technology for power generation, the AVESTAR Center focuses primarily on providing simulation-based training for process engineers and energy plant operators, starting with the deployment of a first-of-a-kind operator training simulator for an integrated gasification combined cycle (IGCC) power plant with CO{sub 2} capture. The IGCC dynamic simulator builds on, and reaches beyond, conventional power plant simulators to merge, for the first time, a 'gasification with CO{sub 2} capture' process simulator with a 'combined-cycle' power simulator. Based on Invensys Operations Management's SimSci-Esscor DYNSIM software, the high-fidelity dynamic simulator provides realistic training on IGCC plant operations, including normal and faulted operations, as well as plant start-up, shutdown and power demand load changes. The highly flexible simulator also allows for testing of different types of fuel sources, such as petcoke and biomass, as well as co-firing fuel mixtures. The IGCC dynamic simulator is available at AVESTAR's two locations, NETL (Figure 1) and West Virginia University's National Research Center for Coal and Energy (www.nrcce.wvu.edu), both in Morgantown, W.Va. By offering a comprehensive IGCC training program, AVESTAR aims to develop a workforce well prepared to operate, control and manage commercial-scale gasification-based power plants with CO{sub 2} capture. The facility and simulator at West Virginia University promotes NETL's outreach mission by offering hands-on simulator training and education to researchers and university students.

Zitney, S.

2012-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "generating plants release" 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

Low Cost Sorbent for Capturing CO{sub 2} Emissions Generated by Existing Coal-fired Power Plants  

SciTech Connect

TDA Research, Inc. has developed a novel sorbent based post-combustion CO{sub 2} removal technology. This low cost sorbent can be regenerated with low-pressure (ca. 1 atm) superheated steam without temperature swing or pressure-swing. The isothermal and isobaric operation is a unique and advantageous feature of this process. The objective of this project was to demonstrate the technical and economic merit of this sorbent based CO{sub 2} capture approach. Through laboratory, bench-scale and field testing we demonstrated that this technology can effectively and efficiently capture CO{sub 2} produced at an existing pulverized coal power plants. TDA Research, Inc is developing both the solid sorbent and the process designed around that material. This project addresses the DOE Program Goal to develop a capture technology that can be added to an existing or new coal fired power plant, and can capture 90% of the CO{sub 2} produced with the lowest possible increase in the cost of energy. .

Elliott, Jeannine

2013-08-31T23:59:59.000Z

342

RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

U. S. Conunercial Nuclear Power Plants", Report WASH-1400 (for Light-Water Cooled Nuclear Power Plants to Assess PlantStandards for Nuclear Power Plants," by A.V. Nero and Y.C.

Nero, A.V.

2010-01-01T23:59:59.000Z

343

Soil Data Release, Aug. 18, 2000  

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

Release, Aug. 18 The ORNL DAAC now offers a data set entitled "Global Distribution of Plant-Extractable Water Capacity of Soil (Dunne)." The data set was added to the holdings in...

344

Next Generation Nuclear Plant Project Technology Development Roadmaps: The Technical Path Forward for 750–800°C Reactor Outlet Temperature  

Science Conference Proceedings (OSTI)

This document presents the NGNP Critical PASSCs and defines their technical maturation path through Technology Development Roadmaps (TDRMs) and their associated Technology Readiness Levels (TRLs). As the critical PASSCs advance through increasing levels of technical maturity, project risk is reduced and the likelihood of within-budget and on-schedule completion is enhanced. The current supplier-generated TRLs and TDRMs for a 750–800°C reactor outlet temperature (ROT) specific to each supplier are collected in Appendix A.

John Collins

2009-08-01T23:59:59.000Z

345

SRP radioactive waste releases. Startup through 1959  

SciTech Connect

This report summarizes and documents radioactive waste released to the environs of the Savannah River Plant from startup through 1959. During this period, the quantity of beta-emitting radioisotopes released was determined by a total or ``gross`` analysis. However, advanced instrumentation and technology now permit an economical determination of most individual radionuclides. Therefore, future waste audit reports, beginning with January 1960, will record the quantity of specific radioisotopes released rather than gross amounts.

Ashley, C.

1960-09-01T23:59:59.000Z

346

Annual Steam-Electric Plant Operation and Design Data (EIA-767 data file)  

Gasoline and Diesel Fuel Update (EIA)

Electricity data files > Form EIA-767 Electricity data files > Form EIA-767 Form EIA-767 historical data files Data Released: November 02, 2006 Next Release: None(discontinued) Annual steam-electric plant operation and design data Historical data files contain annual data from organic-fueled or combustible renewable steam-electric plants with a generator nameplate rating of 10 or more megawatts. The data are derived from the Form EIA-767 "Steam-Electric Plant Operation and Design Report." The files contains data on plant operations and equipment design (including boilers, generators, cooling systems, flue gas desulfurizations, flue gas particulate collectors, and stacks). Beginning in the data year 2001, nuclear plant data were no longer collected by the survey.

347

Theoretical Design of a Thermosyphon for Efficient Process Heat Removal from Next Generation Nuclear Plant (NGNP) for Production of Hydrogen  

DOE Green Energy (OSTI)

The work reported here is the preliminary analysis of two-phase Thermosyphon heat transfer performance with various alkali metals. Thermosyphon is a device for transporting heat from one point to another with quite extraordinary properties. Heat transport occurs via evaporation and condensation, and the heat transport fluid is re-circulated by gravitational force. With this mode of heat transfer, the thermosyphon has the capability to transport heat at high rates over appreciable distances, virtually isothermally and without any requirement for external pumping devices. For process heat, intermediate heat exchangers (IHX) are required to transfer heat from the NGNP to the hydrogen plant in the most efficient way possible. The production of power at higher efficiency using Brayton Cycle, and hydrogen production requires both heat at higher temperatures (up to 1000oC) and high effectiveness compact heat exchangers to transfer heat to either the power or process cycle. The purpose for selecting a compact heat exchanger is to maximize the heat transfer surface area per volume of heat exchanger; this has the benefit of reducing heat exchanger size and heat losses. The IHX design requirements are governed by the allowable temperature drop between the outlet of the NGNP (900oC, based on the current capabilities of NGNP), and the temperatures in the hydrogen production plant. Spiral Heat Exchangers (SHE’s) have superior heat transfer characteristics, and are less susceptible to fouling. Further, heat losses to surroundings are minimized because of its compact configuration. SHEs have never been examined for phase-change heat transfer applications. The research presented provides useful information for thermosyphon design and Spiral Heat Exchanger.

Piyush Sabharwall; Fred Gunnerson; Akira Tokuhiro; Vivek Utgiker; Kevan Weaver; Steven Sherman

2007-10-01T23:59:59.000Z

348

Unlimited Release  

E-Print Network (OSTI)

Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy’s National Nuclear Security Administration under Contract DE-AC04-94AL85000. Approved for public release, further dissemination unlimited. Issued by Sandia National Laboratories, operated for the United States Department of Energy by Sandia Corporation. NOTICE: This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government, nor any agency thereof, nor any of their employees, nor any of their contractors, subcontractors, or their employees, make any warranty, express or implied, or assume any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represent that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government, any agency thereof, or any of their contractors or subcontractors. The views and opinions expressed herein do not necessarily state or reflect those of the United States Government, any agency thereof,

B. L. Larsen; Barbara L. Larsen

2011-01-01T23:59:59.000Z

349

NETL: News Release -Redesigned CCS Website Offers Wealth of Informatio...  

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

greenhouse gases from large stationary sources, such as power plants and refineries, and storing them in ways that prevent their release to the atmosphere-is a...

350

Evaluation of Peak Heat Release Rates in Electrical Cabinet Fires  

Science Conference Proceedings (OSTI)

The purpose of this report is to reanalyze the peak heat release rates (HRRs) from fires occurring in electrical cabinets of nuclear power plants.

2012-02-23T23:59:59.000Z

351

Radionuclide release calculations for selected severe accident scenarios  

Science Conference Proceedings (OSTI)

This report provides the results of source term calculations that were performed in support of the NUREG-1150 study. Severe Accident Risks: An Assessment for Five US Nuclear Power Plants.'' This is the sixth volume of a series of reports. It supplements results presented in the earlier volumes. Analyses were performed for three of the NUREG-1150 plants: Peach Bottom, a Mark I, boiling water reactor; Surry, a subatmospheric containment, pressurized water reactor; and Sequoyah, an ice condenser containment, pressurized water reactor. Complete source term results are presented for the following sequences: short term station blackout with failure of the ADS system in the Peach Bottom plant; station blackout with a pump seal LOCA for the Surry plant; station blackout with a pump seal LOCA in the Sequoyah plant; and a very small break with loss of ECC and spray recirculation in the Sequoyah plant. In addition, some partial analyses were performed which did not require running all of the modules of the Source Term Code Package. A series of MARCH3 analyses were performed for the Surry and Sequoyah plants to evaluate the effects of alternative emergency operating procedures involving primary and secondary depressurization on the progress of the accident. Only thermal-hydraulic results are provided for these analyses. In addition, three accident sequences were analyzed for the Surry plant for accident-induced failure of steam generator tubes. In these analyses, only the transport of radionuclides within the primary system and failed steam generator were examined. The release of radionuclides to the environment is presented for the phase of the accident preceding vessel meltthrough. 17 refs., 176 figs., 113 tabs.

Denning, R.S.; Leonard, M.T.; Cybulskis, P.; Lee, K.W.; Kelly, R.F.; Jordan, H.; Schumacher, P.M.; Curtis, L.A. (Battelle Columbus Div., OH (USA))

1990-08-01T23:59:59.000Z

352

Technical evaluation of the proposed design modifications and technical specification changes on grid voltage degradation (Part A) for the Rancho Seco Nuclear Generating Plant  

Science Conference Proceedings (OSTI)

The Rancho Seco Nuclear Generating Plant has two 4160-volt and two 480-volt Class 1E buses. The existing undervoltage protection design uses a single undervoltage relay on each 4160-volt Class 1E bus. If the voltage drops below 3534 volts (85% of 4160 volts), the undervoltage relay will energize a set of load-shedding relays. The load-shedding relays initiate the disconnection of the emergency 4160-volt buses from the off-site source, load shed the emergency 4160-volt buses, start the emergency diesel generators, and provide an enabling signal for the load-sequencing timing circuit. When the emergency diesel generator reaches the required voltage it is connected to the emergency buses and load-sequencing will begin automatically, if a safety injection (SI) signal exists. The licensee has proposed a design change to establish an automatic degraded voltage protection circuitry. The modification consists of incorporating the existing undervoltage protection scheme will consist of 3 undervoltage relays monitoring each 4160-volt emergency bus. The 3 undervoltage relays will be arranged in a 2-out-of-3 coincident logic with a setpoint of 3771 volts +- 38 volts (90.6% of 4160 volts) with a time delay of 12 seconds +- 1.2 seconds.

White, R.L.

1980-10-01T23:59:59.000Z

353

Financial analysis of experimental releases conducted at Glen Canyon Dam during water year 2011  

DOE Green Energy (OSTI)

This report examines the financial implications of experimental flows conducted at the Glen Canyon Dam (GCD) in water year 2011. It is the third report in a series examining financial implications of experimental flows conducted since the Record of Decision (ROD) was adopted in February 1997 (Reclamation 1996). A report released in January 2011 examined water years 1997 to 2005 (Veselka et al. 2011), and a report released in August 2011 examined water years 2006 to 2010 (Poch et al. 2011). An experimental release may have either a positive or negative impact on the financial value of energy production. This study estimates the financial costs of experimental releases, identifies the main factors that contribute to these costs, and compares the interdependencies among these factors. An integrated set of tools was used to compute the financial impacts of the experimental releases by simulating the operation of the GCD under two scenarios, namely, (1) a baseline scenario that assumes both that operations comply with the ROD operating criteria and the experimental releases that actually took place during the study period, and (2) a 'without experiments' scenario that is identical to the baseline scenario of operations that comply with the GCD ROD, except it assumes that experimental releases did not occur. The Generation and Transmission Maximization (GTMax) model was the main simulation tool used to dispatch GCD and other hydropower plants that comprise the Salt Lake City Area Integrated Projects (SLCA/IP). Extensive data sets and historical information on SLCA/IP powerplant characteristics, hydrologic conditions, and Western Area Power Administration's (Western's) power purchase prices were used for the simulation. In addition to estimating the financial impact of experimental releases, the GTMax model was also used to gain insights into the interplay among ROD operating criteria, exceptions that were made to criteria to accommodate the experimental releases, and Western operating practices. Experimental releases conducted in water year 2011 resulted only in financial costs; the total cost of all experimental releases was about $622,000.

Poch, L. A.; Veselka, T. D.; Palmer, C. S.; Loftin, S.; Osiek, B. (Decision and Information Sciences); (Western Area Power Administration)

2012-07-16T23:59:59.000Z

354

On-Line Monitoring and Diagnostics of the Integrity of Nuclear Plant Steam Generators and Heat Exchangers  

Science Conference Proceedings (OSTI)

Integrity monitoring and flaw diagnostics of flat beams and tubular structures was investigated in this research task using guided acoustic signals. A piezo-sensor suite was deployed to activate and collect Lamb wave signals that propagate along metallic specimens. The dispersion curves of Lamb waves along plate and tubular structures are generated through numerical analysis. Several advanced techniques were explored to extract representative features from acoustic time series. Among them, the Hilbert-Huang transform (HHT) is a recently developed technique for the analysis of non-linear and transient signals. A moving window method was introduced to generate the local peak characters from acoustic time series, and a zooming window technique was developed to localize the structural flaws. The time-frequency analysis and pattern recognition techniques were combined for classifying structural defects in brass tubes. Several types of flaws in brass tubes were tested, both in the air and in water. The techniques also proved to be effective under background/process noise. A detailed theoretical analysis of Lamb wave propagation was performed and simulations were carried out using the finite element software system ABAQUS. This analytical study confirmed the behavior of the acoustic signals acquired from the experimental studies. The report presents the background the analysis of acoustic signals acquired from piezo-electric transducers for structural defect monitoring. A comparison of the use of time-frequency techniques, including the Hilbert-Huang transform, is presented. The report presents the theoretical study of Lamb wave propagation in flat beams and tubular structures, and the need for mode separation in order to effectively perform defect diagnosis. The results of an extensive experimental study of detection, location, and isolation of structural defects in flat aluminum beams and brass tubes are presented. The results of this research show the feasibility of on-line monitoring of small structural flaws by the use of transient and nonlinear acoustic signal analysis, and its implementation by the proper design of a piezo-electric transducer suite.

Belle R. Upadhyaya; J. Wesley Hines

2004-09-27T23:59:59.000Z

355

For Safer Emergencies, Give Your Power Generator Some ...  

Science Conference Proceedings (OSTI)

For Safer Emergencies, Give Your Power Generator Some Space. For Immediate Release: October 6, 2009. ...

2013-11-26T23:59:59.000Z

356

,"California Natural Gas Plant Processing"  

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

Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","California Natural Gas Plant Processing",3,"Annual",2011,"6301967" ,"Release Date:","1031...

357

,"Texas Natural Gas Plant Processing"  

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

,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","Texas Natural Gas Plant Processing",3,"Annual",2011,"6301967" ,"Release Date:","1031...

358

U.S. Nuclear Generation of Electricity  

Annual Energy Outlook 2012 (EIA)

U.S. Nuclear Generation and Generating Capacity Data Released: July 25, 2013 Data for : May 2013 Next Release: August 2013 Contacts: Michael Mobilia Phone: 202-287-6318 E-mail:...

359

RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Report LBL-5287. "Power Plant Reliability-Availability andConunercial Nuclear Power Plants", Report WASH-1400 (NUREG-Standards for Nuclear Power Plants," by A.V. Nero and Y.C.

Nero, A.V.

2010-01-01T23:59:59.000Z

360

Improving Vortex Generators to Enhance the Performance of Air-Cooled Condensers in a Geothermal Power Plant  

SciTech Connect

This report summarizes work at the Idaho National Laboratory to develop strategies to enhance air-side heat transfer in geothermal air-cooled condensers such that it should not significantly increase pressure drop and parasitic fan pumping power. The work was sponsored by the U.S. Department of Energy, NEDO (New Energy and Industrial Technology Development Organization) of Japan, Yokohama National University, and the Indian Institute of Technology, Kanpur, India. A combined experimental and numerical investigation was performed to investigate heat transfer enhancement techniques that may be applicable to largescale air-cooled condensers such as those used in geothermal power applications. A transient heat transfer visualization and measurement technique was employed in order to obtain detailed distributions of local heat transfer coefficients on model fin surfaces. Pressure drop measurements were obtained for a variety of tube and winglet configurations using a single-channel flow apparatus that included four tube rows in a staggered array. Heat transfer and pressure drop measurements were also acquired in a separate multiple-tube row apparatus in the Single Blow Test Facility. In addition, a numerical modeling technique was developed to predict local and average heat transfer for these low-Reynolds number flows, with and without winglets. Representative experimental and numerical results were obtained that reveal quantitative details of local finsurface heat transfer in the vicinity of a circular tube with a single delta winglet pair downstream of the cylinder. Heat transfer and pressure-drop results were obtained for flow Reynolds numbers based on channel height and mean flow velocity ranging from 700 to 6500. The winglets were of triangular (delta) shape with a 1:2 or 1:3 height/length aspect ratio and a height equal to 90% of the channel height. Overall mean fin-surface heat transfer results indicate a significant level of heat transfer enhancement (in terms of Colburn j-factor) associated with deployment of the winglets with circular as well as oval tubes. In general, toe-in (common flow up) type winglets appear to have better performance than the toe-out (common flow down) type winglets. Comparisons of heat transfer and pressure drop results for the elliptical tube versus a circular tube with and without winglets are provided. During the course of their independent research, all of the researchers have established that about 10 to 30% enhancement in Colburn j-factor is expected. However, actual increase in heat transfer rate from a heat exchanger employing finned tubes with winglets may be smaller, perhaps on the order of 2 to 5%. It is also concluded that for any specific application, more full-size experimentation is needed to optimize the winglet design for a specific heat exchanger application. If in place of a circular tube, an oval tube can be economically used in a bundle, it is expected that the pressure drop across the tube bundle with the application of vortex generators (winglets) will be similar to that in a conventional circular tube bundle. It is hoped that the results of this research will demonstrate the benefits of applying vortex generators (winglets) on the fins to improve the heat transfer from the air-side of the tube bundle.

Manohar S. Sohal

2005-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "generating plants release" 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

EIA - Annual Energy Outlook 2013 Early Release  

U.S. Energy Information Administration (EIA)

AEO2013 continues to model the implementation of the Mercury and Air Toxics Standards ... Electricity generation from nuclear power plants grows by 14 percent in ...

362

EIA - Annual Energy Outlook 2014 Early Release  

U.S. Energy Information Administration (EIA)

Sales, revenue and prices, power plants, fuel use, stocks, generation, trade, demand & emissions. ... with annual growth averaging 0.8 million ...

363

DIRECT FUEL/CELL/TURBINE POWER PLANT  

SciTech Connect

This report includes the progress in development of Direct FuelCell/Turbine{reg_sign} (DFC/T{reg_sign}) power plants for generation of clean power at very high efficiencies. The DFC/T power system is based on an indirectly heated gas turbine to supplement fuel cell generated power. The DFC/T power generation concept extends the high efficiency of the fuel cell by utilizing the fuel cell's byproduct heat in a Brayton cycle. Features of the DFC/T system include: electrical efficiencies of up to 75% on natural gas, 60% on coal gas, minimal emissions, simplicity in design, direct reforming internal to the fuel cell, reduced carbon dioxide release to the environment, and potential cost competitiveness with existing combined cycle power plants. FCE successfully completed testing of the pre-alpha DFC/T hybrid power plant. This power plant was constructed by integration of a 250kW fuel cell stack and a microturbine. The tests of the cascaded fuel cell concept for achieving high fuel utilizations were completed. The tests demonstrated that the concept results in higher power plant efficiency. Also, the preliminary design of a 40 MW power plant including the key equipment layout and the site plan was completed.

Hossein Ghezel-Ayagh

2004-05-01T23:59:59.000Z

364

DIRECT FUEL/CELL/TURBINE POWER PLANT  

DOE Green Energy (OSTI)

This report includes the progress in development of Direct FuelCell/Turbine{reg_sign} (DFC/T{reg_sign}) power plants for generation of clean power at very high efficiencies. The DFC/T power system is based on an indirectly heated gas turbine to supplement fuel cell generated power. The DFC/T power generation concept extends the high efficiency of the fuel cell by utilizing the fuel cell's byproduct heat in a Brayton cycle. Features of the DFC/T system include: electrical efficiencies of up to 75% on natural gas, 60% on coal gas, minimal emissions, simplicity in design, direct reforming internal to the fuel cell, reduced carbon dioxide release to the environment, and potential cost competitiveness with existing combined cycle power plants. FCE successfully completed testing of the pre-alpha DFC/T hybrid power plant. This power plant was constructed by integration of a 250kW fuel cell stack and a microturbine. The tests of the cascaded fuel cell concept for achieving high fuel utilizations were completed. The tests demonstrated that the concept results in higher power plant efficiency. Also, the preliminary design of a 40 MW power plant including the key equipment layout and the site plan was completed.

Hossein Ghezel-Ayagh

2004-05-01T23:59:59.000Z

365

Kentucky Natural Gas Plant Liquids, Proved Reserves (Million...  

Gasoline and Diesel Fuel Update (EIA)

W Withheld to avoid disclosure of individual company data. Release Date: 812013 Next Release Date: 812014 Referring Pages: Natural Gas Plant Liquids Proved Reserves...

366

Michigan Natural Gas Plant Liquids, Proved Reserves (Million...  

Gasoline and Diesel Fuel Update (EIA)

W Withheld to avoid disclosure of individual company data. Release Date: 812013 Next Release Date: 812014 Referring Pages: Natural Gas Plant Liquids Proved Reserves...

367

Montana Natural Gas Plant Liquids, Proved Reserves (Million Barrels...  

Annual Energy Outlook 2012 (EIA)

W Withheld to avoid disclosure of individual company data. Release Date: 812013 Next Release Date: 812014 Referring Pages: Natural Gas Plant Liquids Proved Reserves...

368

Colorado Natural Gas Plant Liquids, Proved Reserves (Million...  

Gasoline and Diesel Fuel Update (EIA)

W Withheld to avoid disclosure of individual company data. Release Date: 812013 Next Release Date: 812014 Referring Pages: Natural Gas Plant Liquids Proved Reserves...

369

Kansas Natural Gas Plant Liquids, Proved Reserves (Million Barrels...  

Gasoline and Diesel Fuel Update (EIA)

W Withheld to avoid disclosure of individual company data. Release Date: 812013 Next Release Date: 812014 Referring Pages: Natural Gas Plant Liquids Proved Reserves...

370

Oklahoma Natural Gas Plant Liquids, Proved Reserves (Million...  

Gasoline and Diesel Fuel Update (EIA)

W Withheld to avoid disclosure of individual company data. Release Date: 812013 Next Release Date: 812014 Referring Pages: Natural Gas Plant Liquids Proved Reserves...

371

Annual Electric Generator data - EIA-860 data file  

Gasoline and Diesel Fuel Update (EIA)

60 detailed data with previous form data (EIA-860A/860B) 60 detailed data with previous form data (EIA-860A/860B) Release Date: October 10, 2013 for Final 2012 data Next Release Date: September 2014 Re-Release 2012 data: December 4, 2013 (CORRECTION) The survey Form EIA-860 collects generator-level specific information about existing and planned generators and associated environmental equipment at electric power plants with 1 megawatt or greater of combined nameplate capacity. Summary level data can be found in the Electric Power Annual. Detailed data are compressed (zip) and contain the following files: LayoutYyy – Provides a directory of all (published) data elements collected on the Form EIA-860 together with the related description, specific file location(s), and, where appropriate, an explanation of codes.

372

Kansas Nuclear Profile - Wolf Creek Generating Station  

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

April 2012" "Next Release Date: February 2013" "Wolf Creek Generating Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor...

373

North Carolina Nuclear Profile - Power Plants  

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

Carolina nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

374

New Hampshire Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (nw)","Net generation (thousand mwh)","Share of State nuclear net...

375

New Jersey Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

376

WIPP News Releases  

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

Back to current year news releases 2008 News Releases November 21 WIPP Sets Schedule for Facility Upgrades October 23 New Mexico Environment Department Approves Permit Change for...

377

Press Pass - Press Releases  

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

09 Press Release Archive Recent Releases Beams are Back in the Large Hadron Collider 112009 Fermilab seeks nominations for new Community Advisory Board to assist in future...

378

Global Soil Data Release, Dec. 20, 2000  

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

Soil Data Available The ORNL DAAC has released a data set entitled "Global Gridded Surfaces of Selected Soil Characteristics (IGBP-DIS)." The data surfaces were generated by the...

379

RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Interim Standard for Plutonium in Soils", Los Alamoson the Use of Recycle Plutonium in Mixed Oxide Fuel in LightCharacterization of Particulate Plutonium Released in Fuel

Nero, A.V.

2010-01-01T23:59:59.000Z

380

Methods to reduce CO{sub 2} release to the atmosphere.  

SciTech Connect

The U.S. anthropogenic emission of CO{sub 2} is over 5.5 billion tons a year. Over 1/3 of it is emitted by power plants, and 90% of all power plant emissions is released by coal fired units. Figure 1 shows the amount of coal used and the amount of electricity generated from coal over a several year period. Burning one lb of coal produces about 2.1 lbs of CO{sub 2} and about 1 kWh of electricity, or a 1000 MW coal-fired plant emits over 1000 tons of CO{sub 2} per hour. Therefore, power plants are good candidates for reducing CO{sub 2} emissions. Emissions can be reduced by conserving energy, fuel and oxidant treatment prior to combustion, using fuels with higher H/C ratios, and by capturing the CO{sub 2}.

Jody, B. J.

1998-04-10T23:59:59.000Z

Note: This page contains sample records for the topic "generating plants release" 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

Main Generator Rotor Maintenance  

Science Conference Proceedings (OSTI)

Main generator rotors are constructed and designed to provide decades of reliable and trouble-free operation. However, a number of incidences have occurred over the years that can adversely impact reliable operation of generator rotors and, ultimately, production of electrical power. This report is a guide for power plant personnel responsible for reliable operation and maintenance of main generators. As a guide, this report provides knowledge and experience from generator experts working at power plants...

2006-11-27T23:59:59.000Z

382

Characterization and Dose Modeling of Soil, Sediment and Bedrock During Nuclear Power Plant Decommissioning  

Science Conference Proceedings (OSTI)

A decommissioning nuclear power plant must confirm that the radionuclides present in the soils, sediments, and bedrock left on site at the time of license termination will meet the appropriate dose limits for site release. This process involves the characterization, dose modeling, and if required, remediation, of these media. At some decommissioning nuclear power plants, the management of contaminated soil, sediments, and bedrocks was a major project that led to generation of remediation projects and rad...

2009-11-20T23:59:59.000Z

383

Deep Sludge Gas Release Event Analytical Evaluation  

SciTech Connect

The purpose of the Deep Sludge Gas Release Event Analytical Evaluation (DSGRE-AE) is to evaluate the postulated hypothesis that a hydrogen GRE may occur in Hanford tanks containing waste sludges at levels greater than previously experienced. There is a need to understand gas retention and release hazards in sludge beds which are 200 -300 inches deep. These sludge beds are deeper than historical Hanford sludge waste beds, and are created when waste is retrieved from older single-shell tanks (SST) and transferred to newer double-shell tanks (DST).Retrieval of waste from SSTs reduces the risk to the environment from leakage or potential leakage of waste into the ground from these tanks. However, the possibility of an energetic event (flammable gas accident) in the retrieval receiver DST is worse than slow leakage. Lines of inquiry, therefore, are (1) can sludge waste be stored safely in deep beds; (2) can gas release events (GRE) be prevented by periodically degassing the sludge (e.g., mixer pump); or (3) does the retrieval strategy need to be altered to limit sludge bed height by retrieving into additional DSTs? The scope of this effort is to provide expert advice on whether or not to move forward with the generation of deep beds of sludge through retrieval of C-Farm tanks. Evaluation of possible mitigation methods (e.g., using mixer pumps to release gas, retrieving into an additional DST) are being evaluated by a second team and are not discussed in this report. While available data and engineering judgment indicate that increased gas retention (retained gas fraction) in DST sludge at depths resulting from the completion of SST 241-C Tank Farm retrievals is not expected and, even if gas releases were to occur, they would be small and local, a positive USQ was declared (Occurrence Report EM-RP--WRPS-TANKFARM-2012-0014, "Potential Exists for a Large Spontaneous Gas Release Event in Deep Settled Waste Sludge"). The purpose of this technical report is to (1) present and discuss current understandings of gas retention and release mechanisms for deep sludge in U.S. Department of Energy (DOE) complex waste storage tanks; and (2) to identify viable methods/criteria for demonstrating safety relative to deep sludge gas release events (DSGRE) in the near term to support the Hanford C-Farm retrieval mission. A secondary purpose is to identify viable methods/criteria for demonstrating safety relative to DSGREs in the longer term to support the mission to retrieve waste from the Hanford Tank Farms and deliver it to the Waste Treatment and Immobilization Plant (WTP). The potential DSGRE issue resulted in the declaration of a positive Unreviewed Safety Question (USQ). C-Farm retrievals are currently proceeding under a Justification for Continued Operation (JCO) that only allows tanks 241-AN-101 and 241-AN-106 sludge levels of 192 inches and 195 inches, respectively. C-Farm retrievals need deeper sludge levels (approximately 310 inches in 241-AN-101 and approximately 250 inches in 241-AN-106). This effort is to provide analytical data and justification to continue retrievals in a safe and efficient manner.

Sams, Terry L.

2013-08-15T23:59:59.000Z

384

SRNL - News Release Archives  

SRNL Atmospheric Technologies’ Expertise Helps Guide Response to Graniteville Emergency; 2004 News Releases;

385

Energy Department Report Calculates Emissions and Costs of Power Plant  

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

Report Calculates Emissions and Costs of Power Report Calculates Emissions and Costs of Power Plant Cycling Necessary for Increased Wind and Solar in the West Energy Department Report Calculates Emissions and Costs of Power Plant Cycling Necessary for Increased Wind and Solar in the West September 24, 2013 - 10:08am Addthis A new report released today by the Energy Department's National Renewable Energy Laboratory (NREL) examines the potential impacts of increasing wind and solar power generation on the operators of coal and gas plants in the West. To accommodate higher amounts of wind and solar power on the electric grid, utilities must ramp down and ramp up or stop and start conventional generators more frequently to provide reliable power for their customers - a practice called cycling. Grid operators typically cycle power plants to accommodate fluctuations in

386

Final Report - Gas Retention and Release Tests Supporting the Concentrate Receipt Vessel (CRV-VSL-00002A/2B) Configuration  

DOE Green Energy (OSTI)

Gas Retention and Release (GR and R) tests were performed in the scaled Concentrate Receipt Vessel (CRV) Test Stand at the Savannah River National Laboratory to validate the capability of candidate Hybrid-Mixing systems for the CRV to safely release hydrogen during normal and upset conditions. Hydrogen is generated in the radioactive waste as a result of natural and plant processes and must not be allowed to accumulate above flammability limits. Two types of tests were conducted. Gas holdup tests determined the steady state amount of gas accumulated in the simulant under normal PJM only or PJM plus sparging conditions. Gas release tests determined what operating conditions are necessary to fully release gas after a steady state gas fraction of 4 per cent tank volume or more was reached in the simulant.

GUERRERO, HECTOR

2004-09-01T23:59:59.000Z

387

RMOTC - News - Press Releases  

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

Press Releases Press Releases January Sale of Equipment and Materials Janurary 2014 | Press Releases Read Press Release here. Department of Energy to Sell NPR-3 July 2013 | Press Releases Read Press Release here. View Secretary of Energy Ernest Moniz's Report to Congress here. Press Releases Archive STWA, Inc. to determine the performance of its Applied Oil Technology (AOT(tm)) in reducing crude oil's viscosity to lower transportation costs (PDF) June 2011 | Press Releases Geothermal research initiative at RMOTC (PDF) October 2009 | Press Releases RMOTC partner receives award for tech tested at Teapot Dome (PDF) August 2009 | Press Releases Summer interns work with RMOTC engineers August 2009 | Articles | Casper Journal College, business, government officials launch wind project

388

Final voluntary release assessment/corrective action report  

SciTech Connect

The US Department of Energy, Carlsbad Area Office (DOE-CAO) has completed a voluntary release assessment sampling program at selected Solid Waste Management Units (SWMUs) at the Waste Isolation Pilot Plant (WIPP). This Voluntary Release Assessment/Corrective Action (RA/CA) report has been prepared for final submittal to the Environmental protection Agency (EPA) Region 6, Hazardous Waste Management Division and the New Mexico Environment Department (NMED) Hazardous and Radioactive Materials Bureau to describe the results of voluntary release assessment sampling and proposed corrective actions at the SWMU sites. The Voluntary RA/CA Program is intended to be the first phase in implementing the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) and corrective action process at the WIPP. Data generated as part of this sampling program are intended to update the RCRA Facility Assessment (RFA) for the WIPP (Assessment of Solid Waste Management Units at the Waste Isolation Pilot Plant), NMED/DOE/AIP 94/1. This Final Voluntary RA/CA Report documents the results of release assessment sampling at 11 SWMUs identified in the RFA. With this submittal, DOE formally requests a No Further Action determination for these SWMUs. Additionally, this report provides information to support DOE`s request for No Further Action at the Brinderson and Construction landfill SWMUs, and to support DOE`s request for approval of proposed corrective actions at three other SWMUs (the Badger Unit Drill Pad, the Cotton Baby Drill Pad, and the DOE-1 Drill Pad). This information is provided to document the results of the Voluntary RA/CA activities submitted to the EPA and NMED in August 1995.

NONE

1996-11-12T23:59:59.000Z

389

Hydrogen generation by metal corrosion in simulated Waste Isolation Pilot Plant environments. Progress report for the period November 1989 through December 1992  

DOE Green Energy (OSTI)

The corrosion and gas-generation characteristics of three material types: low-carbon steel (the current waste packaging material for the Waste Isolation Pilot Plant), Cu-base materials, and Ti-base materials were determined in both the liquid and vapor phase of Brine A, a brine representative of an intergranular Salado Formation brine. Test environments included anoxic brine and anoxic brine with overpressures of CO{sub 2}, H{sub 2}S, and H{sub 2}. Low-carbon steel reacted at a slow, measurable rate with anoxic brine, liberating H{sub 2} on an equimolar basis with Fe reacted. Presence of CO{sub 2} caused the initial reaction to proceed more rapidly, but CO{sub 2}-induced passivation stopped the reaction if the CO{sub 2} were present in sufficient quantities. Low-carbon steel immersed in brine with H{sub 2}S showed no reaction, apparently because of passivation of the steel by formation of a protective iron sulfide reaction product. Cu- and Ti-base materials showed essentially no corrosion when exposed to brine and overpressures of N{sub 2}, CO{sub 2}, and H{sub 2}S except for the rapid and complete reaction between Cu-base materials and H{sub 2}S. No significant reaction took place on any material in any environment in the vapor-phase exposures.

Telander, M.R.; Westerman, R.E. [Pacific Northwest Lab., Richland, WA (United States)

1993-09-01T23:59:59.000Z

390

RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

Plants", Report WASH-1400 (NUREG-75/0l4), October 1975. u ICooled Reactors (GESMO), NUREG -0002,ES, August 1976. W. B.Plants", report WASH-1400 (NUREG-75/014), October 1975. See

Nero, A.V.

2010-01-01T23:59:59.000Z

391

New baseload power plants  

Science Conference Proceedings (OSTI)

This is a listing of 221 baseload power plant units currently in the planning stage. The list shows the plant owner, capacity, fuel, engineering firm, constructor, major equipment suppliers (steam generator, turbogenerator, and flue gas desulfurization system), partner, and date the plant is to be online. This data is a result of a survey by the journal of power plant owners.

Not Available

1994-04-01T23:59:59.000Z

392

Model for TCLP Releases from Waste Glasses  

Science Conference Proceedings (OSTI)

A first-order property model for normalized Toxicity Characteristic Leaching Procedure (TCLP) release as a function of glass composition was developed using data collected from various studies. The normalized boron release is used to estimate the release of toxic elements based on the observation that the boron release represents the conservative release for those constituents of interest. The current TCLP model has two targeted application areas: (1) delisting of waste-glass product as radioactive (not mixed) waste and (2) designating the glass wastes generated from waste-glass research activities as hazardous or non-hazardous. This report describes the data collection and model development for TCLP releases and discusses the issues related to the application of the model.

Kim, Dong-Sang; Vienna, John D.

2003-05-01T23:59:59.000Z

393

Model for TCLP Releases from Waste Glasses  

Science Conference Proceedings (OSTI)

A first-order property model for normalized Toxicity Characteristic Leaching Procedure (TCLP) release as a function of glass composition was developed using collected data from various studies. The normalized boron release is used to estimate the release of toxic elements based on the observation that the boron release represents the conservative release for those constituents of interest. The current TCLP model has two targeted application areas: (1) delisting of waste-glass product as radioactive (not mixed) waste and (2) designating the glass wastes generated from waste-glass research activities as hazardous or non-hazardous. This report describes the data collection and model development for TCLP releases and discusses the issues related to the application of the model.

Kim, Dong-Sang; Vienna, John D.

2002-09-01T23:59:59.000Z

394

RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

MISCELLAN £OUS LlOUID STEAM GENERATOR ORAIH OE .. ,N[PALIZEAon the steam system and turbine generator units, as d~fined

Nero, A.V.

2010-01-01T23:59:59.000Z

395

Louisiana Nuclear Profile - Power Plants  

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

Louisiana nuclear power plants, summer capacity and net generation, 2010" "Plant NameTotal Reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear...

396

New baseload power plants  

Science Conference Proceedings (OSTI)

This is a tabulation of the results of this magazines survey of current plans for new baseload power plants. The table lists the unit name, capacity, fuel, engineering firm, constructor, suppliers for steam generator, turbine generator and flue gas desulfurization equipment, date due on-line, and any non-utility participants. The table includes fossil-fuel plants, nuclear plants, geothermal, biomass and hydroelectric plants.

Not Available

1993-04-01T23:59:59.000Z

397

Corrosion-product release in LWRs: 1983 progress report  

SciTech Connect

Corrosion products released from coolant system surfaces are a major cause of radiation buildup in LWRs. This study confirms that cobalt release from Inconel steam generator tubing is a key contributor to radiation fields, and it offers new insights into the release mechanisms of Inconel and other reactor alloys.

Lister, D.H.

1985-01-01T23:59:59.000Z

398

Corrosion-Product Release in LWRs: 1983 Progress Report  

Science Conference Proceedings (OSTI)

Corrosion products released from coolant system surfaces are a major cause of radiation buildup in LWRs. This study confirms that cobalt release from Inconel steam generator tubing is a key contributor to radiation fields, and it offers new insights into the release mechanisms of Inconel and other reactor alloys.

1985-02-04T23:59:59.000Z

399

SRS - News Releases  

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

6/2014 6/2014 SEARCH GO spacer News Releases govDELIVERY Video Releases Fact Sheets Photo Gallery Speakers Media Contacts SRS Home SRS News Releases News releases are in PDF format (requires Acrobat Reader - click here to download). * 2013 News Releases * 2012 News Releases * 2011 News Releases * 2010 News Releases 2013: 12.31.13 Dr. Sam Fink Earns Donald Orth Lifetime Achievement Award 12.31.13 Savannah River Remediation Issues Fiscal Year 2013 Annual Report 12.18.13 Prototype System Brings Advantages of Wireless Technology to Secure Environment 12.16.13 Registration for the 2014 SRS Public Tour Program Begins December 30 12.12.13 Area Children to Benefit from SRS "Toys for Tots" Campaign 12.10.13 Ruth Patrick's Work Opens Doors for SRNL Environmental Remediation

400

NACP Data Sets Released  

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

Set Released The ORNL DAAC is pleased to announce the release of a Global Soil data set : A Global Database of Gas Fluxes from Soils after Rewetting or Thawing, Version 1.0 . Data...

Note: This page contains sample records for the topic "generating plants release" 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

SR 2002 News Release  

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

2 News Releases SRS Environmental Management FY2003 Budget and Top-To-Bottom Review Presented at Friday Meeting - SR-02-01 NNSA Releases Accident Investigation Report On TEF...

402

Dietary guidelines report released  

Science Conference Proceedings (OSTI)

The Report of the Dietary Guidelines Advisory Committee on the Dietary Guidelines for Americans 2010 was released in June by the US Departments of Agriculture and Health and Human Services. Dietary guidelines report released Health Nutrition Tran

403

Sunrise II Power Plant  

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

Sunrise Power Company, LLC (Sunrise), has planned the modification of an existing power plant project to increase its generation capacity by 265 megawatts by 2003. The initial...

404

Definition: Distributed generation | Open Energy Information  

Open Energy Info (EERE)

generation generation Jump to: navigation, search Dictionary.png Distributed generation A term used by the power industry to describe localized or on-site power generation[1] View on Wikipedia Wikipedia Definition Distributed generation, also called on-site generation, dispersed generation, embedded generation, decentralized generation, decentralized energy or distributed energy, generates electricity from many small energy sources. Most countries generate electricity in large centralized facilities, such as fossil fuel, nuclear, large solar power plants or hydropower plants. These plants have excellent economies of scale, but usually transmit electricity long distances and can negatively affect the environment. Distributed generation allows collection of energy from many

405

Pages that link to "Space Coast Next Generation Solar Energy...  

Open Energy Info (EERE)

icon Pages that link to "Space Coast Next Generation Solar Energy Center Solar Power Plant" Space Coast Next Generation Solar Energy Center Solar Power Plant Jump...

406

Changes related to "Space Coast Next Generation Solar Energy...  

Open Energy Info (EERE)

icon Changes related to "Space Coast Next Generation Solar Energy Center Solar Power Plant" Space Coast Next Generation Solar Energy Center Solar Power Plant Jump...

407

Changes related to "Martin Next Generation Solar Energy Center...  

Open Energy Info (EERE)

Twitter icon Changes related to "Martin Next Generation Solar Energy Center Solar Power Plant" Martin Next Generation Solar Energy Center Solar Power Plant Jump to:...

408

Pages that link to "Martin Next Generation Solar Energy Center...  

Open Energy Info (EERE)

Twitter icon Pages that link to "Martin Next Generation Solar Energy Center Solar Power Plant" Martin Next Generation Solar Energy Center Solar Power Plant Jump to:...

409

DIRECT FUEL CELL/TURBINE POWER PLANT  

SciTech Connect

This report includes the progress in development of Direct FuelCell/Turbine{reg_sign} (DFC/T{reg_sign}) power plants for generation of clean power at very high efficiencies. The DFC/T power system is based on an indirectly heated gas turbine to supplement fuel cell generated power. The DFC/T power generation concept extends the high efficiency of the fuel cell by utilizing the fuel cell's byproduct heat in a Brayton cycle. Features of the DFC/T system include: electrical efficiencies of up to 75% on natural gas, 60% on coal gas, minimal emissions, simplicity in design, direct reforming internal to the fuel cell, reduced carbon dioxide release to the environment, and potential cost competitiveness with existing combined cycle power plants. The operation of sub-MW hybrid Direct FuelCell/Turbine power plant test facility with a Capstone C60 microturbine was initiated in March 2003. The inclusion of the C60 microturbine extended the range of operation of the hybrid power plant to higher current densities (higher power) than achieved in previous tests using a 30kW microturbine. The design of multi-MW DFC/T hybrid systems, approaching 75% efficiency on natural gas, was initiated. A new concept was developed based on clusters of One-MW fuel cell modules as the building blocks. System analyses were performed, including systems for near-term deployment and power plants with long-term ultra high efficiency objectives. Preliminary assessment of the fuel cell cluster concept, including power plant layout for a 14MW power plant, was performed.

Hossein Ghezel-Ayagh

2004-11-01T23:59:59.000Z

410

Direct FuelCell/Turbine Power Plant  

SciTech Connect

This report includes the progress in development of Direct Fuel Cell/Turbine. (DFC/T.) power plants for generation of clean power at very high efficiencies. The DFC/T power system is based on an indirectly heated gas turbine to supplement fuel cell generated power. The DFC/T power generation concept extends the high efficiency of the fuel cell by utilizing the fuel cell's byproduct heat in a Brayton cycle. Features of the DFC/T system include: electrical efficiencies of up to 75% on natural gas, 60% on coal gas, minimal emissions, simplicity in design, direct reforming internal to the fuel cell, reduced carbon dioxide release to the environment, and potential cost competitiveness with existing combined cycle power plants. FCE successfully completed testing of the pre-alpha sub-MW DFC/T power plant. This power plant was constructed by integration of a 250kW fuel cell stack and a microturbine. Following these proof-of-concept tests, a stand-alone test of the microturbine verified the turbine power output expectations at an elevated (representative of the packaged unit condition) turbine inlet temperature. Preliminary design of the packaged sub-MW alpha DFC/T unit has been completed and procurement activity has been initiated. The preliminary design of a 40 MW power plant including the key equipment layout and the site plan was completed. A preliminary cost estimate for the 40 MW DFC/T plant has also been prepared. The tests of the cascaded fuel cell concept for achieving high fuel utilizations were completed. The tests demonstrated that the concept results in higher power plant efficiency. Alternate stack flow geometries for increased power output/fuel utilization capabilities are also being evaluated.

Hossein Ghezel-Ayagh

2004-11-19T23:59:59.000Z

411

Direct FuelCell/Turbine Power Plant  

DOE Green Energy (OSTI)

This report includes the progress in development of Direct Fuel Cell/Turbine. (DFC/T.) power plants for generation of clean power at very high efficiencies. The DFC/T power system is based on an indirectly heated gas turbine to supplement fuel cell generated power. The DFC/T power generation concept extends the high efficiency of the fuel cell by utilizing the fuel cell's byproduct heat in a Brayton cycle. Features of the DFC/T system include: electrical efficiencies of up to 75% on natural gas, 60% on coal gas, minimal emissions, simplicity in design, direct reforming internal to the fuel cell, reduced carbon dioxide release to the environment, and potential cost competitiveness with existing combined cycle power plants. FCE successfully completed testing of the pre-alpha sub-MW DFC/T power plant. This power plant was constructed by integration of a 250kW fuel cell stack and a microturbine. Following these proof-of-concept tests, a stand-alone test of the microturbine verified the turbine power output expectations at an elevated (representative of the packaged unit condition) turbine inlet temperature. Preliminary design of the packaged sub-MW alpha DFC/T unit has been completed and procurement activity has been initiated. The preliminary design of a 40 MW power plant including the key equipment layout and the site plan was completed. A preliminary cost estimate for the 40 MW DFC/T plant has also been prepared. The tests of the cascaded fuel cell concept for achieving high fuel utilizations were completed. The tests demonstrated that the concept results in higher power plant efficiency. Alternate stack flow geometries for increased power output/fuel utilization capabilities are also being evaluated.

Hossein Ghezel-Ayagh

2004-11-19T23:59:59.000Z

412

DIRECT FUEL CELL/TURBINE POWER PLANT  

DOE Green Energy (OSTI)

This report includes the progress in development of Direct FuelCell/Turbine{reg_sign} (DFC/T{reg_sign}) power plants for generation of clean power at very high efficiencies. The DFC/T power system is based on an indirectly heated gas turbine to supplement fuel cell generated power. The DFC/T power generation concept extends the high efficiency of the fuel cell by utilizing the fuel cell's byproduct heat in a Brayton cycle. Features of the DFC/T system include: electrical efficiencies of up to 75% on natural gas, 60% on coal gas, minimal emissions, simplicity in design, direct reforming internal to the fuel cell, reduced carbon dioxide release to the environment, and potential cost competitiveness with existing combined cycle power plants. The operation of sub-MW hybrid Direct FuelCell/Turbine power plant test facility with a Capstone C60 microturbine was initiated in March 2003. The inclusion of the C60 microturbine extended the range of operation of the hybrid power plant to higher current densities (higher power) than achieved in previous tests using a 30kW microturbine. The design of multi-MW DFC/T hybrid systems, approaching 75% efficiency on natural gas, was initiated. A new concept was developed based on clusters of One-MW fuel cell modules as the building blocks. System analyses were performed, including systems for near-term deployment and power plants with long-term ultra high efficiency objectives. Preliminary assessment of the fuel cell cluster concept, including power plant layout for a 14MW power plant, was performed.

Hossein Ghezel-Ayagh

2004-11-01T23:59:59.000Z

413

Biomediated continuous release phosphate fertilizer  

DOE Patents (OSTI)

A composition is disclosed for providing phosphate fertilizer to the root zone of plants. The composition comprises a microorganism capable of producing and secreting a solubilization agent, a carbon source for providing raw material for the microorganism to convert into the solubilization agent, and rock phosphate ore for providing a source of insoluble phosphate that is solubilized by the solubilization agent and released as soluble phosphate. The composition is provided in a physical form, such as a granule, that retains the microorganism, carbon source, and rock phosphate ore, but permits water and soluble phosphate to diffuse into the soil. A method of using the composition for providing phosphate fertilizer to plants is also disclosed. 13 figs.

Goldstein, A.H.; Rogers, R.D.

1999-06-15T23:59:59.000Z

414

Biomediated continuous release phosphate fertilizer  

DOE Patents (OSTI)

A composition is disclosed for providing phosphate fertilizer to the root zone of plants. The composition comprises a microorganism capable of producing and secreting a solubilization agent, a carbon source for providing raw material for the microorganism to convert into the solubilization agent, and rock phosphate ore for providing a source of insoluble phosphate that is solubilized by the solubilization agent and released as soluble phosphate. The composition is provided in a physical form, such as a granule, that retains the microorganism, carbon source, and rock phosphate ore, but permits water and soluble phosphate to diffuse into the soil. A method of using the composition for providing phosphate fertilizer to plants is also disclosed.

Goldstein, Alan H. (Beverly Hills, CA); Rogers, Robert D. (Idaho Falls, ID)

1999-01-01T23:59:59.000Z

415

Preliminary Release: August 19, 2011",,,,,,,,,,,,,"Released: April 2013","Releas  

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

,,,,,,,,,,,,,"Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013","Released: April 2013"

416

AEO2008 Overview - Early Release  

Annual Energy Outlook 2012 (EIA)

Report :DOEEIA-0383(2008) Released Date: December 2007 Next Release Date: December 2008 (full report available early 2008) Annual Energy Outlook 2008 (Early Release)...

417

Environmental release summary (ERS) database CY 1997  

Science Conference Proceedings (OSTI)

This report discusses the Environmental Release Summary (ERS) database. The current needs of the Effluent and Environmental database is continually modified to fulfill monitoring (EEM) program (managed by Waste Management Federal Services of Hanford, Incorporated, Air and Water Services Organization). Changes are made to accurately calculate current releases, to affect how past releases are calculated. This document serves as a snap-shot of the database and software for the CY-1997 data and releases. This document contains all of the relevant data for calculating radioactive-airborne and liquid effluent. The ERS database is the official repository for the CY-1997 ERS release reports and the settings used to generate those reports. As part of the Tri-Party Agreement, FDH is committed to provide a hard copy of the ERS database for Washington State Department of Ecology, upon request. This document also serves as that hard copy for the last complete calendar year.

Gleckler, B.P.

1998-07-01T23:59:59.000Z

418

Accident states simulation: process fluids release  

Science Conference Proceedings (OSTI)

Seveso II Directive imposes for high hazardous plants quantitative risk evaluation of the major accident. In a general context the risk is defined as product between frequency and consequences of accident state. There are five steps in quantitative risk ... Keywords: hazard, hydrogen sulphide, mathematical model, release, risk, safety system, simulation

Cornelia Croitoru; Mihai Anghel; Floarea Pop; Ioan Stefanescu; Gheorghe Titescu; Mihai Patrascu; Ervin Watzlawek; Dorin Cheresdi

2008-08-01T23:59:59.000Z

419

Energy Department Report Calculates Emissions and Costs of Power Plant  

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

Energy Department Report Calculates Emissions and Costs of Power Energy Department Report Calculates Emissions and Costs of Power Plant Cycling Necessary for Increased Wind and Solar in the West Energy Department Report Calculates Emissions and Costs of Power Plant Cycling Necessary for Increased Wind and Solar in the West September 24, 2013 - 10:08am Addthis A new report released today by the Energy Department's National Renewable Energy Laboratory (NREL) examines the potential impacts of increasing wind and solar power generation on the operators of coal and gas plants in the West. To accommodate higher amounts of wind and solar power on the electric grid, utilities must ramp down and ramp up or stop and start conventional generators more frequently to provide reliable power for their customers - a practice called cycling.

420

,"Natural Gas Plant Liquids Proved Reserves"  

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

Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","Natural Gas Plant Liquids Proved Reserves",49,"Annual",2011,"6301979" ,"Release Date:","81...

Note: This page contains sample records for the topic "generating plants release" 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

,"Natural Gas Plant Liquids Proved Reserves"  

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

,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","Natural Gas Plant Liquids Proved Reserves",49,"Annual",2011,"6301979" ,"Release...

422

,"Texas Natural Gas Plant Fuel Consumption (MMcf)"  

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

,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","Texas Natural Gas Plant Fuel Consumption (MMcf)",1,"Annual",2011 ,"Release Date:","1031...

423

,"New Mexico Natural Gas Plant Processing"  

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

Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","New Mexico Natural Gas Plant Processing",3,"Annual",2011,"6301967" ,"Release Date:","1031...

424

Press Releases: BioEnergy Science Center  

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

Press Releases Press Releases Current Press Releases BESC researchers tap into genetic reservoir of heat-loving bacteria - 2012 Foxtail Millet Offers Clues for Assembling the Switchgrass Genome - 2012 Gerald A. Tuskan named Forest Biotechnologist of the Year - 2012 ORNL explores proteins in Yellowstone bacteria for biofuel inspiration - 2012 UGA discovery changes how scientists think about plant cell wall formation - 2011 Research collaboration at the Samuel Roberts Noble Foundation discover new type of lignin in vanilla cactus - 2011 First-of-a-kind tension weed study broadens biofuels research - 2011 New lignin "lite" switchgrass boots biofuel yield by more than one-third - 2011 Key Plant Traits Yield More Sugar For Biofuels - 2011 BESC Scores a First with Isobutanol Directly from Cellulose - 2011

425

Options for Generating Steam Efficiently  

E-Print Network (OSTI)

This paper describes how plant engineers can efficiently generate steam when there are steam generators and Heat Recovery Steam Generators in their plant. The process consists of understanding the performance characteristics of the various equipment as a function of load and operating them close to the maximum efficiency point.

Ganapathy, V.

1996-04-01T23:59:59.000Z

426

NETL: News Release - DOE Estimates Future Water Needs for Thermoelectric  

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

December 6, 2007 December 6, 2007 DOE Estimates Future Water Needs for Thermoelectric Power Plants 2007 Analysis Adds Projected Water Requirements for Carbon Capture WASHINGTON, DC - The Office of Fossil Energy's National Energy Technology Laboratory (NETL) has released a 2007 update to its groundbreaking study, Estimating Freshwater Needs to Meet Future Thermoelectric Generation Requirements. The updated analysis increases understanding of regional and national water needs and usage in the power industry, and provides input for research and development aimed at water-use reduction. MORE INFO Link to the updated study NETL's Water-Energy Interface web page New in this year's report is a response to heightened concerns over atmospheric carbon dioxide. The report examines the possibility that future

427

Emissions & Generation Resource Integrated Database (eGRID) ...  

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

Resource Integrated Database, eGRID, clean energy, power generation, electricity generation, production, environment, electricity, utilities, utility, power plant, power...

428

Emissions & Generation Resource Integrated Database (eGRID),...  

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

Resource Integrated Database, eGRID, clean energy, power generation, electricity generation, production, environment, electricity, utilities, utility, power plant, power...

429

MEASUREMENT OF AMMONIA RELEASE FROM SALTSTONE  

SciTech Connect

SRNL was requested by WSRC Waste Solidification Engineering to characterize the release of ammonia from saltstone curing at 95 C by performing experimental testing. These tests were performed with an MCU-type Tank 50H salt simulant containing 0, 50, and 200 mg/L ammonia. The testing program showed that above saltstone made from the 200 mg/L ammonia simulant, the vapor space ammonia concentration was about 2.7 mg/L vapor at 95 C. An upper 95% confidence value for this concentration was found to be 3.9 mg/L. Testing also showed that ammonia was chemically generated from curing saltstone at 95 C; the amount of ammonia generated was estimated to be equivalent to 121 mg/L additional ammonia in the salt solution feed. Even with chemical generation, the ammonia release from saltstone was found to be lower than its release from salt solution only with 200 mg/L ammonia.

Zamecnik, J; Alex Cozzi, A

2009-01-15T23:59:59.000Z

430

Control Scheme Modifications Increase Efficiency of Steam Generation System at ExxonMobil Gas Plant. Office of Industrial Technologies (OIT) Chemicals BestPractices Project Case Study  

Science Conference Proceedings (OSTI)

This case study highlights control scheme modifications made to the steam system at ExxonMobil's Mary Ann Gas Plant in Mobile, Alabama, which improved steam flow efficiency and reduced energy costs.

Not Available

2002-01-01T23:59:59.000Z

431

RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

refabrication. through which nuclear fuel passes. Fusion.with the experience at the Nuclear Fuel Services Plant (seecommitment from the nuclear fuel cycle; see Section 3.2.3. )

Nero, A.V.

2010-01-01T23:59:59.000Z

432

EM Press Releases | Department of Energy  

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

September 19, 2011 September 19, 2011 Annual Environmental Monitoring Report Released The National Nuclear Security Administration Nevada Site Office (NNSA/NSO) has released the Nevada National Security Site Environmental Report 2010. September 15, 2011 DOE Hosts German Energy Official, Signs MOU to Share WIPP Information CARLSBAD, N.M. - A high-ranking energy official from Germany formalized a partnership between her country and the United States during a recent visit to the Waste Isolation Pilot Plant (WIPP). September 15, 2011 Third Chapter of Hanford Story Released to Public - Chapter Dedicated to Those Who Helped Complete Projects Funded by Recovery Act RICHLAND, Wash. - The Department of Energy is releasing the third chapter of The Hanford Story today to the public. September 13, 2011

433

Illinois Nuclear Profile - Power Plants  

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

Illinois nuclear power plants, summer capacity and net generation, 2010" Illinois nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Braidwood Generation Station Unit 1, Unit 2","2,330","19,200",20.0,"Exelon Nuclear" "Byron Generating Station Unit 1, Unit 2","2,300","19,856",20.6,"Exelon Nuclear" "Clinton Power Station Unit 1","1,065","8,612",9.0,"Exelon Nuclear" "Dresden Generating<