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Note: This page contains sample records for the topic "nuclear generation corp" 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
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1

NRC okays nuclear merger at Entergy Corp  

SciTech Connect (OSTI)

The Nuclear Regulatory Commission (NRC) has approved the consolidation of Entergy Corp's nuclear operations into the utility's proposed nuclear management company, Entergy Operations Inc. The NRC action is a significant step in a consolidation process that would place operational responsibility for Entergy's nuclear plants in Mississippi, Arkansas, and Louisiana with Entergy Operations. The NRC action would authorize transfer of the operating licenses for Arkansas Nuclear One (ANO) at Russellville, Ark, Waterford-3 at Taft, La, and Grand Gulf-1 at Port Gibson, Miss, to Entergy Operations. A consolidated nuclear organization will allow for a more focused management structure in its nuclear operations and will result in greater operational efficiencies.

Not Available

1990-02-01T23:59:59.000Z

2

Nuclear Power Generating Facilities (Maine)  

Broader source: Energy.gov [DOE]

The first subchapter of the statute concerning Nuclear Power Generating Facilities provides for direct citizen participation in the decision to construct any nuclear power generating facility in...

3

Generation IV Nuclear Energy Systems ...  

E-Print Network [OSTI]

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

Kemner, Ken

4

Next Generation Nuclear Plant Phenomena  

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

the U.S. Department of Energy (DOE) to develop jointly a licensing strategy for the Next Generation Nuclear plant (NGNP), a very high temperature gas-cooled reactor (VHTR) for...

5

Kansas Nuclear Profile - Power Plants  

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

nuclear net generation (percent)","Owner" "Wolf Creek Generating Station Unit 1","1,160","9,556",100.0,"Wolf Creek Nuclear Optg Corp" "1 Plant 1 Reactor","1,160","9,556",100.0...

6

Managing nuclear predominant generating capacity  

SciTech Connect (OSTI)

The most common belief, associated with nuclear power plant, leads to the conclusion that it can only operate, as a base load plant. This observation can be reversed, by just looking at large generating capacity, using an important nuclear generation mix. Nuclear plants may certainly load follow and contribute to the grid frequency control. The French example illustrates these possibilities. The reactor control of French units has been customized to accommodate the grid requests. Managing such a large nuclear plant fleet requires various actions be taken, ranging from a daily to a multi-annual perspective. The paper describes the various contributions leading to safe, reliable, well accepted and cost competitive nuclear plants in France. The combination of all aspects related to operations, maintenance scheduling, nuclear safety management, are presented. The use of PWR units carries considerable weight in economic terms, with several hundred million francs tied in with outage scheduling every year. This necessitates a global view of the entire generating system which can be mobilized to meet demand. There is considerable interaction between units as, on the one hand, they are competing to satisfy the same need, and, on the other hand, reducing maintenance costs means sharing the necessary resources, and thus a coordinated staggering of outages. In addition, nuclear fuel is an energy reserve which remains in the reactor for 3 or 4 years, with some of the fuel renewed each year. Due to the memory effect, the fuel retains a memory of past use, so that today's choices impact upon the future. A medium-term view of fuel management is also necessary.

Bouget, Y.H.; Herbin, H.C.; Carbonnier, D.

1998-07-01T23:59:59.000Z

7

The Next Generation Nuclear Plant  

SciTech Connect (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

Next Generation Nuclear Plant Licensing Strategy  

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

reactor that is based on research and development (R&D) activities supported by the Generation IV Nuclear Energy Systems Initiative and shall be used to generate electricity,...

9

California Nuclear Profile - San Onofre Nuclear Generating Station  

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

San Onofre Nuclear Generating Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License...

10

Next Generation Nuclear Plant Phenomena  

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

Components," Journal of Nuclear Materials, 212-215, 1223 (1994). 13. Arnold, L, Windscale 1957, Anatomy of a Nuclear Accident, St Martin Press, London, 1992. 14....

11

Next Generation Nuclear Plant Phenomena  

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

and passive heat dissipation to withstand design basis events with minimal fuel damage and source term generation. As such, the NGNP places a burden on the designer to...

12

NEXT GENERATION NUCLEAR PLANT PROJECT IMPLEMENTATION STRATEGY  

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

NEXT GENERATION NUCLEAR PLANT PROJECT IMPLEMENTATION STRATEGY Presented by NGNP Industry Alliance November 30, 2009 I In nd du us st tr ry y A Al ll li ia an nc ce e Clean,...

13

The Fourth Generation of Nuclear Power  

SciTech Connect (OSTI)

The outlook for nuclear power in the U.S. is currently very bright. The economics, operations and safety performance of U.S. nuclear power plants is excellent. In addition, both the safety and economic regulation of nuclear power are being changed to produce better economic parameters for future nuclear plant operations and the licenses for plant operations are being extended to 60 years. There is further a growing awareness of the value of clean, emissions-free nuclear power. These parameters combine to form a firm foundation for continued successful U.S. nuclear plant operations, and even the potential In order to realize a bright future for nuclear power, we must respond successfully to five challenges: Ľ Nuclear power must remain economically competitive, Ľ The public must remain confident in the safety of the plants and the fuel cycle. Ľ Nuclear wastes and spent fuel must be managed and the ultimate disposition pathways for nuclear wastes must be politically settled. Ľ The proliferation potential of the commercial nuclear fuel cycle must continue to be minimized, and Ľ We must assure a sustained manpower supply for the future and preserve the critical nuclear technology infrastructure. The Generation IV program is conceived to focus the efforts of the international nuclear community on responding to these challenges.

Lake, James Alan

2000-11-01T23:59:59.000Z

14

Corps Improvement  

E-Print Network [OSTI]

to mitigate environmental impacts of the proj- ect. The Corps? Fort Worth District and the City of Dallas are using an innovative approach to return floodplain value to the Trinity River, while improving flood damage reduction. Big Fossil Creek Watershed... The Big Fossil Watershed Study will address flood damage reduction, while identifying associated water quality, ecosystem restoration and recreational opportunities within the basin. The watershed is located in northern Tarrant County, encompasses 73...

Wythe, Kathy

2007-01-01T23:59:59.000Z

15

Nuclear power generation and fuel cycle report 1996  

SciTech Connect (OSTI)

This report presents the current status and projections through 2015 of nuclear capacity, generation, and fuel cycle requirements for all countries using nuclear power to generate electricity for commercial use. It also contains information and forecasts of developments in the worldwide nuclear fuel market. Long term projections of U.S. nuclear capacity, generation, and spent fuel discharges for two different scenarios through 2040 are developed. A discussion on decommissioning of nuclear power plants is included.

NONE

1996-10-01T23:59:59.000Z

16

Generation IV Advanced Nuclear Energy Systems By Jacques Bouchard...  

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

Generation IV Advanced Nuclear Energy Systems By Jacques Bouchard, French Commissariat a l'Energie Atomique, France and Ralph Bennett, Idaho National Laboratory. Generation IV...

17

Nuclear power generation and fuel cycle report 1997  

SciTech Connect (OSTI)

Nuclear power is an important source of electric energy and the amount of nuclear-generated electricity continued to grow as the performance of nuclear power plants improved. In 1996, nuclear power plants supplied 23 percent of the electricity production for countries with nuclear units, and 17 percent of the total electricity generated worldwide. However, the likelihood of nuclear power assuming a much larger role or even retaining its current share of electricity generation production is uncertain. The industry faces a complex set of issues including economic competitiveness, social acceptance, and the handling of nuclear waste, all of which contribute to the uncertain future of nuclear power. Nevertheless, for some countries the installed nuclear generating capacity is projected to continue to grow. Insufficient indigenous energy resources and concerns over energy independence make nuclear electric generation a viable option, especially for the countries of the Far East.

NONE

1997-09-01T23:59:59.000Z

18

Incentive Cost Recovery Rule for Nuclear Power Generation (Louisiana)  

Broader source: Energy.gov [DOE]

The Incentive Cost Recovery Rule for Nuclear Power Generation establishes guidelines for any utility seeking to develop a nuclear power plant in Louisiana. The rule clarifies, as well as...

19

State Nuclear Profiles 2010  

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

net generation, 2010 Wolf Creek Generating Station Unit 1 1,160 9,556 100.0 Wolf Creek Nuclear Optg Corp 1 Plant 1 Reactor 1,160 9,556 100.0 Owner Note: Totals may not equal sum...

20

Power generation from nuclear reactors in aerospace applications  

SciTech Connect (OSTI)

Power generation in nuclear powerplants in space is addressed. In particular, the states of technology of the principal competitive concepts for power generation are assessed. The possible impact of power conditioning on power generation is also discussed. For aircraft nuclear propulsion, the suitability of various technologies is cursorily assessed for flight in the Earth's atmosphere. A program path is suggested to ease the conditions of first use of aircraft nuclear propulsion.

English, R.E.

1982-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation corp" 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

Monthly Nuclear Utility Generation by State and Reactor, 2007  

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

applicationvnd.ms-excel X-Translator-Status: translating " Worksheet" "Monthly Nuclear Utility Generation by State and Reactor, 2007" "January through December 2007"...

22

Monthly Nuclear Utility Generation by State and Reactor, 2004  

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

applicationvnd.ms-excel X-Translator-Status: translating " Worksheet" "Monthly Nuclear Utility Generation by State and Reactor, 2004" "January through December 2004"...

23

Monthly Nuclear Utility Generation by State and Reactor, 2005  

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

applicationvnd.ms-excel X-Translator-Status: translating " Worksheet" "Monthly Nuclear Utility Generation by State and Reactor, 2005" "January through December 2005"...

24

Monthly Nuclear Utility Generation by State and Reactor, 2003  

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

applicationvnd.ms-excel X-Translator-Status: translating " Worksheet" "Monthly Nuclear Utility Generation by State and Reactor, 2003" "January through December 2003"...

25

Monthly Nuclear Utility Generation by State and Reactor, 2008  

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

applicationvnd.ms-excel X-Translator-Status: translating " Worksheet" "Monthly Nuclear Utility Generation by State and Reactor, 2008" "January through December 2008"...

26

Next Generation Nuclear Plant GAP Analysis Report  

SciTech Connect (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

27

C Produced by Nuclear Power Reactors Generation and Characterization of  

E-Print Network [OSTI]

14 C Produced by Nuclear Power Reactors ┬ş Generation and Characterization of Gaseous, Liquid and process water from nuclear reactors ┬ş A method for quantitative determination of organic and inorganic and Solid Waste ├?sa Magnusson Division of Nuclear Physics Department of Physics 2007 Akademisk avhandling

Haviland, David

28

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...

29

Washington Nuclear Profile - Columbia Generating Station  

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

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

30

Illinois Nuclear Profile - Dresden Generating Station  

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

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

31

Illinois Nuclear Profile - Byron Generating Station  

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

Byron Generating Station" ,"Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration date"...

32

Illinois Nuclear Profile - Braidwood Generation Station  

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

Braidwood Generation Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License...

33

Risk Framework for the Next Generation Nuclear Power Plant Construction  

E-Print Network [OSTI]

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...

Yeon, Jaeheum 1981-

2012-12-11T23:59:59.000Z

34

The Next Generation Nuclear Plant (NGNP) Project  

SciTech Connect (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 DOEĺs 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

35

Fourth Generation Nuclear Weapons: Military effectiveness and collateral effects  

E-Print Network [OSTI]

The paper begins with a general introduction and update to Fourth Generation Nuclear Weapons (FGNW), and then addresses some particularly important military aspects on which there has been only limited public discussion so far. These aspects concern the unique military characteristics of FGNWs which make them radically different from both nuclear weapons based on previous-generation nuclear-explosives and from conventional weapons based on chemical-explosives: yields in the 1 to 100 tons range, greatly enhanced coupling to targets, possibility to drive powerful shaped charged jets and forged fragments, enhanced prompt radiation effects, reduced collateral damage and residual radioactivity, etc.

Gsponer, A

2005-01-01T23:59:59.000Z

36

Method and apparatus for generating low energy nuclear particles  

DOE Patents [OSTI]

A particle accelerator (12) generates an input particle beam having an initial energy level above a threshold for generating secondary nuclear particles. A thin target (14) is rotated in the path of the input beam for undergoing nuclear reactions to generate the secondary particles and correspondingly decrease energy of the input beam to about the threshold. The target (14) produces low energy secondary particles and is effectively cooled by radiation and conduction. A neutron scatterer (44) and a neutron filter (42) are also used for preferentially degrading the secondary particles into a lower energy range if desired.

Powell, James R. (Shoreham, NY); Reich, Morris (Flushing, NY); Ludewig, Hans (Brookhaven, NY); Todosow, Michael (Miller Place, NY)

1999-02-09T23:59:59.000Z

37

Method and apparatus for generating low energy nuclear particles  

DOE Patents [OSTI]

A particle accelerator generates an input particle beam having an initial energy level above a threshold for generating secondary nuclear particles. A thin target is rotated in the path of the input beam for undergoing nuclear reactions to generate the secondary particles and correspondingly decrease energy of the input beam to about the threshold. The target produces low energy secondary particles and is effectively cooled by radiation and conduction. A neutron scatterer and a neutron filter are also used for preferentially degrading the secondary particles into a lower energy range if desired. 18 figs.

Powell, J.R.; Reich, M.; Ludewig, H.; Todosow, M.

1999-02-09T23:59:59.000Z

38

An Integrated Safety Assessment Methodology for Generation IV Nuclear Systems  

SciTech Connect (OSTI)

The Generation IV International Forum (GIF) Risk and Safety Working Group (RSWG) was created to develop an effective approach for the safety of Generation IV advanced nuclear energy systems. Early work of the RSWG focused on defining a safety philosophy founded on lessons learned from current and prior generations of nuclear technologies, and on identifying technology characteristics that may help achieve Generation IV safety goals. More recent RSWG work has focused on the definition of an integrated safety assessment methodology for evaluating the safety of Generation IV systems. The methodology, tentatively called ISAM, is an integrated ôtoolkitö consisting of analytical techniques that are available and matched to appropriate stages of Generation IV system concept development. The integrated methodology is intended to yield safety-related insights that help actively drive the evolving design throughout the technology development cycle, potentially resulting in enhanced safety, reduced costs, and shortened development time.

Timothy J. Leahy

2010-06-01T23:59:59.000Z

39

U.S. Nuclear Generation of Electricity  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLasDelivered energy consumption by sector Transportation EnergyGlossary API5382009 2010Nuclear

40

THE BIRTH OF NUCLEAR-GENERATED ELECTRICITY  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security AdministrationcontrollerNanocrystallineForeign Object DamageSystemsU.S. TALKS1 | ETHANKSGIVINGBIRTH

Note: This page contains sample records for the topic "nuclear generation corp" 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

Methane generation at Grand Gulf Nuclear Station  

SciTech Connect (OSTI)

The methane generation at Grand Gulf has been brought to light twice. The initial event occurred in February 1990 and the second in December 1993. Both events involved the receipt of a cask at Barnwell Waste Management Facility that when opened indicated a gas escaping. The gas was subsequently sampled and indicated a percentage of explosive gas. Both events involved powdered resin and indicated that the generation was from a bacterial attack of the organic materials (cellulose in the powdered resin mixture). The first event occurred and was believed to be isolated in a particular waste stream. The situation was handled and a biocide was found to be effective in treatment of liners until severe cross contamination of another waste stream occurred. This allowed the shipment of a liner that was required to be sampled for explosive gases. The biocide used by GGNS was allowed reintroduction into the floor drains and this allowed the buildup of immunity of the bacterial population to this particular biocide. The approval of a new biocide has currently allowed GGNS to treat liners and ship them offsite.

Carver, M.L. [Entergy Operations, Inc., Grand Gulf Nuclear Station, Port Gibson, MS (United States)

1995-09-01T23:59:59.000Z

42

ADVANCED CERAMIC MATERIALS FOR NEXT-GENERATION NUCLEAR APPLICATIONS  

SciTech Connect (OSTI)

Rising global energy demands coupled with increased environmental concerns point to one solution; they must reduce their dependence on fossil fuels that emit greenhouse gases. As the global community faces the challenge of maintaining sovereign nation security, reducing greenhouse gases, and addressing climate change nuclear power will play a significant and likely growing role. In the US, nuclear energy already provides approximately one-fifth of the electricity used to power factories, offices, homes, and schools with 104 operating nuclear power plants, located at 65 sites in 31 states. Additionally, 19 utilities have applied to the US Nuclear Regulatory Commission (NRC) for construction and operating licenses for 26 new reactors at 17 sites. This planned growth of nuclear power is occurring worldwide and has been termed the 'nuclear renaissance.' As major industrial nations craft their energy future, there are several important factors that must be considered about nuclear energy: (1) it has been proven over the last 40 years to be safe, reliable and affordable (good for Economic Security); (2) its technology and fuel can be domestically produced or obtained from allied nations (good for Energy Security); and (3) it is nearly free of greenhouse gas emissions (good for Environmental Security). Already an important part of worldwide energy security via electricity generation, nuclear energy can also potentially play an important role in industrial processes and supporting the nation's transportation sector. Coal-to-liquid processes, the generation of hydrogen and supporting the growing potential for a greatly increased electric transportation system (i.e. cars and trains) mean that nuclear energy could see dramatic growth in the near future as we seek to meet our growing demand for energy in cleaner, more secure ways. In order to address some of the prominent issues associated with nuclear power generation (i.e., high capital costs, waste management, and proliferation), the worldwide community is working to develop and deploy new nuclear energy systems and advanced fuel cycles. These new nuclear systems address the key challenges and include: (1) extracting the full energy value of the nuclear fuel; (2) creating waste solutions with improved long term safety; (3) minimizing the potential for the misuse of the technology and materials for weapons; (4) continually improving the safety of nuclear energy systems; and (5) keeping the cost of energy affordable.

Marra, J.

2010-09-29T23:59:59.000Z

43

Corrosion-induced gas generation in a nuclear waste repository: Reactive geochemistry and multiphase flow effect  

E-Print Network [OSTI]

Mallants, D. , 2002. Gas generation and migration in Boomof Post-Disposal Gas Generation in a Repository for SpentCorrosion-Induced Gas Generation in a Nuclear Waste

Xu, T.

2009-01-01T23:59:59.000Z

44

New Generation Nuclear Plant -- High Level Functions and Requirements  

SciTech Connect (OSTI)

This functions and requirements (F&R) document was prepared for the Next Generation Nuclear Plant (NGNP) Project. The highest-level functions and requirements for the NGNP preconceptual design are identified in this document, which establishes performance definitions for what the NGNP will achieve. NGNP designs will be developed based on these requirements by commercial vendor(s).

J. M. Ryskamp; E. J. Gorski; E. A. Harvego; S. T. Khericha; G. A. Beitel

2003-09-01T23:59:59.000Z

45

Hydrogen Production from the Next Generation Nuclear Plant  

SciTech Connect (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

46

Next Generation Nuclear Plant Materials Selection and Qualification Program Plan  

SciTech Connect (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 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

47

Next Generation Nuclear Plant Materials Research and Development Program Plan  

SciTech Connect (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

48

Technological Transfer from Research Nuclear Reactors to New Generation Nuclear Power Reactors  

SciTech Connect (OSTI)

The goal of this paper is the analysis of the technological transfer role in the nuclear field, with particular emphasis on nuclear reactors domain. The presentation is sustained by historical arguments. In this frame, it is very important to start with the achievements of the first nuclear systems, for instant those with natural uranium as fuel and heavy water as moderator, following in time through the history until the New Generation Nuclear Power Reactors.Starting with 1940, the accelerated development of the industry has implied the increase of the global demand for energy. In this respect, the nuclear energy could play an important role, being essentially an unlimited source of energy. However, the nuclear option faces the challenges of increasingly demanding safety requirements, economic competitiveness and public acceptance. Worldwide, a significant amount of experience has been accumulated during development, licensing, construction, and operation of nuclear power reactors. The experience gained is a strong basis for further improvements. Actually, the nuclear programs of many countries are addressing the development of advanced reactors, which are intended to have better economics, higher reliability, improved safety, and proliferation-resistant characteristics in order to overcome the current concerns about nuclear power. Advanced reactors, now under development, may help to meet the demand for energy power of both developed and developing countries as well as for district heating, desalination and for process heat.The paper gives historical examples that illustrate the steps pursued from first research nuclear reactors to present advanced power reactors. Emphasis was laid upon the fact that the progress is due to the great discoveries of the nuclear scientists using the technological transfer.

Radulescu, Laura ['Horia Hulubei' National Institute of Nuclear Physics and Engineering, PO BOX MG-6, Bucharest 077125 (Romania); Pavelescu, Margarit [Academy of Romanian Scientists, Bucharest (Romania)

2010-01-21T23:59:59.000Z

49

Salt disposal of heat-generating nuclear waste.  

SciTech Connect (OSTI)

This report summarizes the state of salt repository science, reviews many of the technical issues pertaining to disposal of heat-generating nuclear waste in salt, and proposes several avenues for future science-based activities to further the technical basis for disposal in salt. There are extensive salt formations in the forty-eight contiguous states, and many of them may be worthy of consideration for nuclear waste disposal. The United States has extensive experience in salt repository sciences, including an operating facility for disposal of transuranic wastes. The scientific background for salt disposal including laboratory and field tests at ambient and elevated temperature, principles of salt behavior, potential for fracture damage and its mitigation, seal systems, chemical conditions, advanced modeling capabilities and near-future developments, performance assessment processes, and international collaboration are all discussed. The discussion of salt disposal issues is brought current, including a summary of recent international workshops dedicated to high-level waste disposal in salt. Lessons learned from Sandia National Laboratories' experience on the Waste Isolation Pilot Plant and the Yucca Mountain Project as well as related salt experience with the Strategic Petroleum Reserve are applied in this assessment. Disposal of heat-generating nuclear waste in a suitable salt formation is attractive because the material is essentially impermeable, self-sealing, and thermally conductive. Conditions are chemically beneficial, and a significant experience base exists in understanding this environment. Within the period of institutional control, overburden pressure will seal fractures and provide a repository setting that limits radionuclide movement. A salt repository could potentially achieve total containment, with no releases to the environment in undisturbed scenarios for as long as the region is geologically stable. Much of the experience gained from United States repository development, such as seal system design, coupled process simulation, and application of performance assessment methodology, helps define a clear strategy for a heat-generating nuclear waste repository in salt.

Leigh, Christi D. (Sandia National Laboratories, Carlsbad, NM); Hansen, Francis D.

2011-01-01T23:59:59.000Z

50

HIGH EFFICIENCY GENERATION OF HYDROGEN FUELS USING NUCLEAR POWER  

SciTech Connect (OSTI)

OAK B202 HIGH EFFICIENCY GENERATION OF HYDROGEN FUELS USING NUCLEAR POWER. Combustion of fossil fuels, used to power transportation, generate electricity, heat homes and fuel industry provides 86% of the world's energy. Drawbacks to fossil fuel utilization include limited supply, pollution, and carbon dioxide emissions. Carbon dioxide emissions, thought to be responsible for global warming, are now the subject of international treaties. Together, these drawbacks argue for the replacement of fossil fuels with a less-polluting potentially renewable primary energy such as nuclear energy. Conventional nuclear plants readily generate electric power but fossil fuels are firmly entrenched in the transportation sector. Hydrogen is an environmentally attractive transportation fuel that has the potential to displace fossil fuels. Hydrogen will be particularly advantageous when coupled with fuel cells. Fuel cells have higher efficiency than conventional battery/internal combustion engine combinations and do not produce nitrogen oxides during low-temperature operation. Contemporary hydrogen production is primarily based on fossil fuels and most specifically on natural gas. When hydrogen is produced using energy derived from fossil fuels, there is little or no environmental advantage. There is currently no large scale, cost-effective, environmentally attractive hydrogen production process available for commercialization, nor has such a process been identified. The objective of this work is to find an economically feasible process for the production of hydrogen, by nuclear means, using an advanced high-temperature nuclear reactor as the primary energy source. Hydrogen production by thermochemical water-splitting (Appendix A), a chemical process that accomplishes the decomposition of water into hydrogen and oxygen using only heat or, in the case of a hybrid thermochemical process, by a combination of heat and electrolysis, could meet these goals. Hydrogen produced from fossil fuels has trace contaminants (primarily carbon monoxide) that are detrimental to precious metal catalyzed fuel cells, as is now recognized by many of the world's largest automobile companies. Thermochemical hydrogen will not contain carbon monoxide as an impurity at any level. Electrolysis, the alternative process for producing hydrogen using nuclear energy, suffers from thermodynamic inefficiencies in both the production of electricity and in electrolytic parts of the process. The efficiency of electrolysis (electricity to hydrogen) is currently about 80%. Electric power generation efficiency would have to exceed 65% (thermal to electrical) for the combined efficiency to exceed the 52% (thermal to hydrogen) calculated for one thermochemical cycle. Thermochemical water-splitting cycles have been studied, at various levels of effort, for the past 35 years. They were extensively studied in the late 70s and early 80s but have received little attention in the past 10 years, particularly in the U.S. While there is no question about the technical feasibility and the potential for high efficiency, cycles with proven low cost and high efficiency have yet to be developed commercially. Over 100 cycles have been proposed, but substantial research has been executed on only a few. This report describes work accomplished during a three-year project whose objective is to ''define an economically feasible concept for production of hydrogen, by nuclear means, using an advanced high temperature nuclear reactor as the energy source.'' The emphasis of the first phase was to evaluate thermochemical processes which offer the potential for efficient, cost-effective, large-scale production of hydrogen from water in which the primary energy input is high temperature heat from an advanced nuclear reactor and to select one (or, at most three) for further detailed consideration. During Phase 1, an exhaustive literature search was performed to locate all cycles previously proposed. The cycles located were screened using objective criteria to determine which could benefit, in terms of efficien

BROWN,LC; BESENBRUCH,GE; LENTSCH,RD; SCHULTZ,KR; FUNK,JF; PICKARD,PS; MARSHALL,AC; SHOWALTER,SK

2003-06-01T23:59:59.000Z

51

US Army Corps of Engineers  

E-Print Network [OSTI]

. Netherland, WES David Sisneros, U.S. Bureau of Reclamation Alison M. Fox, William T. Hailer, University Liquid and Slow-Release Pellet Applications by Michael D. Netherland U.S. Army Corps of Engineers / by Michael D. Netherland ... [et al.]; prepared for U.S. Army Corps of Engineers. 64p. : ill. ; 28 cm

US Army Corps of Engineers

52

Alternative similarity renormalization group generators in nuclear structure calculations  

E-Print Network [OSTI]

The similarity renormalization group (SRG) has been successfully applied to soften interactions for ab initio nuclear calculations. In almost all practical applications in nuclear physics, an SRG generator with the kinetic energy operator is used. With this choice, a fast convergence of many-body calculations can be achieved, but at the same time substantial three-body interactions are induced even if one starts from a purely two-nucleon (NN) Hamiltonian. Three-nucleon (3N) interactions can be handled by modern many-body methods. However, it has been observed that when including initial chiral 3N forces in the Hamiltonian, the SRG transformations induce a non-negligible four-nucleon interaction that cannot be currently included in the calculations for technical reasons. Consequently, it is essential to investigate alternative SRG generators that might suppress the induction of many-body forces while at the same time might preserve the good convergence. In this work we test two alternative generators with operators of block structure in the harmonic oscillator basis. In the no-core shell model calculations for 3H, 4He and 6Li with chiral NN force, we demonstrate that their performances appear quite promising.

Nuiok M. Dicaire; Conor Omand; Petr Navratil

2014-08-22T23:59:59.000Z

53

Removal of deposited copper from nuclear steam generators  

SciTech Connect (OSTI)

A review of the copper-removal process implemented during the cleaning of the NPD nuclear steam generator in Ontario revealed that major shortcomings in the process were depletion of the strong ammonia solution and relatively poor copper removal. Tests have shown that the concentration of the ammonia solution can be preserved close to its initial value, and high concentrations of complexed copper obtained, by sparging the ammonia solution with oxygen recirculating through a gas recirculation loop. Using recirculating oxygen for sparging at ambient air temperature, approximately 11 g/l of copper were dissolved by 100 g/l ammonia solution while the gaseous ammonia content of the recirculating gas remained well below the lower flammability limit. The corrosion rates of mild steel and commonly used nuclear steam generator tube materials in oxygenated ammonia solution were less than 30 mil/yr and no intergranular attack of samples was observed during tests. A second technique studied for the removal of copper is to ammoniate the spent iron-removal solvent to approximately pH 9.5 and sparge with recirculating oxygen. Complexed ferric iron in the spent iron-removal solvent was found to be the major oxidizing agent for metallic copper. The ferric iron can be derived from oxidation of dissolved ferrous iron to the ferric state or from dissolved oxides of iron directly. To extract copper from the secondary sides of nuclear steam generators, strong ammonia solution sparged with recirculating oxygen is recommended as the first stage, while ammoniated spent iron-removal solvent sparged with recirculating oxygen may be used to remove the copper freshly exposed during the removal of iron.

McSweeney, P.

1982-05-01T23:59:59.000Z

54

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]

IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA Energy and Environment

Nero, A.V.

2010-01-01T23:59:59.000Z

55

Peace Corps | Agriculture Agriculture Volunteers  

E-Print Network [OSTI]

Peace Corps | Agriculture Agriculture Volunteers Agriculture is the primary economic activity Volunteers contribute sustain- able solutions to a community's agricultural issues and help preserve natural resources. Programs and Sample Projects Agriculture and Forestry Extension ┬Ě Collaborate with farmers

Kaminsky, Werner

56

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

SciTech Connect (OSTI)

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

57

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

SciTech Connect (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

58

NNSA Administrator Addresses the Next Generation of Nuclear Security Professionals: Part 1  

ScienceCinema (OSTI)

Administrator Thomas DAgostino of the National Nuclear Security Administration addressed the next generation of nuclear security professionals during the opening session of todays 2009 Department of Energy (DOE) Computational Science Graduate Fellowship Annual Conference. Administrator DAgostino discussed NNSAs role in implementing President Obamas nuclear security agenda and encouraged the computing science fellows to consider careers in nuclear security.

Thomas D'Agostino

2010-09-01T23:59:59.000Z

59

Decision-support tool for assessing future nuclear reactor generation portfolios.  

E-Print Network [OSTI]

Decision-support tool for assessing future nuclear reactor generation portfolios. Shashi Jain, where especially capital costs are known to be highly uncertain. Differ- ent nuclear reactor types uncertainties in the cost elements of a nuclear power plant, to provide an optimal portfolio of nuclear reactors

Oosterlee, Cornelis W. "Kees"

60

NNSA Administrator Addresses the Next Generation of Nuclear Security Professionals: Part 2  

ScienceCinema (OSTI)

Administrator Thomas DAgostino of the National Nuclear Security Administration addressed the next generation of nuclear security professionals during the opening session of todays 2009 Department of Energy (DOE) Computational Science Graduate Fellowship Annual Conference. Administrator DAgostino discussed NNSAs role in implementing President Obamas nuclear security agenda and encouraged the computing science fellows to consider careers in nuclear security.

Thomas D'Agostino

2010-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation corp" 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

Marine Corps Base Quantico Achieves 85% Savings in Parking Lighting...  

Energy Savers [EERE]

Marine Corps Base Quantico Achieves 85% Savings in Parking Lighting Marine Corps Base Quantico Achieves 85% Savings in Parking Lighting Marine Corps Base Quantico (MCBQ) in...

62

Next Generation Nuclear Plant Resilient Control System Functional Analysis  

SciTech Connect (OSTI)

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

63

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

SciTech Connect (OSTI)

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

64

Next Generation Nuclear Plant Materials Research and Development Program Plan  

SciTech Connect (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. 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

65

Next Generation Nuclear Plant Research and Development Program Plan  

SciTech Connect (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

66

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

SciTech Connect (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

67

Next Generation Nuclear Plant Methods Technical Program Plan  

SciTech Connect (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 ôhighly rankedö 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

68

Next Generation Nuclear Plant Methods Technical Program Plan  

SciTech Connect (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 ôhighly rankedö 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

69

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

SciTech Connect (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 ôhighly rankedö 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

70

Powerspan Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 No revision hasInformation Earth'sOklahoma/GeothermalOrangePeru:Job CorpPowerVerde Inc formerlyPowerspan Corp

71

Granular flow in pebble-bed nuclear reactors: Scaling, Dust Generation, and Stress  

E-Print Network [OSTI]

Granular flow in pebble-bed nuclear reactors: Scaling, Dust Generation, and Stress Chris H. Keywords: granular flow, dust generation, numerical methods 1. Introduction Pebble-bed nuclear reactors prototypes of pebble-bed reactors, significant quantities of graphite dust have been observed due to rubbing

Rycroft, Chris H.

72

Heat Exchangers for the Next Generation of Nuclear Reactors  

SciTech Connect (OSTI)

The realisation that fossil fuel resources are finite, the associated rising price and a growing concern about greenhouse gas emissions, has resulted in renewed interest in nuclear energy. Generation IV and other programmes are looking at a variety of new reactors. These reactors vary in type from Very High Temperature Gas Cooled Reactors (VHTR) to Liquid Metal Fast Reactors (LFR and SFR) with cooling mediums that include: - Helium, - Supercritical carbon dioxide, - Sodium, - Lead, - Molten salts. In addition interest is not just focused on production of electrical power with an efficiency greater than that associated with the Rankine Cycle (typically 30 -35%); there is now genuine interest in nuclear energy as a heat source for hydrogen production, via the Sulphur Iodine Process (SI) or high temperature electrolysis. The production of electrical power at higher efficiency via a Brayton Cycle, and hydrogen production requires both heat at higher temperatures, up to 1000 deg C and high effectiveness heat exchange to transfer the heat to either the power or process cycle. This presents new challenges for the heat exchangers. If plant efficiencies are to be improved there is a need for: - High effectiveness heat exchange at minimal pressure drop; - Compact heat exchange to improve safety and economics; - An ability to build coded heat exchangers in a variety of nickel based alloys, oxide dispersion strengthened alloys (ODS) and ceramic materials to address the temperature, life and corrosion issues associated with these demanding duties. Heatric has already given consideration to many of these challenges. Their Print Circuit Heat Exchanger (PCHE) and Formed Plate Heat Exchanger (FPHE) technology which are commercially available today, will fulfill all of the duties up to temperatures of 950 deg C. In addition products currently under development will further increase the temperature and pressure range, while offering greater corrosion resistance and operational life. This paper outlines the challenges for the heat exchangers and the development required, with particular attention given to material selection. It is further the objective of this study to demonstrate that heat exchangers such as PCHE and FPHE are able to meet the above challenges. (authors)

Xiuqing, Li; Le Pierres, Renaud; Dewson, Stephen John [Heatric Division of Meggitt (UK) Ltd., 46 Holton Road, Holton Heath, Poole, Dorset BH16 6LT (United Kingdom)

2006-07-01T23:59:59.000Z

73

Next Generation Nuclear Plant Research and Development Program Plan  

SciTech Connect (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

74

A Technology Roadmap for Generation IV Nuclear Energy Systems Executive Summary  

SciTech Connect (OSTI)

To meet future energy needs, ten countries--Argentina, Brazil, Canada, France, Japan, the Republic of Korea, the Republic of South Africa, Switzerland, the United Kingdom, and the United States--have agreed on a framework for international cooperation in research for an advanced generation of nuclear energy systems, known as Generation IV. These ten countries have joined together to form the Generation IV International Forum (GIF) to develop future-generation nuclear energy systems that can be licensed, constructed, and operated in a manner that will provide competitively priced and reliable energy products while satisfactorily addressing nuclear safety, waste, proliferation, and public perception concerns. The objective for Generation IV nuclear energy systems is to be available for international deployment before the year 2030, when many of the world's currently operating nuclear power plants will be at or near the end of their operating licenses.

None

2003-03-01T23:59:59.000Z

75

New Jersey Nuclear Profile - PSEG Salem Generating Station  

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

PSEG Salem Generating Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License...

76

New Jersey Nuclear Profile - PSEG Hope Creek Generating Station  

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

PSEG Hope Creek Generating Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License...

77

Illinois Nuclear Profile - LaSalle Generating Station  

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

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

78

US Army Corps of Engineersr~,  

E-Print Network [OSTI]

-United States-Interviews. 3. Water resources development-Government policy-United States-History-Sources. I individuals who have influenced United States water resources development. I commend this interview to allAwareness: The United States Army Corps of Engineers Environmental Advisory Board, 19704980, Reshaping National Water

US Army Corps of Engineers

79

Peace Corps / Environment Environment Volunteers  

E-Print Network [OSTI]

Peace Corps / Environment Environment Volunteers Environmental damage can have enormous choices about how to best protect and preserve the local environment. Programs and Sample Projects and communications technology, agriculture, and environment. We are looking for applicants with a variety of skills

Kaminsky, Werner

80

Membranes for H2 generation from nuclear powered thermochemical cycles.  

SciTech Connect (OSTI)

In an effort to produce hydrogen without the unwanted greenhouse gas byproducts, high-temperature thermochemical cycles driven by heat from solar energy or next-generation nuclear power plants are being explored. The process being developed is the thermochemical production of Hydrogen. The Sulfur-Iodide (SI) cycle was deemed to be one of the most promising cycles to explore. The first step of the SI cycle involves the decomposition of H{sub 2}SO{sub 4} into O{sub 2}, SO{sub 2}, and H{sub 2}O at temperatures around 850 C. In-situ removal of O{sub 2} from this reaction pushes the equilibrium towards dissociation, thus increasing the overall efficiency of the decomposition reaction. A membrane is required for this oxygen separation step that is capable of withstanding the high temperatures and corrosive conditions inherent in this process. Mixed ionic-electronic perovskites and perovskite-related structures are potential materials for oxygen separation membranes owing to their robustness, ability to form dense ceramics, capacity to stabilize oxygen nonstoichiometry, and mixed ionic/electronic conductivity. Two oxide families with promising results were studied: the double-substituted perovskite A{sub x}Sr{sub 1-x}Co{sub 1-y}B{sub y}O{sub 3-{delta}} (A=La, Y; B=Cr-Ni), in particular the family La{sub x}Sr{sub 1-x}Co{sub 1-y}Mn{sub y}O{sub 3-{delta}} (LSCM), and doped La{sub 2}Ni{sub 1-x}M{sub x}O{sub 4} (M = Cu, Zn). Materials and membranes were synthesized by solid state methods and characterized by X-ray and neutron diffraction, SEM, thermal analyses, calorimetry and conductivity. Furthermore, we were able to leverage our program with a DOE/NE sponsored H{sub 2}SO{sub 4} decomposition reactor study (at Sandia), in which our membranes were tested in the actual H{sub 2}SO{sub 4} decomposition step.

Nenoff, Tina Maria; Ambrosini, Andrea; Garino, Terry J.; Gelbard, Fred; Leung, Kevin; Navrotsky, Alexandra (University of California, Davis, CA); Iyer, Ratnasabapathy G. (University of California, Davis, CA); Axness, Marlene

2006-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation corp" 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

Utah_hexcel_corp  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched Ferromagnetism inS-4500II Field EmissionFunctional Materials forHannah Thompsen

82

NEXT GENERATION NUCLEAR PLANT NGNP Technology Development Roadmapping  

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

ISR Inner Side Reflector Kc Fracture Toughness kg Kilogram K-T Kepner-Tregoe KTA German nuclear technical committee kW Kilowatt LANL Los Alamos National Laboratory LBE Licensing...

83

Kyosemi Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia: Energy Resources Jump to:46 - 429 ThrottledInformation Kumasi Institute of Technology andKurtKyosemi Corp

84

Paving the path for next-generation nuclear energy | Department...  

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

heat that could be used for industrial processes such as seawater desalination or plastics production. Today, China has begun construction of a prototype Generation-IV reactor,...

85

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

SciTech Connect (OSTI)

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

86

Maintenance practices for emergency diesel generator engines onboard United States Navy Los Angeles class nuclear submarines  

E-Print Network [OSTI]

The United States Navy has recognized the rising age of its nuclear reactors. With this increasing age comes increasing importance of backup generators. In addition to the need for decay heat removal common to all (naval ...

Hawks, Matthew Arthur

2006-01-01T23:59:59.000Z

87

Design Features and Technology Uncertainties for the Next Generation Nuclear Plant  

SciTech Connect (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

88

Seismic risk assessment as applied to the Zion Nuclear Generating Station  

SciTech Connect (OSTI)

To assist the US Nuclear Regulatory Commission (NRC) in its licensing and evaluation role, the NRC funded the Seismic Safety Margins Research Program (SSMRP) at Lawrence Livermore National Laboratory (LLNL) with the goal of developing tools and data bases to evaluate the risk of earthquake caused radioactive release from a commercial nuclear power plant. This paper describes the SSMRP risk assessment methodology and the results generated by applying this methodology to the Zion Nuclear Generating Station. In addition to describing the failure probabilities and risk values, the effects of assumptions about plant configuration, plant operation, and dependence will be given.

Wells, J.

1984-08-01T23:59:59.000Z

89

Next Generation Nuclear Plant Project 2009 Status Report  

SciTech Connect (OSTI)

The mission of the NGNP Project is to broaden the environmental and economic benefits of nuclear energy technology to the United States and other economies by demonstrating its applicability to market sectors not served by light water reactors (LWRs). Those markets typically use fossil fuels to fulfill their energy needs, and high temperature gas-cooled reactors (HTGRs) like the NGNP can reduce this dependence and the resulting carbon footprint.

Larry Demick; Jim Kinsey; Keith Perry; Dave Petti

2010-05-01T23:59:59.000Z

90

Raytheon explores thorium for next generation nuclear reactor  

SciTech Connect (OSTI)

Few new orders for nuclear power plants have been placed anywhere in the world in the last 20 years, but that is not discouraging Raytheon Engineers Constructors from making plans to explore new light water reactor technologies for commercial markets. The Lexington, Mass.-based company, which has extensive experience in nuclear power engineering and construction, has a vision for the light water reactor of the future - one that is based on the use of thorium-232, an element that decays over several steps to uranium-233. The use of thorium and a small amount of uranium that is 20 percent enriched is seen as providing operational, environmental, and safety advantages over reactors using the standard fuel mixture of uranium-238 and enriched uranium-235. According to Raytheon, the system could improve the economics of some reactors' operations by reducing fuel costs and lowering related waste volumes. At the same time, reactor safety could be improved by simpler control rod systems and the absence from reactor coolant of corrosive boric acid, which is used to slow neutrons in order to enhance reactions. Using thorium is also attractive because more of the fuel is burned up by the reactor, an estimated 12 percent as compared to about 4 percent for U-235. However, the technology's greatest attraction may well be its implications for nuclear proliferation. Growing plutonium inventories embedded in spent fuel rods from light water reactors have sparked concern worldwide. But according to Raytheon, using a thorium-based fuel core would alleviate this concern because it would produce only small quantities of plutonium. A thorium-based fuel system would produce 12 kilograms of plutonium over a decade versus 2,235 kilograms for an equivalent reactor operating with conventional uranium fuel.

Crawford, M.

1994-03-08T23:59:59.000Z

91

Voluntary Protection Program Onsite Review, Parsons Corp., Salt...  

Office of Environmental Management (EM)

Parsons Corp., Salt Waste Processing Facility Construction Project - May 2014 Voluntary Protection Program Onsite Review, Parsons Corp., Salt Waste Processing Facility Construction...

92

Next-generation nuclear fuel withstands high-temperature accident  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the Contributions andDataNationalNewport News Business55NewsNext

93

Ambient Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of Inspector GeneralDepartmentAUDIT REPORTOpenWende NewSowitecAWSAgri-EnergyAmbene Jump to:Corp Jump to:

94

EPS Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublic Utilities Address:011-DNA Jump37. It is classified as ASHRAEDuvalJusticeEPS Corp Jump to: navigation, search

95

Lab-Corps Announcement Recap  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:Year in3.pdfEnergy Health andofIanJennifer SomersKnown ChallengesLES'LIFELM5841Lab-Corps

96

Mascoma Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia: Energy Resources Jump to:46 - 429Lacey,(MonasterLowellis a townLoading map...(Redirected fromCorp Jump to:

97

Enpower Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 No revision has beenFfe2fb55-352f-473b-a2dd-50ae8b27f0a6 NoSan Leandro, California Zip:Enginuity Energy,Enpower Corp

98

Ferrotec Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublic Utilities Address:011-DNA Jump37.California: EnergyFeilden Clegg BradleyFerrotec Corp Jump to: navigation,

99

Intel Corp | Open Energy Information  

Open Energy Info (EERE)

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

100

11.11.2004 08:48:00 GMT China aims to employ nuclear fusion technology in power generation  

E-Print Network [OSTI]

Search 11.11.2004 08:48:00 GMT China aims to employ nuclear fusion technology in power generation to employ nuclear fusion technologies in power generation by 2050. China will adopt a three-step strategy with thermonuclear reactors; the second step aims to raise the utilization rate of nuclear fuels from the current 1

Note: This page contains sample records for the topic "nuclear generation corp" 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

Potential growth of nuclear and coal electricity generation in the US  

SciTech Connect (OSTI)

Electricity demand should continue to grow at about the same rate as GNP, creating a need for large amounts of new generating capacity over the next fifty years. Only coal and nuclear at this time have the abundant domestic resources and assured technology to meet this need. However, large increase in both coal and nuclear usage will require solutions to many of the problems that now deter their increased usage. For coal, the problems center around the safety and environmental impacts of increased coal mining and coal combustion. For nuclear, the problems center around reactor safety, radioactive waste disposal, financial risk, and nuclear materials safeguards. This report assesses the impacts associated with a range of projected growth rates in electricity demand over the next 50 years. The resource requirements and waste generation resulting from pursuing the coal and nuclear fuel options to meet the projected growth rates are estimated. The fuel requirements and waste generation for coal plants are orders of magnitude greater than for nuclear. Improvements in technology and waste management practices must be pursued to mitigate environmental and safety concerns about electricity generation from both options. 34 refs., 18 figs., 14 tabs.

Bloomster, C.H.; Merrill, E.T.

1989-08-01T23:59:59.000Z

102

Present and future nuclear power generation as a reflection of individual countries' resources and objectives  

SciTech Connect (OSTI)

The nuclear reactor industry has been in a state of decline for more than a decade in most of the world. The reasons are numerous and often unique to the energy situation of individual countries. Two commonly cited issues influence decisions relating to construction of reactors: costs and the need, or lack thereof, for additional generating capacity. Public concern has ''politicized'' the nuclear industry in many non-communist countries, causing a profound effect on the economics of the option. The nuclear installations and future plans are reviewed on a country-by-country basis for 36 countries in the light of the resources and objectives of each. Because oil and gas for power production throughout the world are being phased out as much as possible, coal-fired generation currently tends to be the chosen alternative to nuclear power production. Exceptions occur in many of the less developed countries that collectively have a very limited operating experience with nuclear reactors. The Chernobyl accident in the USSR alarmed the public; however, national strategies and plans to build reactors have not changed markedly in the interim. Assuming that the next decade of nuclear power generation is uneventful, additional electrical demand would cause the nuclear power industry to experience a rejuvenation in Europe as well as in the US. 80 refs., 3 figs., 22 tabs.

Borg, I.Y.

1987-06-26T23:59:59.000Z

103

Apparatus for nuclear transmutation and power production using an intense accelerator-generated thermal neutron flux  

DOE Patents [OSTI]

Apparatus for nuclear transmutation and power production using an intense accelerator-generated thermal neutron flux. High thermal neutron fluxes generated from the action of a high power proton accelerator on a spallation target allows the efficient burn-up of higher actinide nuclear waste by a two-step process. Additionally, rapid burn-up of fission product waste for nuclides having small thermal neutron cross sections, and the practicality of small material inventories while achieving significant throughput derive from employment of such high fluxes. Several nuclear technology problems are addressed including 1. nuclear energy production without a waste stream requiring storage on a geological timescale, 2. the burn-up of defense and commercial nuclear waste, and 3. the production of defense nuclear material. The apparatus includes an accelerator, a target for neutron production surrounded by a blanket region for transmutation, a turbine for electric power production, and a chemical processing facility. In all applications, the accelerator power may be generated internally from fission and the waste produced thereby is transmuted internally so that waste management might not be required beyond the human lifespan.

Bowman, C.D.

1992-11-03T23:59:59.000Z

104

Apparatus for nuclear transmutation and power production using an intense accelerator-generated thermal neutron flux  

DOE Patents [OSTI]

Apparatus for nuclear transmutation and power production using an intense accelerator-generated thermal neutron flux. High thermal neutron fluxes generated from the action of a high power proton accelerator on a spallation target allows the efficient burn-up of higher actinide nuclear waste by a two-step process. Additionally, rapid burn-up of fission product waste for nuclides having small thermal neutron cross sections, and the practicality of small material inventories while achieving significant throughput derive from employment of such high fluxes. Several nuclear technology problems are addressed including 1. nuclear energy production without a waste stream requiring storage on a geological timescale, 2. the burn-up of defense and commercial nuclear waste, and 3. the production of defense nuclear material. The apparatus includes an accelerator, a target for neutron production surrounded by a blanket region for transmutation, a turbine for electric power production, and a chemical processing facility. In all applications, the accelerator power may be generated internally from fission and the waste produced thereby is transmuted internally so that waste management might not be required beyond the human lifespan.

Bowman, Charles D. (Los Alamos, NM)

1992-01-01T23:59:59.000Z

106

CONTROL OF POPULATION DENSITIES SURROUNDING NUCLEAR POWER PLANTS. VOLUME 5 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA Energy and Environment

Nero, jA.V.

2010-01-01T23:59:59.000Z

107

D.McNew/GettyIMaGes San Onofre Nuclear Generating Station, California.  

E-Print Network [OSTI]

D.McNew/GettyIMaGes San Onofre Nuclear Generating Station, California. CORRESPONDENCE Checklist be supplied by solar power plants covering about 36,000 square kilometres of land in the desert southwest,theycanberampedupquickly.Annualinstallationofwind- energy capacity in the United States has quadrupled from Counterpoint Not wanted, not needed J. Doyne

108

Qualification of Class 1E static battery charges and inverters for nuclear power generating stations  

SciTech Connect (OSTI)

This standard describes methods for qualifying static battery chargers and inverters for Class 1E installations in environmentally controlled areas outside containment in nuclear power generating stations. The purpose of this standard is to provide specific procedures to meet the requirements of IEEE Std. 323-1974.

Not Available

1981-01-01T23:59:59.000Z

109

Generation IV Nuclear Energy Systems Ten-Year Program Plan Fiscal Year 2005, Volume 1  

SciTech Connect (OSTI)

As reflected in the U.S. ''National Energy Policy'', nuclear energy has a strong role to play in satisfying our nation's future energy security and environmental quality needs. The desirable environmental, economic, and sustainability attributes of nuclear energy give it a cornerstone position, not only in the U.S. energy portfolio, but also in the world's future energy portfolio. Accordingly, on September 20, 2002, U.S. Energy Secretary Spencer Abraham announced that, ''The United States and nine other countries have agreed to develop six Generation IV nuclear energy concepts''. The Secretary also noted that the systems are expected to ''represent significant advances in economics, safety, reliability, proliferation resistance, and waste minimization''. The six systems and their broad, worldwide research and development (R&D) needs are described in ''A Technology Roadmap for Generation IV Nuclear Energy Systems'' (hereafter referred to as the Generation IV Roadmap). The first 10 years of required U.S. R&D contributions to achieve the goals described in the Generation IV Roadmap are outlined in this Program Plan.

None

2005-03-01T23:59:59.000Z

110

U.S. Army Corps of Engineers  

Broader source: Energy.gov [DOE]

Presentation covers the U.S. Army Corps of Engineers and is given at the Spring 2010 Federal Utility Partnership Working Group (FUPWG) meeting in Rapid City, South Dakota.

111

Magnetic Field Generation in Planets and Satellites by Natural Nuclear Fission Reactors  

E-Print Network [OSTI]

One of the most fundamental problems in physics has been to understand the nature of the mechanism that generates the geomagnetic field and the magnetic fields of other planets and satellites. For decades, the dynamo mechanism, thought to be responsible for generating the geomagnetic field and other planetary magnetic fields, has been ascribed to convection in each planet's iron-alloy core. Recently, I described the problems inherent in Earth-core convection and proposed instead that the geomagnetic field is produced by a dynamo mechanism involving convection, not in the fluid core, but in the electrically conductive, fluid, fission-product sub-shell of a natural nuclear fission reactor at the center of the Earth, called the georeactor. Here I set forth in detail the commonality in the Solar System of the matter like that of the inside of the Earth, which is my basis for generalizing the concept of planetary magnetic field generation by natural planetocentric nuclear fission reactors.

J. Marvin Herndon

2007-09-27T23:59:59.000Z

112

1 hour, 59 minutes ago President Jacques Chirac announced plans to build a prototype fourth-generation nuclear reactor by 2020 as well as symbolic targets  

E-Print Network [OSTI]

-generation nuclear reactor by 2020 as well as symbolic targets for cutting France's reliance on oil in the coming and is conducting research into several new models of nuclear reactor. Business leaders in the French energy sector-generation nuclear reactor 1/5/06 3:19 PMPrint Story: France to develop fourth-generation nuclear reactor on Yahoo

113

A Statistical Model for Generating a Population of Unclassified Objects and Radiation Signatures Spanning Nuclear Threats  

SciTech Connect (OSTI)

This report describes an approach for generating a simulated population of plausible nuclear threat radiation signatures spanning a range of variability that could be encountered by radiation detection systems. In this approach, we develop a statistical model for generating random instances of smuggled nuclear material. The model is based on physics principles and bounding cases rather than on intelligence information or actual threat device designs. For this initial stage of work, we focus on random models using fissile material and do not address scenarios using non-fissile materials. The model has several uses. It may be used as a component in a radiation detection system performance simulation to generate threat samples for injection studies. It may also be used to generate a threat population to be used for training classification algorithms. In addition, we intend to use this model to generate an unclassified 'benchmark' threat population that can be openly shared with other organizations, including vendors, for use in radiation detection systems performance studies and algorithm development and evaluation activities. We assume that a quantity of fissile material is being smuggled into the country for final assembly and that shielding may have been placed around the fissile material. In terms of radiation signature, a nuclear weapon is basically a quantity of fissile material surrounded by various layers of shielding. Thus, our model of smuggled material is expected to span the space of potential nuclear weapon signatures as well. For computational efficiency, we use a generic 1-dimensional spherical model consisting of a fissile material core surrounded by various layers of shielding. The shielding layers and their configuration are defined such that the model can represent the potential range of attenuation and scattering that might occur. The materials in each layer and the associated parameters are selected from probability distributions that span the range of possibilities. Once an object is generated, its radiation signature is calculated using a 1-dimensional deterministic transport code. Objects that do not make sense based on physics principles or other constraints are rejected. Thus, the model can be used to generate a population of spectral signatures that spans a large space, including smuggled nuclear material and nuclear weapons.

Nelson, K; Sokkappa, P

2008-10-29T23:59:59.000Z

114

Generation IV Nuclear Energy Systems Construction Cost Reductions Through the Use of Virtual Environments  

SciTech Connect (OSTI)

The objective of this multi-phase project is to demonstrate the feasibility and effectiveness of using full-scale virtual reality simulation in the design, construction, and maintenance of future nuclear power plants. The project will test the suitability of immersive virtual reality technology to aid engineers in the design of the next generation nuclear power plant and to evaluate potential cost reductions that can be realized by optimization of installation and construction sequences. The intent is to see if this type of information technology can be used in capacities similar to those currently filled by full-scale physical mockups. This report presents the results of the completed project.

Timothy Shaw; Vaugh Whisker

2004-02-28T23:59:59.000Z

115

Generation IV Nuclear Energy Systems Construction Cost Reductions through the Use of Virtual Environments - Final Report  

SciTech Connect (OSTI)

Final report of 3 year DOE NERI-sponsored effort evaluating immersive virtual reality (CAVE) technology for design review, construction planning, and maintenance planning and training for next generation nuclear power plants. Program covers development of full-scale virtual mockups generated from 3D CAD data presented in a CAVE visualization facility. Mockups applied to design review of AP600/1000, Construction planning for AP 600, and AP 1000 maintenance evaluation. Proof of concept study also performed for GenIV PBMR models.

Timothy Shaw; Anthony Baratta; Vaughn Whisker

2005-02-28T23:59:59.000Z

116

IEEE Standard for qualification of Class 1E lead storage batteries for nuclear power generating stations  

SciTech Connect (OSTI)

This document describes qualification methods for Class 1E lead storage batteries and racks to be used in nuclear power generating stations outside of primary containment. Qualification required in ANSI/IEEE Std 279-1979 and IEEE Std 308-1978, can be demonstrated by using the procedures provided in this Standard in accordance with IEEE Std 323-1974. Battery sizing, maintenance, capacity testing, installation, charging equipment and consideration of other types batteries are beyond the scope of this Standard.

Not Available

1980-01-01T23:59:59.000Z

117

Confirmatory Survey Results for the Reactor Building Dome Upper Surfaces, Rancho Saco Nuclear Generating Station  

SciTech Connect (OSTI)

Results from a confirmatory survey of the upper structural surfaces of the Reactor Building Dome at the Rancho Seco Nuclear Generating Station (RSNGS) performed by the Oak Ridge Institute for Science and Education for the NRC. Also includes results of interlaboratory comparison analyses on several archived soil samples that would be provided by RSNGS personnel. The confirmatory surveys were performed on June 7 and 8, 2006.

Wade C. Adams

2006-10-25T23:59:59.000Z

118

Educating Next Generation Nuclear Criticality Safety Engineers at the Idaho National Laboratory  

SciTech Connect (OSTI)

One of the challenges in educating our next generation of nuclear safety engineers is the limitation of opportunities to receive significant experience or hands-on training prior to graduation. Such training is generally restricted to on-the-job-training before this new engineering workforce can adequately provide assessment of nuclear systems and establish safety guidelines. Participation in the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and the International Reactor Physics Experiment Evaluation Project (IRPhEP) can provide students and young professionals the opportunity to gain experience and enhance critical engineering skills. The ICSBEP and IRPhEP publish annual handbooks that contain evaluations of experiments along with summarized experimental data and peer-reviewed benchmark specifications to support the validation of neutronics codes, nuclear cross-section data, and the validation of reactor designs. Participation in the benchmark process not only benefits those who use these Handbooks within the international community, but provides the individual with opportunities for professional development, networking with an international community of experts, and valuable experience to be used in future employment. Traditionally students have participated in benchmarking activities via internships at national laboratories, universities, or companies involved with the ICSBEP and IRPhEP programs. Additional programs have been developed to facilitate the nuclear education of students while participating in the benchmark projects. These programs include coordination with the Center for Space Nuclear Research (CSNR) Next Degree Program, the Collaboration with the Department of Energy Idaho Operations Office to train nuclear and criticality safety engineers, and student evaluations as the basis for their Master's thesis in nuclear engineering.

J. D. Bess; J. B. Briggs; A. S. Garcia

2011-09-01T23:59:59.000Z

119

Locating hot and cold-legs in a nuclear powered steam generation system  

DOE Patents [OSTI]

A nuclear reactor steam generator includes a reactor vessel for heating water and a steam generator with a pump casing at the lowest point on the steam generator. A cold-leg pipe extends horizontally between the steam generator and the reactor vessel to return water from the steam generator to the reactor vessel. The bottom of the cold-leg pipe is at a first height above the bottom of the reactor vessel. A hot-leg pipe with one end connected to the steam generator and a second end connected to the reactor vessel has a first pipe region extending downwardly from the steam generator to a location between the steam generator and the reactor vessel at which a bottom of the hot-leg pipe is at a second height above the bottom of the reactor vessel. A second region extends from that location in a horizontal direction at the second height to the point at which the hot-leg pipe connects to the reactor vessel. A pump is attached to the casing at a location below the first and second heights and returns water from the steam generator to the reactor vessel over the cold-leg. The first height is greater than the second height and the bottom of the steam generator is at a height above the bottom of the reactor vessel that is greater than the first and second heights. A residual heat recovery pump is below the hot-leg and has an inlet line from the hot-leg that slopes down continuously to the pump inlet.

Ekeroth, Douglas E. (Delmont, PA); Corletti, Michael M. (New Kensington, PA)

1993-01-01T23:59:59.000Z

120

Locating hot and cold-legs in a nuclear powered steam generation system  

DOE Patents [OSTI]

A nuclear reactor steam generator includes a reactor vessel for heating water and a steam generator with a pump casing at the lowest point on the steam generator. A cold-leg pipe extends horizontally between the steam generator and the reactor vessel to return water from the steam generator to the reactor vessel. The bottom of the cold-leg pipe is at a first height above the bottom of the reactor vessel. A hot-leg pipe with one end connected to the steam generator and a second end connected to the reactor vessel has a first pipe region extending downwardly from the steam generator to a location between the steam generator and the reactor vessel at which a bottom of the hot-leg pipe is at a second height above the bottom of the reactor vessel. A second region extends from that location in a horizontal direction at the second height to the point at which the hot-leg pipe connects to the reactor vessel. A pump is attached to the casing at a location below the first and second heights and returns water from the steam generator to the reactor vessel over the cold-leg. The first height is greater than the second height and the bottom of the steam generator is at a height above the bottom of the reactor vessel that is greater than the first and second heights. A residual heat recovery pump is below the hot-leg and has an inlet line from the hot-leg that slopes down continuously to the pump inlet. 2 figures.

Ekeroth, D.E.; Corletti, M.M.

1993-11-16T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation corp" 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
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121

0101,"SPRAGUE ENERGY CORP",1,150,"MOGAS, REFORMULATED",0131,...  

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

101,"SPRAGUE ENERGY CORP",1,150,"MOGAS, REFORMULATED",0131,"PORTSMOUTH, NH","NH",100,260,"CANADA",240,0,0 0101,"SPRAGUE ENERGY CORP",2,462,"DIST, > 0.05% SUL (DOM.)",0401,"BOSTON,...

122

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

SciTech Connect (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

123

Composite Materials under Extreme Radiation and Temperature Environments of the Next Generation Nuclear Reactors  

SciTech Connect (OSTI)

In the nuclear energy renaissance, driven by fission reactor concepts utilizing very high temperatures and fast neutron spectra, materials with enhanced performance that exceeds are expected to play a central role. With the operating temperatures of the Generation III reactors bringing the classical reactor materials close to their performance limits there is an urgent need to develop and qualify new alloys and composites. Efforts have been focused on the intricate relations and the high demands placed on materials at the anticipated extreme states within the next generation fusion and fission reactors which combine high radiation fluxes, elevated temperatures and aggressive environments. While nuclear reactors have been in operation for several decades, the structural materials associated with the next generation options need to endure much higher temperatures (1200 C), higher neutron doses (tens of displacements per atom, dpa), and extremely corrosive environments, which are beyond the experience on materials accumulated to-date. The most important consideration is the performance and reliability of structural materials for both in-core and out-of-core functions. While there exists a great body of nuclear materials research and operating experience/performance from fission reactors where epithermal and thermal neutrons interact with materials and alter their physio-mechanical properties, a process that is well understood by now, there are no operating or even experimental facilities that will facilitate the extreme conditions of flux and temperature anticipated and thus provide insights into the behaviour of these well understood materials. Materials, however, still need to be developed and their interaction and damage potential or lifetime to be quantified for the next generation nuclear energy. Based on material development advances, composites, and in particular ceramic composites, seem to inherently possess properties suitable for key functions within the operating envelope of both fission and fusion reactors. In advanced fission reactors composite materials are being designed in an effort to extend the life and improve the reliability of fuel rod cladding as well as structural materials. Composites are being considered for use as core internals in the next generation of gas-cooled reactors. Further, next-generation plasma-fusion reactors, such as the International Thermonuclear Experimental Reactor (ITER) will rely on the capabilities of advanced composites to safely withstand extremely high neutron fluxes while providing superior thermal shock resistance.

Simos, N.

2011-05-01T23:59:59.000Z

124

High Efficiency Generation of Hydrogen Fuels using Nuclear Power Annual Report August, 2000 - July 2001  

SciTech Connect (OSTI)

OAK B188 High Efficiency Generation of Hydrogen Fuels using Nuclear Power Annual Report August 2000 - July 2001. Currently no large scale, cost-effective, environmentally attractive hydrogen production process is available for commercialization nor has such a process been identified. Hydrogen is a promising energy carrier, which potentially could replace the fossil fuels used in the transportation sector of our economy. Carbon dioxide emissions from fossil fuel combustion are thought to be responsible for global warming. The purpose of this work is to determine the potential for efficient, cost-effective, large-scale production of hydrogen utilizing high temperature heat from an advanced nuclear power station. The benefits of this work will include the generation of a low-polluting transportable energy feedstock in an efficient method that has little or no implication for greenhouse gas emissions from a primary energy source whose availability and sources are domestically controlled. This will help to ensure energy for a future transportation/energy infrastructure that is not influenced/controlled by foreign governments. This report describes work accomplished during the second year (Phase 2) of a three year project whose objective is to ''define an economically feasible concept for production of hydrogen, by nuclear means, using an advanced high temperature nuclear reactor as the energy source.'' The emphasis of the first year (Phase 1) was to evaluate thermochemical processes which offer the potential for efficient, cost-effective, large-scale production of hydrogen from water, in which the primary energy input is high temperature heat from an advanced nuclear reactor and to select one (or, at most, three) for further detailed consideration. Phase 1 met its goals and did select one process, the sulfur-iodine process, for investigation in Phases 2 and 3. The combined goals of Phases 2 and 3 were to select the advanced nuclear reactor best suited to driving the selected thermochemical process and to define the selected reactor and process to the point that capital costs, operating costs and the resultant cost of hydrogen can be estimated. During original contract negotiation, it was necessary to reduce work scope to meet funding limits. As a result, the reactor interface and process will not be iterated to the point that only hydrogen is produced. Rather, hydrogen and electricity will be co-generated and the hydrogen cost will be stated as a function of the electricity sales price.

Brown, L.C.

2002-11-01T23:59:59.000Z

125

CHARACTERISTICS OF NEXT-GENERATION SPENT NUCLEAR FUEL (SNF) TRANSPORT AND STORAGE CASKS  

SciTech Connect (OSTI)

The design of spent nuclear fuel (SNF) casks used in the present SNF disposition systems has evolved from early concepts about the nuclear fuel cycle. The reality today is much different from that envisioned by early nuclear scientists. Most SNF is placed in pool storage, awaiting reprocessing (as in Russia) or disposal at a geologic SNF repository (as in the United States). Very little transport of SNF occurs. This paper examines the requirements for SNF casks from today's perspective and attempts to answer this question: What type of SNF cask would be produced if we were to start over and design SNF casks based on today's requirements? The characteristics for a next-generation SNF cask system are examined and are found to be essentially the same in Russia and the United States. It appears that the new depleted uranium dioxide (DUO2)-steel cermet material will enable these requirements to be met. Depleted uranium (DU) is uranium in which a portion of the 235U isotope has been removed during a uranium enrichment process. The DUO2-steel cermet material is described. The United States and Russia are cooperating toward the development of a next-generation, dual-purpose, storage and transport SNF system.

Haire, M.J.; Forsberg, C.W.; Matveev, V.Z.; Shapovalov, V.I.

2004-10-03T23:59:59.000Z

126

Monroe County Industrial Development Corp., New York  

E-Print Network [OSTI]

Monroe County Industrial Development Corp., New York University Of Rochester; Joint Criteria: Good Operating Performance Related Criteria And Research August 11, 2011 www Of Rochester; Joint Criteria; Private Coll/Univ - General Obligation Credit Profile US$124.00 mil rev bnds

Portman, Douglas

127

Review the CSC AmeriCorps service  

E-Print Network [OSTI]

Corps Coordinator to get your required FBI background check Bring a copy of your driver's license & either valid passport OR birth certificate for citizenship verification to your scheduled FBI scan Print out your FBI of your FBI scan. Now you're ready to start serving! Remember to record your service hours

128

Potential Applications for Nuclear Energy besides Electricity Generation: AREVA Global Perspective of HTR Potential Market  

SciTech Connect (OSTI)

Energy supply is increasingly showing up as a major issue for electricity supply, transportation, settlement, and process heat industrial supply including hydrogen production. Nuclear power is part of the solution. For electricity supply, as exemplified in Finland and France, the EPR brings an immediate answer; HTR could bring another solution in some specific cases. For other supply, mostly heat, the HTR brings a solution inaccessible to conventional nuclear power plants for very high or even high temperature. As fossil fuels costs increase and efforts to avoid generation of Greenhouse gases are implemented, a market for nuclear generated process heat will develop. Following active developments in the 80's, HTR have been put on the back burner up to 5 years ago. Light water reactors are widely dominating the nuclear production field today. However, interest in the HTR technology was renewed in the past few years. Several commercial projects are actively promoted, most of them aiming at electricity production. ANTARES is today AREVA's response to the cogeneration market. It distinguishes itself from other concepts with its indirect cycle design powering a combined cycle power plant. Several reasons support this design choice, one of the most important of which is the design flexibility to adapt readily to combined heat and power applications. From the start, AREVA made the choice of such flexibility with the belief that the HTR market is not so much in competition with LWR in the sole electricity market but in the specific added value market of cogeneration and process heat. In view of the volatility of the costs of fossil fuels, AREVA's choice brings to the large industrial heat applications the fuel cost predictability of nuclear fuel with the efficiency of a high temperature heat source free of greenhouse gases emissions. The ANTARES module produces 600 MWth which can be split into the required process heat, the remaining power drives an adapted prorated electric plant. Depending on the process heat temperature and power needs, up to 80 % of the nuclear heat is converted into useful power. An important feature of the design is the standardization of the heat source, as independent as possible of the process heat application. This should expedite licensing. The essential conditions for success include: 1. Timely adapted licensing process and regulations, codes and standards for such application and design; 2. An industry oriented R and D program to meet the technological challenges making the best use of the international collaboration. Gen IV could be the vector; 3. Identification of an end user (or a consortium of) willing to fund a FOAK. (authors)

Soutworth, Finis; Gauthier, Jean-Claude; Lecomte, Michel [AREVA, 3315 Old Forest Road, Lynchburg, Virginia, 24506 (United States); Carre, Franck [CEA, Saclay (France)

2007-07-01T23:59:59.000Z

129

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

SciTech Connect (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

130

Automatic code generation enables nuclear gradient computations for fully internally contracted multireference theory  

E-Print Network [OSTI]

Analytical nuclear gradients for fully internally contracted complete active space second-order perturbation theory (CASPT2) are reported. This implementation has been realized by an automated code generator that can handle spin-free formulas for the CASPT2 energy and its derivatives with respect to variations of molecular orbitals and reference coefficients. The underlying complete active space self-consistent field and the so-called Z-vector equations are solved using density fitting. With full internal contraction the size of first-order wave functions scales polynomially with the number of active orbitals. The CASPT2 gradient program and the code generator are both publicly available. This work enables the CASPT2 geometry optimization of molecules as complex as those investigated by respective single-point calculations.

MacLeod, Matthew K

2015-01-01T23:59:59.000Z

131

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

DOE Patents [OSTI]

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

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

1996-01-01T23:59:59.000Z

132

Method and apparatus for improving the performance of a nuclear power electrical generation system  

DOE Patents [OSTI]

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

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

1995-01-01T23:59:59.000Z

133

Effect of Hurricane Andrew on the Turkey Point Nuclear Generating Station from August 20--30, 1992. [Final report  

SciTech Connect (OSTI)

On August 24, 1992, Hurricane Andrew, a Category 4 hurricane, struck the Turkey Point Electrical Generating Station with sustained winds of 145 mph (233 km/h). This is the report of the team that the US Nuclear Regulatory Commission (NRC) and the Institute of Nuclear Power Operations (INPO) jointly sponsored (1) to review the damage that the hurricane caused the nuclear units and the utility`s actions to prepare for the storm and recover from it, and (2) to compile lessons that might benefit other nuclear reactor facilities.

Hebdon, F.J. [Institute of Nuclear Power Operations, Atlanta, GA (United States)

1993-03-01T23:59:59.000Z

134

Update report on the performance of 400 megawatt and larger nuclear and coal-fired generating units. Performance through 1977  

SciTech Connect (OSTI)

Forty-seven nuclear generating units and 125 coal-fired generating plants that have had at least one full year of commercial operation are covered in this report. Their performances are evaluated using the capacity factor, availability factor, equivalent availability, and forced outage rate. The data are arranged by state and utility. (DLC)

None

1981-01-01T23:59:59.000Z

135

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

SciTech Connect (OSTI)

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

136

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

SciTech Connect (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

137

Generation IV Nuclear Energy Systems Construction Cost Reductions through the Use of Virtual Environments - Task 5 Report: Generation IV Reactor Virtual Mockup Proof-of-Principle Study  

SciTech Connect (OSTI)

Task 5 report is part of a 3 year DOE NERI-sponsored effort evaluating immersive virtual reality (CAVE) technology for design review, construction planning, and maintenance planning and training for next generation nuclear power plants. Program covers development of full-scale virtual mockups generated from 3D CAD data presented in a CAVE visualization facility. Created a virtual mockup of PBMR reactor cavity and discussed applications of virtual mockup technology to improve Gen IV design review, construction planning, and maintenance planning.

Timothy Shaw; Anthony Baratta; Vaughn Whisker

2005-02-28T23:59:59.000Z

138

Life Cycle Greenhouse Gas Emissions of Nuclear Electricity Generation: Systematic Review and Harmonization  

SciTech Connect (OSTI)

A systematic review and harmonization of life cycle assessment (LCA) literature of nuclear electricity generation technologies was performed to determine causes of and, where possible, reduce variability in estimates of life cycle greenhouse gas (GHG) emissions to clarify the state of knowledge and inform decision making. LCA literature indicates that life cycle GHG emissions from nuclear power are a fraction of traditional fossil sources, but the conditions and assumptions under which nuclear power are deployed can have a significant impact on the magnitude of life cycle GHG emissions relative to renewable technologies. Screening 274 references yielded 27 that reported 99 independent estimates of life cycle GHG emissions from light water reactors (LWRs). The published median, interquartile range (IQR), and range for the pool of LWR life cycle GHG emission estimates were 13, 23, and 220 grams of carbon dioxide equivalent per kilowatt-hour (g CO{sub 2}-eq/kWh), respectively. After harmonizing methods to use consistent gross system boundaries and values for several important system parameters, the same statistics were 12, 17, and 110 g CO{sub 2}-eq/kWh, respectively. Harmonization (especially of performance characteristics) clarifies the estimation of central tendency and variability. To explain the remaining variability, several additional, highly influential consequential factors were examined using other methods. These factors included the primary source energy mix, uranium ore grade, and the selected LCA method. For example, a scenario analysis of future global nuclear development examined the effects of a decreasing global uranium market-average ore grade on life cycle GHG emissions. Depending on conditions, median life cycle GHG emissions could be 9 to 110 g CO{sub 2}-eq/kWh by 2050.

Warner, E. S.; Heath, G. A.

2012-04-01T23:59:59.000Z

139

April 13 2011 Webinar: A Guide to Using AmeriCorps NCCC Teams to Execute Your Mission  

Broader source: Energy.gov [DOE]

April 13 2011 Webinar: A Guide to Using AmeriCorps NCCC Teams to Execute Your Mission; help with program implementating AmeriCorpsĺ National Civilian Community Corps.

140

Ohio Valley Electric Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia: Energy ResourcesLoading map...(UtilityCounty, Michigan: Energy ResourcesCo Jump to: navigation, search Name:Corp

Note: This page contains sample records for the topic "nuclear generation corp" 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

Ormat Funding Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia: Energy ResourcesLoading map...(UtilityCounty,Orleans County, Vermont: Energy Resources JumpOrmat Funding Corp

142

Caribbean Energy Resources Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of InspectorConcentrating SolarElectricEnergyCTBarreis aCallahan DivideCannonCirculatingCorp Jump to:

143

NF Energy Saving Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia: Energy Resources Jump to:46 -Energieprojekte3 ClimateSpurrInformation NAMA-ProgrammeNF Energy Saving Corp

144

GS Yuasa Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia: Energy Resources Jump to: navigation, search Equivalent URIFrontier,Jump to:Wilmette,TransportYuasa Corp Jump

145

Georgia Transmission Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia: Energy Resources Jump to: navigation, searchGeauga County, Ohio:Information4348438┬░InformationCorp Jump

146

EVALUATION METHODOLOGY FOR PROLIFERATION RESISTANCE AND PHYSICAL PROTECTION OF GENERATION IV NUCLEAR ENERGY SYSTEMS: AN OVERVIEW.  

SciTech Connect (OSTI)

This paper provides an overview of the methodology approach developed by the Generation IV International Forum Expert Group on Proliferation Resistance & Physical Protection for evaluation of Proliferation Resistance and Physical Protection robustness of Generation IV nuclear energy systems options. The methodology considers a set of alternative systems and evaluates their resistance or robustness to a collection of potential threats. For the challenges considered, the response of the system to these challenges is assessed and expressed in terms of outcomes. The challenges to the system are given by the threats posed by potential proliferant States and sub-national adversaries on the nuclear systems. The characteristics of the Generation IV systems, both technical and institutional, are used to evaluate their response to the threats and determine their resistance against the proliferation threats and robustness against sabotage and theft threats. System response encompasses three main elements: (1) System Element Identification. The nuclear energy system is decomposed into smaller elements (subsystems) at a level amenable to further analysis. (2) Target Identification and Categorization. A systematic process is used to identify and select representative targets for different categories of pathways, within each system element, that actors (proliferant States or adversaries) might choose to use or attack. (3) Pathway Identification and Refinement. Pathways are defined as potential sequences of events and actions followed by the proliferant State or adversary to achieve its objectives (proliferation, theft or sabotage). For each target, individual pathway segments are developed through a systematic process, analyzed at a high level, and screened where possible. Segments are connected into full pathways and analyzed in detail. The outcomes of the system response are expressed in terms of PR&PP measures. Measures are high-level characteristics of a pathway that include information important to the evaluation methodology users and to the decisions of a proliferant State or adversary. They are first evaluated for segments and then aggregated for complete pathways. Results are aggregated as appropriate to permit pathway comparisons and system assessment. The paper highlights the current achievements in the development of the Proliferation Resistance and Physical Protection Evaluation Methodology. The way forward is also briefly presented together with some conclusions.

BARI, R.; ET AL.

2006-03-01T23:59:59.000Z

147

Evaluation Methodology For Proliferation Resistance And Physical Protection Of Generation IV Nuclear Energy Systems: An Overview  

SciTech Connect (OSTI)

This paper provides an overview of the methodology approach developed by the Generation IV International Forum Expert Group on Proliferation Resistance & Physical Protection for evaluation of Proliferation Resistance and Physical Protection robustness of Generation IV nuclear energy systems options. The methodology considers a set of alternative systems and evaluates their resistance or robustness to a collection of potential threats. For the challenges considered, the response of the system to these challenges is assessed and expressed in terms of outcomes. The challenges to the system are given by the threats posed by potential proliferant States and sub-national adversaries on the nuclear systems. The characteristics of the Generation IV systems, both technical and institutional, are used to evaluate their response to the threats and determine their resistance against the proliferation threats and robustness against sabotage and theft threats. System response encompasses three main elements: 1.System Element Identification. The nuclear energy system is decomposed into smaller elements (subsystems) at a level amenable to further analysis. 2.Target Identification and Categorization. A systematic process is used to identify and select representative targets for different categories of pathways, within each system element, that actors (proliferant States or adversaries) might choose to use or attack. 3.Pathway Identification and Refinement. Pathways are defined as potential sequences of events and actions followed by the proliferant State or adversary to achieve its objectives (proliferation, theft or sabotage). For each target, individual pathway segments are developed through a systematic process, analyzed at a high level, and screened where possible. Segments are connected into full pathways and analyzed in detail. The outcomes of the system response are expressed in terms of PR&PP measures. Measures are high-level characteristics of a pathway that include information important to the evaluation methodology users and to the decisions of a proliferant State or adversary. They are first evaluated for segments and then aggregated for complete pathways. Results are aggregated as appropriate to permit pathway comparisons and system assessment. The paper highlights the current achievements in the development of the Proliferation Resistance and Physical Protection Evaluation Methodology. The way forward is also briefly presented together with some conclusions.

T. Bjornard; R. Bari; R. Nishimura; P. Peterson; J. Roglans; D. Bley; J. Cazalet; G.G.M. Cojazzi; P. Delaune; M. Golay; G. Rendad; G. Rochau; M. Senzaki; I. Therios; M. Zentner

2006-05-01T23:59:59.000Z

148

Can Next-Generation Reactors Power a Safe Nuclear Futur By Clay Dillow Posted 03.17.2011 at 12:18 pm  

E-Print Network [OSTI]

Can Next-Generation Reactors Power a Safe Nuclear Futur By Clay Dillow Posted 03.17.2011 at 12 of nuclear reactors are designed to prevent exactly what we old Fukushima Daiichi plant. Which is good the world rush to reconsider their nuclear plans, nuclear experts look toward a future of smaller, safer

Danon, Yaron

149

Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project - Final Technical Report  

SciTech Connect (OSTI)

This report is the Final Technical Report for the Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project conducted by a team led by General Atomics under DOE Award DE-NE0000245. The primary overall objective of the project was to develop and document a conceptual design for the Steam Cycle Modular Helium Reactor (SC-MHR), which is the reactor concept proposed by General Atomics for the NGNP Demonstration Plant. The report summarizes the project activities over the entire funding period, compares the accomplishments with the goals and objectives of the project, and discusses the benefits of the work. The report provides complete listings of the products developed under the award and the key documents delivered to the DOE.

Saurwein, John

2011-07-15T23:59:59.000Z

150

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

SciTech Connect (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

151

New generation nuclear fuel structures: dense particles in selectively soluble matrix  

SciTech Connect (OSTI)

We have developed a technology for dispersing sub-millimeter sized fuel particles within a bulk matrix that can be selectively dissolved. This may enable the generation of advanced nuclear fuels with easy separation of actinides and fission products. The large kinetic energy of the fission products results in most of them escaping from the sub-millimeter sized fuel particles and depositing in the matrix during burning of the fuel in the reactor. After the fuel is used and allowed to cool for a period of time, the matrix can be dissolved and the fission products removed for disposal while the fuel particles are collected by filtration for recycle. The success of such an approach would meet a major goal of the GNEP program to provide advanced recycle technology for nuclear energy production. The benefits of such an approach include (1) greatly reduced cost of the actinide/fission product separation process, (2) ease of recycle of the fuel particles, and (3) a radiation barrier to prevent theft or diversion of the recycled fuel particles during the time they are re-fabricated into new fuel. In this study we describe a method to make surrogate nuclear fuels of micrometer scale W (shell)/Mo (core) or HfO2 particles embedded in an MgO matrix that allows easy separation of the fission products and their embedded particles. In brief, the method consists of physically mixing W-Mo or hafnia particles with an MgO precursor. Heating the mixture, in air or argon, without agitation, to a temperature is required for complete decomposition of the precursor. The resulting material was examined using chemical analysis, scanning electron microscopy, X-ray diffraction and micro X-ray computed tomography and found to consist of evenly dispersed particles in an MgO + matrix. We believe this methodology can be extended to actinides and other matrix materials.

Sickafus, Kurt E [Los Alamos National Laboratory; Devlin, David J [Los Alamos National Laboratory; Jarvinen, Gordon D [Los Alamos National Laboratory; Patterson, Brian M [Los Alamos National Laboratory; Pattillo, Steve G [Los Alamos National Laboratory; Valdez, James [Los Alamos National Laboratory; Phillips, Jonathan [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

152

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

SciTech Connect (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

153

US Synthetic Corp (TRL 4 Component) - The Development of Open...  

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

Polycrystalline Diamond Thrust Bearings for use in Marine Hydrokinetic (MHK) Energy Machines US Synthetic Corp (TRL 4 Component) - The Development of Open, Water Lubricated...

154

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

E-Print Network [OSTI]

IMPACTS OF FOSSIL-FUEL NUCLEAR, GEOTHERMAL, AND ELECTRIC GENERATION IN CALIFORNIA Energy and Environment

Nero, A.V.

2010-01-01T23:59:59.000Z

155

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]

IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA Energy and Environment

Nero, A.V.

2010-01-01T23:59:59.000Z

156

A REVIEW OF AIR QUALITY MODELING TECHNIQUES. VOLUME 8 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA Energy and Environment

Rosen, L.C.

2010-01-01T23:59:59.000Z

157

Next Generation Reactors  

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

Nuclear Advances We are coordinating the Generation IV Nuclear Systems Initiative - an international effort to develop the next generation of nuclear power reactors. Skip...

158

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

SciTech Connect (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 ľ i.e., within the next 10-15 years.

L.E. Demick

2010-09-01T23:59:59.000Z

159

Targeting Net Zero Energy at Marine Corps Base Kaneohe Bay, Hawaii...  

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

Targeting Net Zero Energy at Marine Corps Base Kaneohe Bay, Hawaii: Assessment and Recommendations Targeting Net Zero Energy at Marine Corps Base Kaneohe Bay, Hawaii: Assessment...

160

New Energy Capital Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia: Energy Resources Jump to:46 -Energieprojekte3InformationofServicesNeuCo620572┬░,York: EnergyCapital Corp

Note: This page contains sample records for the topic "nuclear generation corp" from the National Library of EnergyBeta (NLEBeta).
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they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
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161

Colquitt Electric Membership Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublic Utilities Address: 160Benin:EnergyWisconsin: Energy,(EC-LEDS) |Colquitt Electric Membership Corp Jump to:

162

Connected Energy Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublic Utilities Address: 160Benin:EnergyWisconsin:2003) | Open EnergyConductive Plays -Connected Energy Corp Jump

163

Terranova Energy Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of Inspector GeneralDepartmentAUDIT REPORTOpenWende NewSowitec do Brasil EnergiaSur deT-OTerranova Energy Corp

164

Lab-Corps Program | Argonne National Laboratory  

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

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

165

Arkansas Electric Coop Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublic Utilities Address: 160 East 300AlgoilEnergyElectric Coop Corp Place: Arkansas References: EIA Form EIA-861

166

Beacon Power Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublic Utilities Address: 160 EastMaine:Barbers Point Housing,Illinois:CountyNewWest, New Jersey:Beacon Power Corp

167

Blue Sphere Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of InspectorConcentrating SolarElectricEnergyCTBarre BiomassTHIS PAGE ISJumpSphere Corp Jump to: navigation,

168

Peak Sun Silicon Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 No revision hasInformation Earth'sOklahoma/GeothermalOrange County isParadise, Nevada:PavilionSun Silicon Corp

169

Pine Ridge Job Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 No revision hasInformation Earth'sOklahoma/GeothermalOrangePeru:Job Corp Jump to: navigation, search Name Pine

170

Polymer Technology Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 No revision hasInformation Earth'sOklahoma/GeothermalOrangePeru:Job Corp Jump Partner Poland

171

Magnet Motor Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia: Energy Resources Jump to:46 - 429Lacey,(MonasterLowell Point,ECO Auger11.Spain: EnergyMagnet Motor Corp Jump to:

172

West Central School Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublic Utilities Address: 160 East 300 South Place: SaltTroyer & AssociatesWest Central School Corp Facility

173

Windblade Power Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia:FAQ < RAPID Jump to:SeadovCooperative JumpWilliamson County,Bay, OR) JumpPhoto fromWindblade Power Corp Jump

174

Yu Energy Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia:FAQ < RAPID Jump to:SeadovCooperative JumpWilliamsonWoodsonCounty is aYoakumYu Energy Corp Region: United

175

Green Energy Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia: Energy Resources Jump to: navigation,Ohio: EnergyGrasslands RenewableGreatwood, Texas:Open45. ItEmpowermentCorp

176

PacifiCorp (Idaho) | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia: Energy ResourcesLoading map...(UtilityCounty,Orleans County,PPP Equipment CorporationPV World CoPacifiCorp

177

Jackson Energy Coop Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia: Energy Resources Jump to:46 - 429 Throttled (botOpen Energy2005) |JMalucelliIowa Andrew,Jackson County is35.Corp

178

Amereco Biofuels Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublic Utilities Address: 160 East 300Algoil JumpAltergy Systems Place:AlwitraAmberley,Amereco Biofuels Corp Jump

179

First Philec Solar Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublicIDAPowerPlantSitingConstruction.pdfNotify98.pdf Jump to:Siting.pdf JumpFirelands ElectricPhilec Solar Corp

180

State Grid Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia:FAQ < RAPID Jump to:Seadov Pty Ltd JumpGTZHolland,0162112┬░,St.Stanly County,Manufacturing IncandCorp Jump to:

Note: This page contains sample records for the topic "nuclear generation corp" 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

Farmers Electric Coop Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublic Utilities Address:011-DNA Jump37.California: Energy Resources Jump4748456┬░,FallonBranch, Texas:Coop Corp

182

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

SciTech Connect (OSTI)

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

183

PHYSICAL REVIEW A 90, 063412 (2014) Effect of nuclear vibration on high-order-harmonic generation of aligned H2  

E-Print Network [OSTI]

PHYSICAL REVIEW A 90, 063412 (2014) Effect of nuclear vibration on high-order-harmonic generation of aligned H2 + molecules Dmitry A. Telnov,1,* John Heslar,2, and Shih-I Chu2,3, 1 Department of Physics, St. Petersburg State University, St. Petersburg 198504, Russia 2 Department of Physics, Center for Quantum

Chu, Shih-I

184

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

SciTech Connect (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, 2╝Cr-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

185

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

SciTech Connect (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

186

Miscellaneous Paper A-95-1 US Army Corps  

E-Print Network [OSTI]

Induced Stress in Submerse ┬ĚAquatic Plants: A Review by Susan L. Sprecher, Michael D. Netherland in Submersed Aquatic Plants: A Review by Susan L. Sprecher, Michael D. Netherland U.S. Army Corps of Engineers. Netherland; pre pared for U.S. Army Corps of Engineers. 41 p. : ill. ; 28 em. - (Miscellaneous paper; A-95

US Army Corps of Engineers

187

Reference: RGL 81-02 Subject: NEPA-CORPS EIS  

E-Print Network [OSTI]

Reference: RGL 81-02 Subject: NEPA-CORPS EIS Title: REVIEW OF ANOTHER AGENCY'S EIS Issued: 03/17/81 Expires: 12/31/83 Originator: DAEN-CWO-N Description: EIS WILL ONLY BE PREPARED WHEN CORPS PERMIT ACTION sentence of paragraph 23 of Appendix B to 33 CFR 230, a draft and final supplement to another agency's EIS

US Army Corps of Engineers

188

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

SciTech Connect (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 ôhighly rankedö 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

189

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

SciTech Connect (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

190

Property exempt from taxation: nuclear generation facility property: K.S.A. 79-230 (Kansas)  

Broader source: Energy.gov [DOE]

This legislation would exempt from state property taxes any property purchased, constructed or installed to expand capacity at an existing nuclear plant or to build a new nuclear plant. A...

191

Observations on A Technology Roadmap for Generation IV Nuclear Energy Systems: Technical Roadmap Report  

Broader source: Energy.gov [DOE]

The development of advanced nuclear energy systems in the U.S. will depend greatly on the continued success of currently operating light water nuclear power plants and the ordering of new...

193

The Long-Life Core Encapsulated Nuclear Heat Source (ENHS) Generation IV Reactor  

SciTech Connect (OSTI)

The long-life core for the Encapsulated Nuclear Heat Source (ENHS) reactor has been redesigned so as to provide for fuel rod clad integrity up to the discharge burnup design goal. It was found feasible to design a nearly zero burnup reactivity swing long-life core that will maintain the fuel rod integrity up to the peak discharge burnup while enabling to handle the rated power using natural circulation. The core life is limited by radiation damage to its structural material. The core power shape is exceptionally constant throughout the core life. The new reference core design can deliver 125 MW{sub th} while having very generous margins for maximum acceptable temperatures or temperature differences. Using a cover-gas lift-pump it may be possible to design an ENHS module to deliver {approx}50% more power than the set goal. Briefly reviewed are unique features of the ENHS reactor along with the potential of this reactor to meet the goals set for Generation IV reactors. (authors)

Greenspan, E.; Barak, A.; Saphier, D. [Department of Nuclear Engineering, University of California, Berkeley, CA 94720 (United States); Buongiorno, J. [Idaho National Engineering and Environmental Laboratory, P.O. Box 1625, Idaho Falls, ID 83415 (United States); Brown, N.W.; Hossain, Q. [Lawrence Livermore National Laboratory, 7000 East Avenue, Livermore, CA 94550 (United States); Carelli, M.D.; Conway, L.; Dzodzo, M. [Westinghouse Electric Co., Sci. and Tech., 1344 Beulah Rd., Pittsburgh, PA 15235 (United States); Feldman, E.; Sienicki, J.J.; Sofu, T.; Wade, D.C. [Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439 (United States); Hong, S.G.; Kim, Y.I. [Korea Atomic Energy Research Institute, Yusong, Taejon 305-600, Rep. of Korea (Korea, Republic of)

2002-07-01T23:59:59.000Z

194

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

SciTech Connect (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. Todayĺs 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

195

FirstEnergy Generation Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of InspectorConcentrating Solar Power Basics (TheEtelligence (Smart

196

Monitoring attosecond dynamics of coherent electron-nuclear wave packets by molecular high-order-harmonic generation  

SciTech Connect (OSTI)

A pump-probe scheme for preparing and monitoring electron-nuclear motion in a dissociative coherent electron-nuclear wave packet is explored from numerical solutions of a non-Born-Oppenheimer time-dependent Schroedinger equation. A mid-ir intense few-cycle probe pulse is used to generate molecular high-order-harmonic generation (MHOHG) from a coherent superposition of two or more dissociative coherent electronic-nuclear wave packets, prepared by a femtosecond uv pump pulse. Varying the time delay between the intense ir probe pulse and the uv pump pulse by a few hundreds of attoseconds, the MHOHG signal intensity is shown to vary by orders of magnitude, thus showing the high sensitivity to electron-nuclear dynamics in coherent electron-nuclear wave packets. We relate this high sensitivity of MHOHG spectra to opposing electron velocities (fluxes) in the electron wave packets of the recombining (recolliding) ionized electron and of the bound electron in the initial coherent superposition of two electronic states.

Bredtmann, Timm [Laboratoire de Chimie Theorique, Faculte des Sciences, Universite de Sherbrooke, Sherbrooke, Quebec, J1K 2R1 (Canada); Institut fuer Chemie und Biochemie, Freie Universitaet Berlin, Takustrasse 3, D-14195 Berlin (Germany); Chelkowski, Szczepan; Bandrauk, Andre D. [Laboratoire de Chimie Theorique, Faculte des Sciences, Universite de Sherbrooke, Sherbrooke, Quebec, J1K 2R1 (Canada)

2011-08-15T23:59:59.000Z

197

STARLIB: A NEXT-GENERATION REACTION-RATE LIBRARY FOR NUCLEAR ASTROPHYSICS  

SciTech Connect (OSTI)

STARLIB is a next-generation, all-purpose nuclear reaction-rate library. For the first time, this library provides the rate probability density at all temperature grid points for convenient implementation in models of stellar phenomena. The recommended rate and its associated uncertainties are also included. Currently, uncertainties are absent from all other rate libraries, and, although estimates have been attempted in previous evaluations and compilations, these are generally not based on rigorous statistical definitions. A common standard for deriving uncertainties is clearly warranted. STARLIB represents a first step in addressing this deficiency by providing a tabular, up-to-date database that supplies not only the rate and its uncertainty but also its distribution. Because a majority of rates are lognormally distributed, this allows the construction of rate probability densities from the columns of STARLIB. This structure is based on a recently suggested Monte Carlo method to calculate reaction rates, where uncertainties are rigorously defined. In STARLIB, experimental rates are supplemented with: (1) theoretical TALYS rates for reactions for which no experimental input is available, and (2) laboratory and theoretical weak rates. STARLIB includes all types of reactions of astrophysical interest to Z = 83, such as (p, {gamma}), (p, {alpha}), ({alpha}, n), and corresponding reverse rates. Strong rates account for thermal target excitations. Here, we summarize our Monte Carlo formalism, introduce the library, compare methods of correcting rates for stellar environments, and discuss how to implement our library in Monte Carlo nucleosynthesis studies. We also present a method for accessing STARLIB on the Internet and outline updated Monte Carlo-based rates.

Sallaska, A. L. [National Institute of Standards and Technology, Gaithersburg, MD 20899-8462 (United States); Iliadis, C.; Champange, A. E. [University of North Carolina at Chapel Hill, Chapel Hill, NC 27599-3255 (United States); Goriely, S. [Institut d'Astronomie et d'Astrophysique, Universite Libre de Bruxelles, C.P. 226, B-1050 Brussels (Belgium); Starrfield, S.; Timmes, F. X., E-mail: anne.sallaska@nist.gov [Arizona State University, Tempe, AZ 85287-1504 (United States)

2013-07-15T23:59:59.000Z

198

Design of Radiation-Tolerant Structural Alloys for Generation IV Nuclear Energy Systems  

SciTech Connect (OSTI)

This project will use proton irradiation to further understand the microstructural stability of ceramics being considered as matrix material for advanced nuclear fuels.

Todd R. Allen

2009-06-30T23:59:59.000Z

199

DOE - Office of Legacy Management -- Nuclear Development Corp of America -  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou are herePA 3003A01 CarolinaNorton Co -NY

200

DOE - Office of Legacy Management -- Sylvania Corning Nuclear Corp Inc  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou areDowntown Site - MO 02Sutton Steele and

Note: This page contains sample records for the topic "nuclear generation corp" 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

China National Nuclear Corp CNNC | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of Inspector GeneralDepartmentAUDIT REPORTOpenWendeGuoCatalystPathways Calculator Jump to: navigation,CNNC Jump

202

Characterization of a Stochastic Procedure for the Generation and Transport of Fission Fragments within Nuclear Fuels  

E-Print Network [OSTI]

With the ever-increasing demands of the nuclear power community to extend fuel cycles and overall core-lifetimes in a safe and economic manner, it is becoming more necessary to extend the working knowledge of nuclear fuel performance. From...

Hackemack, Michael Wayne

2013-04-15T23:59:59.000Z

203

Acculturation in International Development: The Peace Corps in Costa Rica  

E-Print Network [OSTI]

In its thirty years of service, the Peace Corps has acquired a well founded international reputation for successful grassroots development assistance through the unpretentious lifestyle of American individuals living and ...

Tsatsoulis-Bonnekessen, Barbara

1994-04-08T23:59:59.000Z

204

EPRI PEAC Corp.: Certification Model Program and Interconnection Agreement Tools  

SciTech Connect (OSTI)

Summarizes the work of EPRI PEAC Corp., under contract to DOE's Distribution and Interconnection R&D, to develop a certification model program and interconnection agreement tools to support the interconnection of distributed energy resources.

Not Available

2003-10-01T23:59:59.000Z

205

Diesel fuel to dc power: Navy & Marine Corps Applications  

SciTech Connect (OSTI)

During the past year Analytic Power has tested fuel cell stacks and diesel fuel processors for US Navy and Marine Corps applications. The units are 10 kW demonstration power plants. The USN power plant was built to demonstrate the feasibility of diesel fueled PEM fuel cell power plants for 250 kW and 2.5 MW shipboard power systems. We designed and tested a ten cell, 1 kW USMC substack and fuel processor. The complete 10 kW prototype power plant, which has application to both power and hydrogen generation, is now under construction. The USN and USMC fuel cell stacks have been tested on both actual and simulated reformate. Analytic Power has accumulated operating experience with autothermal reforming based fuel processors operating on sulfur bearing diesel fuel, jet fuel, propane and natural gas. We have also completed the design and fabrication of an advanced regenerative ATR for the USMC. One of the significant problems with small fuel processors is heat loss which limits its ability to operate with the high steam to carbon ratios required for coke free high efficiency operation. The new USMC unit specifically addresses these heat transfer issues. The advances in the mill programs have been incorporated into Analytic Power`s commercial units which are now under test.

Bloomfield, D.P. [Analytic Power Corp., Boston, MA (United States)

1996-12-31T23:59:59.000Z

206

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]

On other hand, accidents at nuclear facilities could nott ed expos ur e from a nuclear accident which would warrantresulting from accidents at nuclear facilities. Average

Nero, A.V.

2010-01-01T23:59:59.000Z

207

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]

average value for nuclear plants) aFinal Envir. Statement (Statement, Koshkonong Nuclear Plant, August 1976. U. S.rem; operation of the nuclear plants themselves only *Other

Nero, A.V.

2010-01-01T23:59:59.000Z

208

DOE - Office of Legacy Management -- Sylvania Corning Nuclear...  

Office of Legacy Management (LM)

to SYLVANIA CORNING NUCLEAR CORP., INC., SYLVANIA LABORATORIES NY.07-1 - Letter, Smith to Norris, Contract at (30-1)-1293- U Metal Requirements, March 5, 1953 NY.07-2 -...

209

A comparison of delayed radiobiological effects of depleted-uranium munitions versus fourth-generation nuclear weapons  

E-Print Network [OSTI]

It is shown that the radiological burden due to the battle-field use of circa 400 tons of depleted-uranium munitions in Iraq (and of about 40 tons in Yugoslavia) is comparable to that arising from the hypothetical battle-field use of more than 600 kt (respectively 60 kt) of high-explosive equivalent pure-fusion fourth-generation nuclear weapons. Despite the limited knowledge openly available on existing and future nuclear weapons, there is sufficient published information on their physical principles and radiological effects to make such a comparison. In fact, it is shown that this comparison can be made with very simple and convincing arguments so that the main technical conclusions of the paper are undisputable -- although it would be worthwhile to supplement the hand calculations presented in the paper by more detailed computer simulations in order to consolidate the conclusions and refute any possible objections.

Gsponer, A; Vitale, B; Gsponer, Andre; Hurni, Jean-Pierre; Vitale, Bruno

2002-01-01T23:59:59.000Z

210

Electronic constant current and current pulse signal generator for nuclear instrumentation testing  

DOE Patents [OSTI]

Circuitry is described for testing the ability of an intermediate range nuclear instrument to detect and measure a constant current and a periodic current pulse. The invention simulates the resistance and capacitance of the signal connection of a nuclear instrument ion chamber detector and interconnecting cable. An LED flasher/oscillator illuminates an LED at a periodic rate established by a timing capacitor and circuitry internal to the flasher/oscillator. When the LED is on, a periodic current pulse is applied to the instrument. When the LED is off, a constant current is applied. An inductor opposes battery current flow when the LED is on. 1 figures.

Brown, R.A.

1994-04-19T23:59:59.000Z

211

Electronic constant current and current pulse signal generator for nuclear instrumentation testing  

DOE Patents [OSTI]

Circuitry for testing the ability of an intermediate range nuclear instrut to detect and measure a constant current and a periodic current pulse. The invention simulates the resistance and capacitance of the signal connection of a nuclear instrument ion chamber detector and interconnecting cable. An LED flasher/oscillator illuminates an LED at a periodic rate established by a timing capacitor and circuitry internal to the flasher/oscillator. When the LED is on, a periodic current pulse is applied to the instrument. When the LED is off, a constant current is applied. An inductor opposes battery current flow when the LED is on.

Brown, Roger A. (Amsterdam, NY)

1994-01-01T23:59:59.000Z

212

Generation IV Nuclear Energy Systems Construction Cost Reductions through the Use of Virtual Environments - Task 4 Report: Virtual Mockup Maintenance Task Evaluation  

SciTech Connect (OSTI)

Task 4 report of 3 year DOE NERI-sponsored effort evaluating immersive virtual reality (CAVE) technology for design review, construction planning, and maintenance planning and training for next generation nuclear power plants. Program covers development of full-scale virtual mockups generated from 3D CAD data presented in a CAVE visualization facility. This report focuses on using Full-scale virtual mockups for nuclear power plant training applications.

Timothy Shaw; Anthony Baratta; Vaughn Whisker

2005-02-28T23:59:59.000Z

213

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

SciTech Connect (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

214

New approaches to interfacing thermoelectric generators to the load bus in a nuclear space vehicle  

E-Print Network [OSTI]

reactor and the thermoelectrics. This type oi' system wastes the excess power generated as heat. Heat dissipation in space is very difficult. In the reference design TCAs (thermoelectric converter assembly) and shunt regulators connect directly... ballast load. The variable ballast compensa, tes 1' or the variation of the load. This type of control philosophy is very inefficient. Of the power generated, some is wasted in the variable ballast by heat dissipation. New architectures of controlling...

Brohlin, Paul LeRoy

1988-01-01T23:59:59.000Z

215

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]

in U. S. Conunercial Nuclear Power Plants", Report WASH-Related Standards for Nuclear Power Plants," by A.V. NeroResponse Planning for Nuclear Power Plants in California,"

Nero, A.V.

2010-01-01T23:59:59.000Z

216

US Army Corps of Engineers BUILDING STRONG  

E-Print Network [OSTI]

Nuclear Regulatory Commission US Environmental Protection Agency US Department of Energy Babcock Wilcox Team #12;BUILDING STRONG® Project Objectives Protect human health and the environment Complete cleanup in a safe, effective, and efficient manner Comply with the Comprehensive Environmental Response

US Army Corps of Engineers

217

Risk perception & strategic decision making :general insights, a framework, and specific application to electricity generation using nuclear energy.  

SciTech Connect (OSTI)

The objective of this report is to promote increased understanding of decision making processes and hopefully to enable improved decision making regarding high-consequence, highly sophisticated technological systems. This report brings together insights regarding risk perception and decision making across domains ranging from nuclear power technology safety, cognitive psychology, economics, science education, public policy, and neural science (to name a few). It forms them into a unique, coherent, concise framework, and list of strategies to aid in decision making. It is suggested that all decision makers, whether ordinary citizens, academics, or political leaders, ought to cultivate their abilities to separate the wheat from the chaff in these types of decision making instances. The wheat includes proper data sources and helpful human decision making heuristics; these should be sought. The chaff includes ''unhelpful biases'' that hinder proper interpretation of available data and lead people unwittingly toward inappropriate decision making ''strategies''; obviously, these should be avoided. It is further proposed that successfully accomplishing the wheat vs. chaff separation is very difficult, yet tenable. This report hopes to expose and facilitate navigation away from decision-making traps which often ensnare the unwary. Furthermore, it is emphasized that one's personal decision making biases can be examined, and tools can be provided allowing better means to generate, evaluate, and select among decision options. Many examples in this report are tailored to the energy domain (esp. nuclear power for electricity generation). The decision making framework and approach presented here are applicable to any high-consequence, highly sophisticated technological system.

Brewer, Jeffrey D.

2005-11-01T23:59:59.000Z

218

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

SciTech Connect (OSTI)

The United States Department of Energyĺs 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 Energyĺs lead laboratory for nuclear energy development. The ATR is one of the worldĺs 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

219

Los Alamos National Laboratory new generation standard nuclear material storage container - the SAVY4000 design  

SciTech Connect (OSTI)

Incidents involving release of nuclear materials stored in containers of convenience such as food pack cans, slip lid taped cans, paint cans, etc. has resulted in defense board concerns over the lack of prescriptive performance requirements for interim storage of nuclear materials. Los Alamos National Laboratory (LANL) has shared in these incidents and in response proactively moved into developing a performance based standard involving storage of nuclear material (RD003). This RD003 requirements document has sense been updated to reflect requirements as identified with recently issued DOE M 441.1-1 'Nuclear Material Packaging Manual'. The new packaging manual was issued at the encouragement of the Defense Nuclear Facilities Safety Board with a clear directive for protecting the worker from exposure due to loss of containment of stored materials. The Manual specifies a detailed and all inclusive approach to achieve a high level of protection; from package design & performance requirements, design life determinations of limited life components, authorized contents evaluations, and surveillance/maintenance to ensure in use package integrity over time. Materials in scope involve those stored outside an approved engineered-contamination barrier that would result in a worker exposure of in excess of 5 rem Committed Effective Does Equivalent (CEDE). Key aspects of meeting the challenge as developed around the SAVY-3000 vented storage container design will be discussed. Design performance and acceptance criteria against the manual, bounding conditions as established that the user must ensure are met to authorize contents in the package (based upon the activity of heat-source plutonium (90% Pu-238) oxide, which bounds the requirements for weapons-grade plutonium oxide), interface as a safety class system within the facility under the LANL plutonium facility DSA, design life determinations for limited life components, and a sense of design specific surveillance program implementation as LANL moves forward into production and use of the SAVY-3000 will all be addressed. The SAVY-3000 is intended as a work horse package for the DOE complex as a vented storage container primarily for plutonium in solid form.

Stone, Timothy Amos [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

220

"What Are Marines For?" The United States Marine Corps in the Civil War Era  

E-Print Network [OSTI]

This dissertation provides analysis on several areas of study related to the history of the United States Marine Corps in the Civil War Era. One element scrutinizes the efforts of Commandant Archibald Henderson to transform the Corps into a more...

Krivdo, Michael Edward

2012-07-16T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation corp" 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

New technology for purging the steam generators of nuclear power plants  

SciTech Connect (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

222

Evaluation Metrics for Intermediate Heat Exchangers for Next Generation Nuclear Reactors  

SciTech Connect (OSTI)

The Department of Energy (DOE) is working with industry to develop a next generation, high-temperature gas-cooled reactor (HTGR) as a part of the effort to supply the United States with abundant, clean, and secure energy as initiated by the Energy Policy Act of 2005 (EPAct; Public Law 109-58,2005). The NGNP Project, led by the Idaho National Laboratory (INL), will demonstrate the ability of the HTGR to generate hydrogen, electricity, and/or high-quality process heat for a wide range of industrial applications.

Piyush Sabharwall; Eung Soo Kim; Nolan Anderson

2011-06-01T23:59:59.000Z

223

The Transmutation of Nuclear Waste in the Two-Zone Subcritical System Driven by High- Intensity Neutron Generator - 12098  

SciTech Connect (OSTI)

The main problems of transmutation of high-level radioactive waste (minor actinides and long-lived fission products) are considered in our work. The range of radioactive waste of nuclear power is analyzed. The conditions under which the transmutation of radioactive waste will be most effective are analyzed too. The modeling results of a transmutation of the main radioactive isotopes are presented and discussed. The transmutation of minor actinides and long-lived fission products are modeled in our work (minor actinides - Np-237, Am-241, Am-242, Am-243, Cm-244, Cm-245; long-lived fission products - I-129, Tc-99). The two-zone subcritical system is calculated with help of different neutron-physical codes (MCNP, Scale, Montebarn, Origen). The ENDF/B-VI nuclear data library used in above calculations. Thus, radioactive wastes can be divided into two main groups that need to be transmuted. The minor actinides form the first group and the long-lived fission products form the second one. For the purpose of effective transmutation these isotopes must be extracted from the spent nuclear fuel with the help of either PUREX technology or pyrometallurgical technology. The two-zone reactor system with fast and thermal regions is more effective for nuclear waste transmutation than the one-zone reactor. Modeling results show that nearly all radioactive wastes can be transmuted in the two-zone subcritical system driven by a high-intensity neutron generator with the external neutron source strength of 1.10{sup 13} n/sec. Obviously, transmutation rate will increase with a rise of the external neutron source strength. From the results above we can also see that the initial loading of radioactive isotopes into the reactor system should exceed by mass those isotopes that are finally produced. (authors)

Babenko, V.O. [Bogolyubov Institute for Theoretical Physics, Metrolohichna str. 14-b, Kiev, 03680 (Ukraine); Gulik, V.I.; Pavlovych, V.M. [Institute for Nuclear Research, pr. Nauky 47, Kyiv, 03680 (Ukraine)

2012-07-01T23:59:59.000Z

224

U.S. Army Corps of Engineers | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 No revisionEnvReviewNonInvasiveExplorationUT-gTaguspark JumpDetective:ToyoTurkey:S Army Corps of EngineersCorps of

225

Model of sludge behavior in nuclear plant steam generators. Final report  

SciTech Connect (OSTI)

The accumulation of large amounts of sludge in pressurized water reactor steam generators is thought to be a cause of accelerated corrosion by trace impurities which concentrate in such deposits. Based on fundamental principles, this study develops a mathematical model for predicting the behavior (e.g., deposition and reentrainment) of sludge in steam generators. The calculated sludge behavior shows good agreement with the limited amount of experimental data available. The results suggest that the continued accumulation of sludge on the tubesheet might be preventable, and that if it could be, the incoming sludge would be removed by blowdown. An analysis of the uncertainties in the model led to suggested priorities for further analytical and experimental work to gain a better understanding of sludge behavior. 29 refs., 12 figs., 15 tabs.

Beal, S.K.; Chen, J.H.

1986-06-01T23:59:59.000Z

226

corp-toc | netl.doe.gov  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched5 Industrial Carbon Capture and Storageconvert program | National NuclearInstitutional

227

Nuclear Power Overview  

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

San Onofre Nuclear Generating Station San Onofre Nuclear Generating Station Bob Ashe-Everest Southern California Edison 10 Incoming New Fuel Inspecting New Fuel SONGS Unit 1 Fuel...

228

Monitoring equipment environment during nuclear plant operation at Salem and Hope Creek generating stations  

SciTech Connect (OSTI)

Monitoring of environmental parameters has become a significant issue for operating nuclear power plants. While the long-term benefits of plant life extension programs are being pursued with comprehensive environmental monitoring programs, the potential effect of local hot spots at various plant locations needs to be evaluated for its effect on equipment degradation and shortening of equipment qualified life. A significant benefit can be experienced from temperature monitoring when a margin exists between the design versus actual operating temperature. This margin can be translated into longer equipment qualified life and significant reduction in maintenance activities. At PSE and G, the immediate need for monitoring environmental parameters is being accomplished via the use of a Logic Beach Bitlogger. The Bitlogger is a portable data loggings system consisting of a system base, input modules and a communication software package. Thermocouples are installed on selected electrical equipment and cables are run from the thermocouples to the input module of the Bitlogger. Temperature readings are taken at selected intervals, stored in memory, and downloaded periodically to a PC software program, i.e., Lotus. The data is formatted into tabular or graphical documents. Because of their versatility, Bitloggers are being used differently at the authors Nuclear facility. At the Salem Station (2 Units-4 loop Westinghouse PWR), a battery powered, fully portable, calibrated Bitlogger is located in an accessible area inside Containment where it monitors the temperature of various electrical equipment within the Pressurizer Enclosure. It is planned that close monitoring of the local hot spot temperatures in this area will allow them to adjust and reconcile the environmental qualification of the equipment.

Blum, A.; Smith, R.J. [Public Service Electric and Gas Co., Hancocks Bridge, NJ (United States)

1991-06-01T23:59:59.000Z

229

Wave Energy Test Site (WETS) Marine Corps Base Hawaii (MCBH)  

E-Print Network [OSTI]

Wave Energy Test Site (WETS) Marine Corps Base Hawaii (MCBH) Alexandra DeVisser, NAVFAC-EXWC Brian June 10, 2013 #12;Wave Energy Test Site (WETS) Objective: Provide location for year-long in WETS? Year-round data collection in a wide range of wave conditions is possible. #12;4 Daily Wave Power

230

Bryan H. Wood Assistant Deputy Commandant of the Marine Corps  

E-Print Network [OSTI]

and stations throughout the world and for the operating forces across the U.S. Marine Corps. Mr. Wood advisor to the Commander, Combined Joint Task Force- Horn of Africa (CJTF-HOA) in Djibouti, Africa. Mr as the Environmental Law Section Head and Senior Associate Counsel (Environment/ Safety), Naval Sea Systems Command

231

US ARMY CORPS OF ENGINEERS PLANNING AND RESPONSE TEAM  

E-Print Network [OSTI]

US ARMY CORPS OF ENGINEERS PLANNING AND RESPONSE TEAM INFRASTRUCTURE ASSESSMENT MISSION GUIDE March, hazardous materials, water and wastewater infrastructure (e.g. treatment facilities, lift stations, other Federal agencies (e.g. Bureau of Reclamation). The IA PRT program also supports water/wastewater

US Army Corps of Engineers

232

Peace Corps / Youth & Community Development Youth and Community Development Volunteers  

E-Print Network [OSTI]

Peace Corps / Youth & Community Development Youth and Community Development Volunteers Through engage in a wide variety of locally sustainable projects. Volunteers act as catalysts for change Development Sample Projects ┬Ě Help young people form youth groups, clubs, sports teams, or extracurricular

Kaminsky, Werner

233

a Miscellaneous Paper A-96-1 US Army Corps  

E-Print Network [OSTI]

. Netherland, Judy F. Shearer =.=- -===- Approved For Public Release; Distribution Is Unlimited Prepared for Control of Hydrilla by Michael D. Netherland, Judy F. Shearer U.S. Army Corps of Engineers Waterways Netherland, Michael D. Integrated use of fluridone and a fungal pathogen for control of hydrilla / by Michael

US Army Corps of Engineers

234

m Technical Report A-94-3 US Army Corps  

E-Print Network [OSTI]

as Potential Herbicide Delivery Systems by Michael D. Netherland, R. Michael Stewart David Sisneros U.S. Bureau of Controlled-Release Matrices as Potential Herbicide Delivery Systems by Michael D. Netherland, R. Michael as potential herbicide delivery systems I by Michael D. Netherland ┬Ě.. let al.] ; prepared for U.S. Army Corps

US Army Corps of Engineers

235

The design and construction of a low cost Van de Graaff generator for nuclear research  

E-Print Network [OSTI]

silk belt rtxudng between a pulley in its interior arxf a grour?ed motor driven pulley at the bass of . he rod, 'hc ascending surface of the belt is charged near the lower pulley by a brush discharzw& maintained by a 10w000 volt transformer kenotron... tubes rather than the Tesla coil. After they oon- str xcted a one meter diameter generatcrx this smae group reconstructed an emlier outdoor two meter generator in sn appropriate indoor labora- 17 toxy, he high volta!w terminal consisted of the two...

Riggs, James Willborn

1953-01-01T23:59:59.000Z

236

In-Plant Reliability Data base for nuclear plant components. Interim report: diesel generators, batteries, chargers and inverters  

SciTech Connect (OSTI)

The objective of the In-Plant Reliability Data (IPRD) program is to develop a comprehensive, component-specific reliability data base for probabilistic risk assessment and for other statistical analyses relevant to component reliability evaluations. This document is the product of a pilot study that was undertaken to demonstrate the methodology and feasibility of applying IPRDS techniques to develop and analyze the reliability characteristics of key electrical components in five nuclear power plants. These electrical components include diesel generators, batteries, battery chargers and inverters. The sources used to develop the data base and produce the component failure rates and mean repair times were the plant equipment lists, plant drawings, maintenance work requests, Final Safety Analysis Reports (FSARs), and interviews with plant personnel. The data spanned approximately 33 reactor-years of commercial operation.

Kahl, W.K.; Borkowski, R.J.

1985-01-01T23:59:59.000Z

237

Volume reduction/solidification of liquid radioactive waste using bitumen at Ontario Hydro`s Bruce Nuclear Generating Station `A`  

SciTech Connect (OSTI)

Ontario Hydro at the Bruce Nuclear Generating Station `A` has undertaken a program to render the station`s liquid radioactive waste suitable for discharge to Lake Huron by removing sufficient radiological and chemical contaminants to satisfy regulatory requirements for emissions. The system will remove radionuclide and chemical contaminants from five different plant waste streams. The contaminants will be immobilized and stored at on-site radioactive waste storage facilities and the purified streams will be discharged. The discharge targets established by Ontario Hydro are set well below the limits established by the Ontario Ministry of Environment (MOE) and are based on the Best Available Technology Economically Achievable Approach (B.A.T.E.A.). ADTECHS Corporation has been selected by Ontario Hydro to provide volume reduction/solidification technology for one of the five waste streams. The system will dry and immobilize the contaminants from a liquid waste stream in emulsified asphalt using thin film evaporation technology.

Day, J.E.; Baker, R.L.

1995-05-01T23:59:59.000Z

238

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]

and Related Standards for Fossil-Fuel and Geo- thermal Powerposed Nuclear, Geothermal, and Fossil-Fuel Sites and Facili-NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN

Nero, A.V.

2010-01-01T23:59:59.000Z

239

Temperature and thermal stress distributions for the HFIR permanent reflector generated by nuclear heating  

SciTech Connect (OSTI)

The beryllium permanent reflector of the High Flux Isotope Reactor has the main functions for slowing down and reflecting the neutrons and housing the experimental facilities. The reflector is heated as a result of the nuclear reaction. Heat is removed mainly by the cooling water passing through the densely distributed coolant holes along the vertical or axial direction of the reflector. The reflector neutronic distribution and its heating rate are calculated by J.C. Gehin of the Oak Ridge National Laboratory by applying the Monte Carlo Code MCNP. The heat transfer boundary conditions along several reflector interfaces are estimated to remove additional heat from the reflector. The present paper is to report the calculation results of the temperature and the thermal stress distributions of the permanent reflector by applying the computer aided design code I-DEAS and the finite element code ABAQUS. The present calculation is to estimate the high stress areas as a result of the new beam tube cutouts along the horizontal mid-plane of the reflector of the recent reactor upgrade project. These high stresses were not able to be calculated in the preliminary design analysis in earlier 60`s. The heat transfer boundary conditions are used in this redesigned calculation. The material constants and the acceptance criteria for the allowable stresses are mainly based on that assumed in the preliminary design report.

Chang, S.J.

1998-04-01T23:59:59.000Z

240

Novel Concepts for Damage-Resistant Alloys in Next Generation Nuclear Power Systems  

SciTech Connect (OSTI)

The discovery of a damage-resistant alloy based on Hf solute additions to a low-carbon 316SS is the highlight of the Phase II research. This damage resistance is supported by characterization of radiation-induced microstructures and microchemistries along with measurements of environmental cracking. The addition of Hf to a low-carbon 316SS reduced the detrimental impact of radiation by changing the distribution of Hf. Pt additions reduced the impact of radiation on grain boundary segregation but did not alter its effect on microstructural damage development or cracking. Because cracking susceptibility is associated with several material characteristics, separate effect experiments exploring strength effects using non-irradiated stainless steels were conducted. These crack growth tests suggest that irradiation strength by itself can promote environmental cracking. The second concept for developing damage resistant alloys is the use of metastable precipitates to stabilize the microstructure during irradiation. Three alloys have been tailored for evaluation of precipitate stability influences on damage evolution. The first alloy is a Ni-base alloy (alloy 718) that has been characterized at low neutron irradiation doses but has not been characterized at high irradiation doses. The other two alloys are Fe-base alloys (PH 17-7 and PH 17-4) that have similar precipitate structures as alloy 718 but is more practical in nuclear structures because of the lower Ni content and hence lesser transmutation to He.

Stephen M. Bruemmer; Peter L. Andersen; Gary Was

2002-12-27T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation corp" 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

Securing the Sustainability of Global Medical Nuclear Supply Chains  

E-Print Network [OSTI]

, according to Kramer (2011), the South African Nuclear Energy Corp (Necsa) believes that the LEU productionSecuring the Sustainability of Global Medical Nuclear Supply Chains Through Economic Cost Recovery-17, 2012 University of Massachusetts Amherst Securing the Sustainability of Medical Nuclear Supply Chains

Nagurney, Anna

242

Evaluation of the Effectiveness of a New Technology for Extraction of Insoluble Impurities from Nuclear Power Plant Steam Generators with Purge Water  

SciTech Connect (OSTI)

An experimental technology for the removal of insoluble impurities from a horizontal steam generator with purge water during planned shutdowns of the power generating unit is improved through a more representative determination of the concentration of impurities in the purge water ahead of the water cleanup facility and a more precise effective time for the duration of the purge process. Tests with the improved technique at power generating unit No. 1 of the Rostov Nuclear Power Plant show that the efficiency with which insoluble impurities are removed from the steam generator volume was more than two orders of magnitude greater than under the standard regulations.

Bud'ko, I. O. [JSC NIITsE 'Tsentrenergo' (Russian Federation)] [JSC NIITsE 'Tsentrenergo' (Russian Federation); Zhukov, A. G. [Rostov Nuclear Power Plant (Russian Federation)] [Rostov Nuclear Power Plant (Russian Federation)

2013-11-15T23:59:59.000Z

243

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

244

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

SciTech Connect (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

245

he students, faculty, and research staff of the MIT Department of Nuclear Science and Engineering (NSE) generate, control, and apply nuclear  

E-Print Network [OSTI]

T he students, faculty, and research staff of the MIT Department of Nuclear Science and Engineering and technology. Professor Richard K. Lester Head, Department of Nuclear Science & Engineering rklester contact Professor Richard K. Lester, Head Department of Nuclear Science & Engineering rklester

Polz, Martin

246

On-Line Monitoring and Diagnostics of the Integrity of Nuclear Plant Steam Generators and Heat Exchangers, Volumes 1, 2.  

SciTech Connect (OSTI)

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. ├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬Ě 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. ├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬Ě 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. ├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬Ě Development of a hybrid modeling technique for process diagnosis and its evaluation using laboratory heat exchanger test data. ├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬Ě 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. ├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬Ě Development of advanced signal processing methods using wavelet transforms and image processing techniques for isolating flaw types. ├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬?├?┬Ě 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

Upadhyaya, Belle R.; Hines, J. Wesley; Lu, Baofu; Huang, Xuedong; Penha, Rosani, L.; Perillo, Sergio, R.; Zhao, Ke

2005-06-03T23:59:59.000Z

247

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

SciTech Connect (OSTI)

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

248

Vorbeck Materials Corp. | Department of Energy  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched Ferromagnetism inS-4500IIVasudhaSurface. |Volunteering employees,Vorbeck Materials

249

Sandia National Laboratories: Northrop Grumman Corp.  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -theErik Spoerke SSLSMolten-Salt StorageNo More Green Waste in the

250

Monthly/Annual Energy Review - nuclear section  

Reports and Publications (EIA)

Monthly and latest annual statistics on nuclear electricity capacity, generation, and number of operable nuclear reactors.

2015-01-01T23:59:59.000Z

251

Fuel Cell Opportunities in Marine Corps Garrison  

E-Print Network [OSTI]

Response ┬ş Distributed Power Generation Power `Spectrum' 101 102 103 104 105 106 107 108 FUEL CELL Watts% 315,343, 4% 1,585,200, 19% 5,937,358, 73% E85 CNG B100 Diesel Gasoline #12;1 3 0 5 10 15 20 25 30 FY01 MilitaryCivil Soldier Power Residential Automotive Electronics Ship Service Ship Propulsion Heavy Vehicle

252

National Wetlands Inventory The U.S. Army Corps of Engineers (Corps) as of 2006 has accepted the administrative responsibility for  

E-Print Network [OSTI]

National Wetlands Inventory The U.S. Army Corps of Engineers (Corps) as of 2006 has accepted the administrative responsibility for the National Wetland Plant List from the U.S. Fish and Wildlife Service (FWS). In early 2009 the FWS removed the published 1988 and 1996 wetland plant lists from their National Wetland

US Army Corps of Engineers

253

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

SciTech Connect (OSTI)

The United States Department of Energyĺs 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 Energyĺs lead laboratory for nuclear energy development. The ATR is one of the worldĺs 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

254

Pee Dee Electric Member Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of InspectorConcentrating Solar Powerstories onFocusOski Energy LLCPascoag Utility DistrictPeaCouncilMember Corp

255

Safe Harbor Water Power Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of InspectorConcentrating Solar PowerstoriesNrelPartnerType JumpJersey)Carbon DevelopmentCorp Jump to:

256

Just Energy New York Corp. (New York) | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of InspectorConcentrating Solar Powerstories on climateJuno Beach, Florida: Energy Resources Jump to:Corp. (New

257

Tipmont Rural Elec Member Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of InspectorConcentrating SolarElectric Coop, IncTipmont Rural Elec Member Corp Jump to: navigation, search

258

Clay County Electric Coop Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of Inspector GeneralDepartmentAUDITOhioOglesby,Sullivan, MissouriWebsterElectric Coop Corp Jump to: navigation,

259

Solar installer training: Home Builders Institute Job Corps  

SciTech Connect (OSTI)

The instructors describe the solar installation training program operated since 1979 by the Home Builders Institute, the Educational Arm of the National Association of Home Builders for the US Department of Labor, Job Corps in San Diego, CA. The authors are the original instructors and have developed the program since its inception by a co-operative effort between the Solar Energy Industries Association, NAHB and US DOL. Case studies of a few of the 605 students who have gone to work over the years after the training are included. It is one of the most successful programs under the elaborate Student Performance Monitoring Information System used by all Job Corps programs. Job Corps is a federally funded residential job training program for low income persons 16--24 years of age. Discussion details the curriculum and methods used in the program including classroom, shop and community service projects. Solar technologies including all types of hot water heating, swimming pool and spa as well as photovoltaics are included.

Hansen, K.; Mann, R. [San Diego Job Corps Center, Imperial Beach, CA (United States). Home Builders Inst.

1996-10-01T23:59:59.000Z

260

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

SciTech Connect (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

Note: This page contains sample records for the topic "nuclear generation corp" 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

A Cargo Inspection System for Special Nuclear Material (SNM) Based on Associated Particle Neutron Generators and Liquid-Kr Detectors  

SciTech Connect (OSTI)

A feasibility analysis is presented of a cargo inspection system based on neutron-induced fission followed by the coincident detection of multiple prompt fission gamma rays as a signature of Special Nuclear Material (SNM). The system does not require gamma ray spectroscopy and would be capable of distinguishing U-238 from U-235 using the ratio of signals from two modes of detection: thermal neutron capture induced fission and fast neutron-induced fission. The system utilizes two deuterium-tritium (DT) associated particle neutron generators, each capable of 10{sup 9} neutrons/s at 14.1 MeV, with sub-nanosecond timing resolution ZnO:Ga alpha detectors. The expected {approx}1 MeV prompt gamma rays are detected using liquid krypton (LKr) detectors with sub-nanosecond timing resolution ({approx}600 ps) and high detection efficiency. The expected SNM signal and randomly correlated background rates are discussed using Monte Carlo N-Particle (MCNP) code.

Koltick, David S.; Kane, Steven Z. [Purdue University Applied Physics Laboratory 740 Navco Dr., Lafayette, IN 47906 (United States)

2009-03-10T23:59:59.000Z

262

Ann. Sci. Math. Quebec (2005), no. , 00. UNIT ES ELLIPTIQUES, CORPS QUADRATIQUES  

E-Print Network [OSTI]

┬┤e question dans l'expos┬┤e de Radan Kucera [Ku] fournissent un outil puissant dans l'┬┤etude des corps

Darmon, Henri

2005-01-01T23:59:59.000Z

263

Unites elliptiques, corps quadratiques reels, et une formule limite de Kronecker  

E-Print Network [OSTI]

dans l'expos┬┤e de Radan Kucera fournissent un outil puissant dans l'┬┤etude des corps cyclotomiques. Ces

Dasgupta, Samit

264

U.S. Marine Corps Stand at Forefront of Energy and Water Savings (Fact Sheet)  

SciTech Connect (OSTI)

This fact sheet is an overview of the U.S. Marine Corps Beaufort Air Station's energy and water savings accomplishments.

Not Available

2012-12-01T23:59:59.000Z

265

Peace Corps Volunteers and the Boundaries of Bottom-up Development  

E-Print Network [OSTI]

agricultural volunteers in Africa sidestepped these organizationally initiated projects just as Peace Corps Mongolia volunteers avoided showing the Alcohol Task Force film ô

Schuckman, Hugh Erik

2012-01-01T23:59:59.000Z

266

E-Print Network 3.0 - access health corp Sample Search Results  

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

Science 2 Regional Network Access Point DS1 (T1) single or multiple Summary: Regional Health Care Corp Tonalea Chapter House Pima County Adult Detention Center University...

267

E-Print Network 3.0 - army medical corps Sample Search Results  

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

... Source: US Army Corps of Engineers - Coastal and Hydraulics Laboratory (CERC) Engineer Waterways Experiment Station Vicksburg, MS Collection: Engineering 2 BUILDING STRONG...

268

E-Print Network 3.0 - army chemical corps Sample Search Results  

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

for ... Source: US Army Corps of Engineers - Coastal and Hydraulics Laboratory (CERC) Engineer Waterways Experiment Station Vicksburg, MS Collection: Engineering 2 US ArmyUS Army...

269

A decision-support model for managing the fuel inventory of a Panamanian generating company  

E-Print Network [OSTI]

Bahia Las Minas Corp (BLM) is a fuelpowered generating company in the Panamanian power system. The purpose of this thesis is to design and evaluate a decision-support model for managing the fuel inventory of this company. ...

Perez-Franco, Roberto, 1976-

2004-01-01T23:59:59.000Z

270

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...

271

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...

272

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...

273

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...

274

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...

275

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...

276

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...

277

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...

278

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...

279

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...

280

Maryland 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...

Note: This page contains sample records for the topic "nuclear generation corp" 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

Illinois Nuclear Profile - Power Plants  

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

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

282

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...

283

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...

284

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...

285

Salt River Electric Coop Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of InspectorConcentrating Solar PowerstoriesNrelPartnerType JumpJersey)Carbon DevelopmentCorp JumpRiver

286

New England Hydro-Trans Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia: Energy Resources Jump to:46 -Energieprojekte3InformationofServicesNeuCo620572┬░,York:Hydro-Trans Corp Jump

287

Sky WindPower Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of Inspector GeneralDepartmentAUDIT REPORTOpenWende New EnergyAnatoliaSciraShenhuaWindPower Corp Place: Ramona,

288

Arima Photovoltaic And Optical Corp Arima PV | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublic Utilities Address: 160 East 300AlgoilEnergy InformationArcata,Koblitz Jump to:ArgonautMaine:Optical Corp

289

C & L Electric Coop Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublic Utilities Address: 160Benin: EnergyBoston Areais aBurkittsville,Bushyhead,ButtsC & L Electric Coop Corp

290

Liberty Power Corp. (New York) | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of InspectorConcentrating Solar Powerstories on climateJuno Beach,October, 2012LeeCaliforniaLiberty Power Corp.

291

North Georgia Elec Member Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of InspectorConcentrating Solar Powerstories onFocus AreaDataBusPFAN) | OpenIncNobleNorrisElec Member Corp Jump

292

U S Army Corps of Engineers | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 No revisionEnvReviewNonInvasiveExplorationUT-gTaguspark JumpDetective:ToyoTurkey:S Army Corps of Engineers

293

U.S. Marine Corp Logistics Base | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 No revisionEnvReviewNonInvasiveExplorationUT-gTaguspark JumpDetective:ToyoTurkey:S Army 200px Name: U.S.Corp

294

Nippon Coke and Engineering Sumitomo Corp JV | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 No revision hasInformation Earth's HeatMexico: EnergyMithunCenterInformationNexxus(CTI PFAN)Corp JV Jump to:

295

Stream Fund High Tech Group Corp Ltd | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 No revisionEnvReviewNonInvasiveExplorationUT-g GrantAtlas (PACAOpen Energy InformationStonyMonitoring |Corp Ltd

296

DOE - Office of Legacy Management -- American Bearing Corp - IN 09  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou are here Home ┬╗ SitesNJ 24 FUSRAPAlaskaBearing Corp

297

DOE - Office of Legacy Management -- Dorr Corp - CT 14  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou are here Home ┬╗HillNY 28Dorr Corp - CT 14

298

DOE - Office of Legacy Management -- Michigan Velsicol Chemical Corp - MI  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou are here HomeGunnison-EngineerSelling Corp03

299

Pacific Fuel Cell Corp PFCE | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia: Energy ResourcesLoading map...(UtilityCounty,Orleans County,PPP EquipmentPartners LLC Jump to: navigation,Corp

300

Alaska District US Army Corps of Engineers | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublic Utilities Address: 160 East 300 SouthWaterBrasil JumpAerowattOpen2008District NoRegulations Webpage |Corps

Note: This page contains sample records for the topic "nuclear generation corp" 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

Cape Hatteras Elec Member Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublic Utilities Address: 160Benin: EnergyBostonFacility | Open EnergySolar33.6850215┬░,Hatteras Elec Member Corp

302

Green Wave Energy Corp GWEC | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 No revision hasInformation Earth's Heat Jump to:Photon Place: Golden, COIndianaLondon,Wind FarmEnergy Corp GWEC

303

SunEnergy Power Corp SEPC | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia:FAQ < RAPID Jump to:Seadov Pty LtdSteen, Minnesota:36052┬░, -97.6114217┬░SunEnergy Power Corp SEPC Jump to:

304

Tri-State Electric Member Corp (Tennessee) | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia:FAQ < RAPID Jump to:Seadov Pty LtdSteen,LtdInformation DixieTraverse Electric Coop,Trenton,Corp

305

Tri-State Electric Member Corp | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia:FAQ < RAPID Jump to:Seadov Pty LtdSteen,LtdInformation DixieTraverse Electric Coop,Trenton,CorpJump to:

306

Imara Corp formerly Lion Cells | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia: Energy Resources Jump to: navigation,Ohio:GreerHiCalifornia:ISI SolarIdanha,Information Jump to:Imara Corp

307

Report to the NRC on guidance for preparing scenarios for emergency preparedness exercises at nuclear generating stations. Draft report for comment  

SciTech Connect (OSTI)

A scenario guidance handbook was prepared to assist emergency planners in developing scenarios for emergency preparedness exercises at nuclear power plants. The handbook provides guidance for the development of the objectives of an exercise, the descriptions of scenario events and responses, and the instructions to the participants. Information concerning implementation of the scenario, critiques and findings, and generation and format of scenario data are also included. Finally, examples of manual calculational techniques for producing radiological data are included as an appendix.

Martin, G.F.; Hickey, E.E.; Moeller, M.P.; Schultz, D.H.; Bethke, G.W.

1986-03-01T23:59:59.000Z

308

RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

EMERGENCY PLANNING FOR NUCLEAR POWER PLANTS: THE LICENSINGEmergency Planning for Nuclear Power Plants Determination ofproposed nuclear power plants . . . . . . . . . Ľ . . . .

Yen, W.W.S.

2010-01-01T23:59:59.000Z

309

EPA and the Army Corps' Proposed Rule to Define "Waters of the United States"  

E-Print Network [OSTI]

EPA and the Army Corps' Proposed Rule to Define "Waters of the United States" Claudia Copeland.crs.gov R43455 #12;EPA and the Army Corps' Proposed Rule to Define "Waters of the United States regulatory definition of "waters of the United States" consistent with legal rulings--especially the Supreme

Gilbes, Fernando

310

U.S. Air Force Fact Sheet Air Force Reserve Officer Training Corps  

E-Print Network [OSTI]

U.S. Air Force Fact Sheet Air Force Reserve Officer Training Corps Mission Develop Quality Leaders for the Air Force. Personnel and Resources Air Force Reserve Officer Training Corps (ROTC) includes four,796 new Second Lieutenants who entered active duty in the United States Air Force. Organization Air Force

Su, Xiao

311

GIS Professionals The Forestry Corp., based in Edmonton, Alberta, has been providing exceptional quality professional  

E-Print Network [OSTI]

GIS Professionals The Forestry Corp., based in Edmonton, Alberta, has been providing exceptional: Be self-motivated Be a good problem solver Have some experience or exposure to the business of forestry. Please forward resumes and cover letters to: The Forestry Corp. Attention: Information Services Manager

312

Miscellaneous Paper A-97-2 I!Ius Army Corps  

E-Print Network [OSTI]

Accomplishments by Kurt D. Getsinger, Michael D. Netherland Plants: Summary of Research Accomplishments by Kurt D. Getsinger, Michael D. Netherland U.S. Army Corps / by Kurt D. Getsinger, Michael D. Netherland ; prepared for U.S. Army Corps ofEngineers. 22 p. : ill. ; 28

US Army Corps of Engineers

313

PEACE CORPS ENERGY AND CLIMATE PARTNERSHIP OF THE AMERICAS (ECPA) INITIATIVE  

E-Print Network [OSTI]

the capacity of communities in Latin America to address rural energy poverty through a multi-faceted approachPEACE CORPS ENERGY AND CLIMATE PARTNERSHIP OF THE AMERICAS (ECPA) INITIATIVE Peace Corps' awareness to promote behavior change related to energy conservation, use of renewable energy, climate

Mlllet, Dylan B.

314

Wetlands Research Program Technical Report Y-87-1 (on-line edition) Corps of Engineers  

E-Print Network [OSTI]

Wetlands Research Program Technical Report Y-87-1 (on-line edition) Corps of Engineers Wetlands used as part of the number designating technical reports of research published under the Wetlands;Wetlands Research Program Technical Report Y-87-1 January 1987 Corps of Engineers Wetlands Delineation

US Army Corps of Engineers

315

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

SciTech Connect (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

316

Reactor Physics Parametric and Depletion Studies in Support of TRISO Particle Fuel Specification for the Next Generation Nuclear Plant  

SciTech Connect (OSTI)

Reactor physics calculations were initiated to answer several major questions related to the proposed TRISO-coated particle fuel that is to be used in the prismatic Very High Temperature Reactor (VHTR) or the Next Generation Nuclear Plant (NGNP). These preliminary design evaluation calculations help ensure that the upcoming fuel irradiation tests will test appropriate size and type of fuel particles for a future NGNP reactor design. Conclusions from these calculations are expected to confirm and suggest possible modifications to the current particle fuel parameters specified in the evolving Fuel Specification. Calculated results dispel the need for a binary fuel particle system, which is proposed in the General Atomics GT-MHR concept. The GT-MHR binary system is composed of both a fissile and fertile particle with 350- and 500- micron kernel diameters, respectively. For the NGNP reactor, a single fissile particle system (single UCO kernel size) can meet the reactivity and power cycle length requirements demanded of the NGNP. At the same time, it will provide substantial programmatic cost savings by eliminating the need for dual particle fabrication process lines and dual fuel particle irradiation tests required of a binary system. Use of a larger 425-micron kernel diameter single fissile particle (proposed here), as opposed to the 350-micron GT-MHR fissile particle size, helps alleviate current compact particle packing fractions fabrication limitations (<35%), improves fuel block loading for higher n-batch reload options, and tracks the historical correlation between particle size and enrichment (10 and 14 wt% U-235 particle enrichments are proposed for the NGNP). Overall, the use of the slightly larger kernel significantly broadens the NGNP reactor core design envelope and provides increased design margin to accommodate the (as yet) unknown final NGNP reactor design. Maximum power-peaking factors are calculated for both the initial and equilibrium NGNP cores. Radial power-peaking can be fully controlled with particle packing fraction zoning (no enrichment zoning required) and discrete burnable poison rods. Optimally loaded NGNP cores can expect radial powerpeaking factors as low as 1.14 at beginning of cycle (BOC), increasing slowly to a value of 1.25 by end of cycle (EOC), an axial power-peaking value of 1.30 (BOC), and for individual fuel particles in the maximum compact <1.05 (BOC) and an approximate value of 1.20 (EOC) due to Pu-239 buildup in particles on the compact periphery. The NGNP peak particle powers, using a conservative total power-peaking factor (~2.1 factor), are expected to be <150 mW/particle (well below the 250 mW/particle limit, even with the larger 425-micron kernel size).

James W. Sterbentz; Bren Phillips; Robert L. Sant; Gray S. Chang; Paul D. Bayless

2003-09-01T23:59:59.000Z

317

Effect of Nuclear Motion on Molecular High-Order Harmonics and on Generation of Attosecond Pulses in Intense Laser Pulses  

SciTech Connect (OSTI)

We calculate harmonic spectra and shapes of attosecond-pulse trains using numerical solutions of Non-Born-Oppenheimer time-dependent Shroedinger equation for 1D H{sub 2} molecules in an intense laser pulse. A very strong signature of nuclear motion is seen in the time profiles of high-order harmonics. In general the nuclear motion shortens the part of the attosecond-pulse train originating from the first electron contribution, but it may enhance the second electron contribution for longer pulses. The shape of time profiles of harmonics can thus be used for monitoring the nuclear motion.

Bandrauk, Andre D.; Chelkowski, Szczepan; Kawai, Shinnosuke; Lu, Huizhong [Departement de Chimie, Universite de Sherbrooke, Sherbrooke, Qc, J1K 2R1 (Canada)

2008-10-10T23:59:59.000Z

318

Energy Department Announces New Investments to Train Next Generation...  

Office of Environmental Management (EM)

to Train Next Generation of Nuclear Energy Leaders, Advance University-Led Nuclear Innovation Energy Department Announces New Investments to Train Next Generation of Nuclear Energy...

319

Energy Department Invests $60 Million to Train Next Generation...  

Office of Environmental Management (EM)

60 Million to Train Next Generation Nuclear Energy Leaders, Pioneer Advanced Nuclear Technology Energy Department Invests 60 Million to Train Next Generation Nuclear Energy...

320

Activation cross sections of $?$-particle induced nuclear reactions on hafnium and deuteron induced nuclear reaction on tantalum: production of $^{178}$W/$^{178m}$Ta generator  

E-Print Network [OSTI]

In the frame of a systematic study of charged particle production routes of medically relevant radionuclei, the excitation function for indirect production of $^{178m}$Ta through $^{nat}$Hf($\\alpha$,xn)$^{178}$W-$^{178m}$Ta nuclear reaction was measured for the first time up to 40 MeV. In parallel, the side reactions $^{nat}$Hf($\\alpha$,x)$^{179,177,176,175}$W, $^{183,182,178g,177,176,175}$Ta, $^{179m,177m,175}$Hf were also assessed. Stacked foil irradiation technique and $\\gamma$-ray spectrometry were used. New experimental cross section data for the $^{nat}$Ta(d,xn)$^{178}$W reaction are also reported up to 40 MeV. The measured excitation functions are compared with the results of the ALICE-IPPE, and EMPIRE nuclear reaction model codes and with the TALYS 1.4 based data in the TENDL-2013 library. The thick target yields were deduced and compared with yields of other charged particle ((p,4n), (d,5n) and ($^3$He,x)) production routes for $^{178}$W.

F. Tßrk'anyi; S. Tak'acs; F. Ditrˇi; A. Hermanne; A. V. Ignatyuk; M. S. Uddin

2014-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation corp" 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

Washington Nuclear Profile - Power Plants  

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

total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Columbia Generating Station Unit...

322

RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

S. Commercial Nuclear Power Plants. WASH-1400. October 1975.Content of for Nuclear Power Plants. Regulatory Guide 1.101.PLANNING FOR NUCLEAR POWER PLANTS: THE LICENSING PROCESS

Yen, W.W.S.

2010-01-01T23:59:59.000Z

323

RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

from the Rancho Seco nuclear plant was simulated, A total ofdistributions around the nuclear plant sites based on thegrowth surrounding nuclear plants after the issuance of the

Yen, W.W.S.

2010-01-01T23:59:59.000Z

324

CONTROL OF POPULATION DENSITIES SURROUNDING NUCLEAR POWER PLANTS. VOLUME 5 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

surrounding a nuclear plant, and they are stronglylocation for a nuclear plant, but it is the measures thatand consequences of nuclear plant accidents and would match

Nero, jA.V.

2010-01-01T23:59:59.000Z

325

Proceedings of the 2. MIT international conference on the next generation of nuclear power technology. Final report  

SciTech Connect (OSTI)

The goal of the conference was to try to attract a variety of points of view from well-informed people to debate issues concerning nuclear power. Hopefully from that process a better understanding of what one should be doing will emerge. In organizing the conference lessons learned from the previous one were applied. A continuous effort was made to see to it that the arguments for the alternatives to nuclear power were given abundant time for presentation. This is ultimately because nuclear power is going to have to compete with all of the energy technologies. Thus, in discussing energy strategy all of the alternatives must be considered in a reasonable fashion. The structure the conference used has seven sessions. The first six led up to the final session which was concerned with what the future nuclear power strategy should be. Each session focused upon a question concerning the future. None of these questions has a unique correct answer. Rather, topics are addressed where reasonable people can disagree. In order to state some of the important arguments for each session`s question, the combination of a keynote paper followed by a respondent was used. The respondent`s paper is not necessarily included to be a rebuttal to the keynote; but rather, it was recognized that two people will look at a complex question with different shadings. Through those two papers the intention was to get out the most important arguments affecting the question for the session. The purpose of the papers was to set the stage for about an hour of discussion. The real product of this conference was that discussion.

NONE

1993-12-31T23:59:59.000Z

326

Incorporation of Hydride Nuclear Fuels in Commercial Light Water Reactors  

E-Print Network [OSTI]

electricity generation capacity and operating efficiency of nuclear plants [Nuclear Plant Capacity Factor Nuclear Electricity Generationelectricity generation capacity and operating efficiency of nu- clear plants [

Terrani, Kurt Amir

2010-01-01T23:59:59.000Z

327

Air Flow North America Corp. ľ FE Dkt. No. 14-53-LNG (Re-export)  

Broader source: Energy.gov [DOE]

The Office of Fossil Energy (FE) of the Department of Energy (DOE) gives notice of receipt of an application filed on March 25, 2014, by Air Flow North America Corp. (AIR FLOW) requesting short...

328

New Lab-Corps program marries science and business to help move...  

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

New Lab-Corps program marries science and business to help move technologies to the market By Justin H.S. Breaux * December 3, 2014 Tweet EmailPrint ARGONNE, Ill. - The U.S....

329

An overview and comparative analysis of United States Army Corps of Engineers partnering in construction  

E-Print Network [OSTI]

The construction industry is attacking the challenges of the 1990's by implementing the use of a concept known as partnering. Private and public sectors alike are showing interest in the application of this concept. The US Army Corps...

Rock, Timothy Patrick

1992-01-01T23:59:59.000Z

330

FEMP ESPC Success Story- Marine Corps Base Camp Pendleton, Camp Pendleton, California  

Broader source: Energy.gov [DOE]

Fact sheet describes the Energy savings Performance Contract (ESPC) Success Story on how a comprehensive effort cuts energy use by 44% at Marine Corps Base Camp Pendleton in Camp Pendleton, California.

331

Air Flow North America Corp.- Fe Dkt. No. 14-206-LNG  

Broader source: Energy.gov [DOE]

The Office of Fossil Energy gives notice of receipt of an Application filed December 16, 2014, by Air Flow North America Corp. (Air Flow), seeking a long-term multi-contract authorization to export...

332

Radioisotope Power System Delivery, Ground Support and Nuclear Safety Implementation: Use of the Multi-Mission Radioisotope Thermoelectric Generator for the NASA's Mars Science Laboratory  

SciTech Connect (OSTI)

Radioisotope power systems have been used for over 50 years to enable missions in remote or hostile environments. They are a convenient means of supplying a few milliwatts up to a few hundred watts of useable, long-term electrical power. With regard to use of a radioisotope power system, the transportation, ground support and implementation of nuclear safety protocols in the field is a complex process that requires clear identification of needed technical and regulatory requirements. The appropriate care must be taken to provide high quality treatment of the item to be moved so it arrives in a condition to fulfill its missions in space. Similarly it must be transported and managed in a manner compliant with requirements for shipment and handling of special nuclear material. This presentation describes transportation, ground support operations and implementation of nuclear safety and security protocols for a radioisotope power system using recent experience involving the Multi-Mission Radioisotope Thermoelectric Generator for National Aeronautics and Space Administrationĺs Mars Science Laboratory, which launched in November of 2011.

S.G. Johnson; K.L. Lively; C.C. Dwight

2014-07-01T23:59:59.000Z

333

HIGH EFFICIENCY GENERATION OF HYDROGEN FUELS USING NUCLEAR POWER FINAL RECHNICAL REPORT FOR THE PERIOD AUGUST 1, 1999 THROUGH SEPTEMBER 30, 2002 REV. 1  

SciTech Connect (OSTI)

OAK-B135 Combustion of fossil fuels, used to power transportation, generate electricity, heat homes and fuel industry provides 86% of the world's energy [1-1,1-2]. Drawbacks to fossil fuel utilization include limited supply, pollution, and carbon dioxide emissions. Carbon dioxide emissions, thought to be responsible for global warming, are now the subject of international treaties [1-3,1-4]. Together, these drawbacks argue for the replacement of fossil fuels with a less-polluting potentially renewable primary energy such as nuclear energy. Conventional nuclear plants readily generate electric power but fossil fuels are firmly entrenched in the transportation sector. Hydrogen is an environmentally attractive transportation fuel that has the potential to displace fossil fuels. Hydrogen will be particularly advantageous when coupled with fuel cells. Fuel cells have higher efficiency than conventional battery/internal combustion engine combinations and do not produce nitrogen oxides during low-temperature operation. Contemporary hydrogen production is primarily based on fossil fuels and most specifically on natural gas. When hydrogen is produced using energy derived from fossil fuels, there is little or no environmental advantage. There is currently no large scale, cost-effective, environmentally attractive hydrogen production process available for commercialization, nor has such a process been identified. The objective of this work is to find an economically feasible process for the production of hydrogen, by nuclear means, using an advanced high-temperature nuclear reactor as the primary energy source. Hydrogen production by thermochemical water-splitting (Appendix A), a chemical process that accomplishes the decomposition of water into hydrogen and oxygen using only heat or, in the case of a hybrid thermochemical process, by a combination of heat and electrolysis, could meet these goals. Hydrogen produced from fossil fuels has trace contaminants (primarily carbon monoxide) that are detrimental to precious metal catalyzed fuel cells, as is now recognized by many of the world's largest automobile companies. Thermochemical hydrogen will not contain carbon monoxide as an impurity at any level. Electrolysis, the alternative process for producing hydrogen using nuclear energy, suffers from thermodynamic inefficiencies in both the production of electricity and in electrolytic parts of the process. The efficiency of electrolysis (electricity to hydrogen) is currently about 80%. Electric power generation efficiency would have to exceed 65% (thermal to electrical) for the combined efficiency to exceed the 52% (thermal to hydrogen) calculated for one thermochemical cycle. Thermochemical water-splitting cycles have been studied, at various levels of effort, for the past 35 years. They were extensively studied in the late 70s and early 80s but have received little attention in the past 10 years, particularly in the U.S. While there is no question about the technical feasibility and the potential for high efficiency, cycles with proven low cost and high efficiency have yet to be developed commercially. Over 100 cycles have been proposed, but substantial research has been executed on only a few. This report describes work accomplished during a three-year project whose objective is to ''define an economically feasible concept for production of hydrogen, by nuclear means, using an advanced high temperature nuclear reactor as the energy source.''

BROWN,LC; BESENBRUCH,GE; LENTSCH, RD; SCHULTZ,KR; FUNK,JF; PICKARD,PS; MARSHALL,AC; SHOWALTER,SK

2003-12-01T23:59:59.000Z

334

Predictions of leadership in Texas A&M University's Corps of Cadets  

E-Print Network [OSTI]

PREDICTIONS OF LEADERSHIP IN TEXAS AQ1 UNIVERSITY'S CORPS OF CADETS A Thesis by Donald R. Henderson Submitted to the Graduate College of Texas ASM University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE... August 1974 Major Subject: Educational Psychology PREDICTIONS OF LEADERSHIP IN TEXAS ASM UNIVERSITY'S CORPS OF CADETS A Thesis by Donald R. Henderson Approved as to style and content by: airman of Cosmittee CiK Head of Departmen Membe r mbe r...

Henderson, Donald Raymond

1974-01-01T23:59:59.000Z

335

Nuclear Hydrogen  

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

Hydrogen High temperature options for nuclear generation of hydrogen on a commercial basis are several years in the future. Thermo-chemical water splitting has been proven to be...

336

Verification of voltage/frequency requirement for emergency diesel generator in nuclear power plant using dynamic modeling  

SciTech Connect (OSTI)

One major cause of the plant shutdown is the loss of electrical power. The study is to comprehend the coping action against station blackout including emergency diesel generator, sequential loading of safety system and to ensure that the emergency diesel generator should meet requirements, especially voltage and frequency criteria using modeling tool. This paper also considered the change of the sequencing time and load capacity only for finding electrical design margin. However, the revision of load list must be verified with safety analysis. From this study, it is discovered that new load calculation is a key factor in EDG localization and in-house capability increase.

Hur, Jin-Suk; Roh, Myung- Sub [KEPCO International Nuclear Graduate School, 1456-1 Shinam-ri, Seosaeng-myeon, Ulju-gun, Ulsan, 689-882 (Korea, Republic of)

2014-02-12T23:59:59.000Z

337

Investigation of a Novel NDE Method for Monitoring Thermomechanical Damage and Microstructure Evolution in Ferritic-Martensitic Steels for Generation IV Nuclear Energy Systems  

SciTech Connect (OSTI)

The main goal of the proposed project is the development of validated nondestructive evaluation (NDE) techniques for in situ monitoring of ferritic-martensitic steels like Grade 91 9Cr-1Mo, which are candidate materials for Generation IV nuclear energy structural components operating at temperatures up to ~650{degree}C and for steam-generator tubing for sodium-cooled fast reactors. Full assessment of thermomechanical damage requires a clear separation between thermally activated microstructural evolution and creep damage caused by simultaneous mechanical stress. Creep damage can be classified as "negligible" creep without significant plastic strain and "ordinary" creep of the primary, secondary, and tertiary kind that is accompanied by significant plastic deformation and/or cavity nucleation and growth. Under negligible creep conditions of interest in this project, minimal or no plastic strain occurs, and the accumulation of creep damage does not significantly reduce the fatigue life of a structural component so that low-temperature design rules, such as the ASME Section III, Subsection NB, can be applied with confidence. The proposed research project will utilize a multifaceted approach in which the feasibility of electrical conductivity and thermo-electric monitoring methods is researched and coupled with detailed post-thermal/creep exposure characterization of microstructural changes and damage processes using state-of-the-art electron microscopy techniques, with the aim of establishing the most effective nondestructive materials evaluation technique for particular degradation modes in high-temperature alloys that are candidates for use in the Next Generation Nuclear Plant (NGNP) as well as providing the necessary mechanism-based underpinnings for relating the two. Only techniques suitable for practical application in situ will be considered. As the project evolves and results accumulate, we will also study the use of this technique for monitoring other GEN IV materials. Through the results obtained from this integrated materials behavior and NDE study, new insight will be gained into the best nondestructive creep and microstructure monitoring methods for the particular mechanisms identified in these materials. The proposed project includes collaboration with a national laboratory partner and the results will also serve as a foundation to guide the efforts of scientists in the DOE laboratory, university, and industrial communities concerned with the technological challenges of monitoring creep and microstructural evolution in materials planned to be used in Generation IV Nuclear Energy Systems.

Nagy, Peter

2013-09-30T23:59:59.000Z

338

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...

339

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...

340

New York 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...

Note: This page contains sample records for the topic "nuclear generation corp" 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

Regenerative Heater Optimization for Steam Turbo-Generation Cycles of Generation IV Nuclear Power Plants with a Comparison of Two Concepts for the Westinghouse International Reactor Innovative and Secure (IRIS)  

SciTech Connect (OSTI)

The intent of this study is to discuss some of the many factors involved in the development of the design and layout of a steam turbo-generation unit as part of a modular Generation IV nuclear power plant. Of the many factors involved in the design and layout, this research will cover feed water system layout and optimization issues. The research is arranged in hopes that it can be generalized to any Generation IV system which uses a steam powered turbo-generation unit. The research is done using the ORCENT-II heat balance codes and the Salisbury methodology to be reviewed herein. The Salisbury methodology is used on an original cycle design by Famiani for the Westinghouse IRIS and the effects due to parameter variation are studied. The vital parameters of the Salisbury methodology are the incremental heater surface capital cost (S) in $/ft{sup 2}, the value of incremental power (I) in $/kW, and the overall heat transfer coefficient (U) in Btu/ft{sup 2}-degrees Fahrenheit-hr. Each is varied in order to determine the effects on the cycles overall heat rate, output, as well as, the heater surface areas. The effects of each are shown. Then the methodology is then used to compare the optimized original Famiani design consisting of seven regenerative feedwater heaters with an optimized new cycle concept, INRC8, containing four regenerative heaters. The results are shown. It can be seen that a trade between the complexity of the seven stage regenerative Famiani cycle and the simplicity of the INRC8 cycle can be made. It is desired that this methodology can be used to show the ability to evaluate modularity through the value of size a complexity of the system as well as the performance. It also shows the effectiveness of the Salisbury methodology in the optimization of regenerative cycles for such an evaluation.

Williams, W.C.

2002-08-01T23:59:59.000Z

342

Next Generation Nuclear Plant Project Technology Development Roadmaps: The Technical Path Forward for 750ľ800░C Reactor Outlet Temperature  

SciTech Connect (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 750ľ800░C reactor outlet temperature (ROT) specific to each supplier are collected in Appendix A.

John Collins

2009-08-01T23:59:59.000Z

343

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

E-Print Network [OSTI]

-cooled Fast Reactor (GFR), Lead-cooled Fast Reactor (LFR), Molten Salt Reactor (MSR), Sodium-cooled Fast Reactor (SFR), Supercritical-water-cooled Reactor (SCWR) and the Very-high-temperature Reactor (VHTR). An international effort to develop these new... and the hydrogen production plant4,5. Davis et al. investigated the possibility of helium and molten salts in the IHTL2. The thermal efficiency of the power conversion unit is paramount to the success of this next generation technology. Current light water...

Barner, Robert Buckner

2007-04-25T23:59:59.000Z

344

Volume reduction/solidification of liquid radioactive waste using bitumen at Ontario hydro`s Bruce nuclear generating station {open_quotes}A{close_quotes}  

SciTech Connect (OSTI)

Ontario Hydro at the Bruce Nuclear Generating Station {open_quotes}A{close_quotes} has undertaken a program to render the station`s liquid radioactive waste suitable for discharge to Lake Huron by removing sufficient radiological and chemical contaminants from five different plant waste streams. The contaminants will be immobilized and stored at on-site radioactive waste storage facilities and the purified streams will be discharged. The discharge targets established by Ontario Hydro are set well below the limits established by the Ontario Ministry of Environment (MOE) and are based on the Best Available Technology Economically Achievable Approach (B.A.T.E.A.). ADTECHS Corporation has been selected by Ontario Hydro to provide volume reduction/solidification technology for one of the five waste streams. The system will dry and immobilize the contaminants from a liquid waste stream in emulsified asphalt using thin film evaporation technology.

Day, J.E.; Baker, R.L. [ADTECHS Corporation, Herndon, VA (United States)

1994-12-31T23:59:59.000Z

345

CONTROL OF POPULATION DENSITIES SURROUNDING NUCLEAR POWER PLANTS. VOLUME 5 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

Related Standards for Nuclear Power Plants," by A.V. NeroResponse Planning for Nuclear Power Plants in California,"Densities Surrounding Nuclear Power Plants," by A.V. Nero,

Nero, jA.V.

2010-01-01T23:59:59.000Z

346

CONTROL OF POPULATION DENSITIES SURROUNDING NUCLEAR POWER PLANTS. VOLUME 5 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

Standards for Nuclear Power Plants," by A.V. Nero and Y.C.Planning for Nuclear Power Plants in California," by W.W.S.Surrounding Nuclear Power Plants," by A.V. Nero, C.H.

Nero, jA.V.

2010-01-01T23:59:59.000Z

347

Preparing Non-nuclear Engineers for the Nuclear Field  

E-Print Network [OSTI]

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

Ervin, Elizabeth K.

348

Novel Concepts for Damage-Resistant Alloys in Next Generation Nuclear Power Systems - Final Report , Project 99-0280  

SciTech Connect (OSTI)

The discovery of a damage-resistant alloy based on Hf solute additions to a low-carbon 316SS is the highlight of the Phase II research. This damage resistance is supported by characterization of radiation-induced microstructures and microchemistries along with measurements of environmental cracking. The addition of Hf to a low-carbon 316SS reduced the detrimental impact of radiation by changing the distribution of Hf. Pt additions reduced the impact of radiation on grain boundary segregation but did not alter its effect on microstructural damage development or cracking. Because cracking susceptibility is associated with several material characteristics, separate effect experiments exploring strength effects using non-irradiated stainless steels were conducted. These crack growth tests suggest that irradiation strength by itself can promote environmental cracking. The second concept for developing damage resistant alloys is the use of metastable precipitates to stabilize the microstructure during irradiation. Three alloys have been tailored for evaluation of precipitate stability influences on damage evolution. The first alloy is a Ni-base alloy (alloy 718) that has been characterized at low neutron irradiation doses but has not been characterized at high irradiation doses. The other two alloys are Fe-base alloys (PH 17-7 and PH 17-4) that have similar precipitate structures as alloy 718 but is more practical in nuclear structures because of the lower Ni content and hence lesser transmutation to He.

Bruemmer, Stephen M.; Simonen, Edward P.; Gan, Jian; Garner, Francis A.; Gelles, David S.; Edwards, Danny J.; Andresen, Peter L.; Young, Lisa M.; Was, Gary S.; Fournier, L.; Sencer, Bulent H.

2002-12-27T23:59:59.000Z

349

Wisconsin Nuclear Profile - Point Beach Nuclear Plant  

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

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

350

Tennessee Nuclear Profile - Watts Bar Nuclear Plant  

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

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

351

Massachusetts Nuclear Profile - Pilgrim Nuclear Power Station  

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

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

352

Arkansas Nuclear Profile - Arkansas Nuclear One  

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

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

353

Gas Generation Equations for CRiSP 1.6 April 21, 1998 1 Gas Generation Equations for CRiSP 1.6  

E-Print Network [OSTI]

Gas Generation Equations for CRiSP 1.6 April 21, 1998 1 Gas Generation Equations for CRiSP 1.6 Theory For CRiSP.1.6 new equations have been implemented for gas production from spill. As a part of the US Army Corps' Gas Abatement study, Waterways Experiment Station (WES) has developed these new

Washington at Seattle, University of

354

Waste Classification based on Waste Form Heat Generation in Advanced Nuclear Fuel Cycles Using the Fuel-Cycle Integration and Tradeoffs (FIT) Model - 13413  

SciTech Connect (OSTI)

This study explores the impact of wastes generated from potential future fuel cycles and the issues presented by classifying these under current classification criteria, and discusses the possibility of a comprehensive and consistent characteristics-based classification framework based on new waste streams created from advanced fuel cycles. A static mass flow model, Fuel-Cycle Integration and Tradeoffs (FIT), was used to calculate the composition of waste streams resulting from different nuclear fuel cycle choices. This analysis focuses on the impact of waste form heat load on waste classification practices, although classifying by metrics of radiotoxicity, mass, and volume is also possible. The value of separation of heat-generating fission products and actinides in different fuel cycles is discussed. It was shown that the benefits of reducing the short-term fission-product heat load of waste destined for geologic disposal are neglected under the current source-based radioactive waste classification system, and that it is useful to classify waste streams based on how favorable the impact of interim storage is in increasing repository capacity. (authors)

Djokic, Denia [Department of Nuclear Engineering, University of California - Berkeley, 4149 Etcheverry Hall, Berkeley, CA 94720-1730 (United States)] [Department of Nuclear Engineering, University of California - Berkeley, 4149 Etcheverry Hall, Berkeley, CA 94720-1730 (United States); Piet, Steven J.; Pincock, Layne F.; Soelberg, Nick R. [Idaho National Laboratory - INL, 2525 North Fremont Avenue, Idaho Falls, ID 83415 (United States)] [Idaho National Laboratory - INL, 2525 North Fremont Avenue, Idaho Falls, ID 83415 (United States)

2013-07-01T23:59:59.000Z

355

Waste Classification based on Waste Form Heat Generation in Advanced Nuclear Fuel Cycles Using the Fuel-Cycle Integration and Tradeoffs (FIT) Model  

SciTech Connect (OSTI)

This study explores the impact of wastes generated from potential future fuel cycles and the issues presented by classifying these under current classification criteria, and discusses the possibility of a comprehensive and consistent characteristics-based classification framework based on new waste streams created from advanced fuel cycles. A static mass flow model, Fuel-Cycle Integration and Tradeoffs (FIT), was used to calculate the composition of waste streams resulting from different nuclear fuel cycle choices. This analysis focuses on the impact of waste form heat load on waste classification practices, although classifying by metrics of radiotoxicity, mass, and volume is also possible. The value of separation of heat-generating fission products and actinides in different fuel cycles is discussed. It was shown that the benefits of reducing the short-term fission-product heat load of waste destined for geologic disposal are neglected under the current source-based radioactive waste classification system , and that it is useful to classify waste streams based on how favorable the impact of interim storage is in increasing repository capacity.

Denia Djokic; Steven J. Piet; Layne F. Pincock; Nick R. Soelberg

2013-02-01T23:59:59.000Z

356

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

SciTech Connect (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

357

Distributed Generation Study/10 West 66th Street Corp | Open Energy  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublic Utilities Address:011-DNA Jump to:52c8ff988c1Dering Harbor,Discount Power Jump

358

INSTRUCTIONS FOR SUBMITTING NUCLEAR  

E-Print Network [OSTI]

. Decommissioning 13 I. Performance 13 J. Nuclear Fuel 14 K. Nuclear Insurance 14 L. Relicensing or Plant RetirementCALIFORNIA ENERGY COMMISSION INSTRUCTIONS FOR SUBMITTING NUCLEAR POWER PLANT-RELATED DATA of Submitted Data 3 NUCLEAR POWER PLANT DATA REQUESTS 6 A. Environmental Impacts 6 B. Spent Fuel Generation 8 C

359

A Comparative Analysis of Mestizo and Indigenous Mayan Young Women in Guatemala: Attitudes and Knowledge of Sexual Reproduction and Health among Members of Children International's Youth Health Corps  

E-Print Network [OSTI]

Children Internationalĺs Youth Health Corps Program uses Peer Education techniques to teach impoverished adolescents about Sexual Health and Reproduction. In the Youth Health Corps in Guatemala, both rural indigenous Maya ...

Trapp, Sarah Casement

2011-04-21T23:59:59.000Z

360

US Army Corps of Engineers Caribbean Islands Region Version 2.0 WETLAND DETERMINATION DATA FORM Caribbean Islands Region  

E-Print Network [OSTI]

US Army Corps of Engineers Caribbean Islands Region ┬ş Version 2.0 WETLAND DETERMINATION DATA FORM ┬ş Caribbean Islands Region Project/Site: Municipality/Town: Sampling Date: Applicant/Owner: PR or USVI or problematic. Hydrophytic Vegetation Present? Yes No Remarks: #12;US Army Corps of Engineers Caribbean Islands

US Army Corps of Engineers

Note: This page contains sample records for the topic "nuclear generation corp" 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

Upriver to Hue and Dong Ha: The U.S. Navy's War in I Corps, Vietnam 1967-1970  

E-Print Network [OSTI]

.S. Navy?s War in I Corps, Vietnam, 1967-1970. (December 2011) Jonathan Blackshear Chavanne, B.A., Baylor University; M.A., American Military University Chair of Advisory Committee: Dr. James Bradford The United States Navy?s involvement... .................................................................................................. 1 Bucklew and Vung Ro ................................................................... 7 ?More Different Types of Boats Than You Can Imagine? ............ 11 I Corps...

Chavanne, Jonathan Blackshear

2012-02-14T23:59:59.000Z

362

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...

363

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...

364

Pennsylvania Nuclear Profile - Power Plants  

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

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

365

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...

366

Iowa Nuclear Profile - Power Plants  

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

total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Duane Arnold Energy Center Unit...

367

ORNL signs agreement with Whirlpool Corp. to develop new energy...  

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

with current models. The goal of the cooperative research and development agreement, or CRADA, is to make a next-generation household refrigerator more energy efficient by using...

368

DOE Cites Safety and Ecology Corp. for Violating Nuclear Safety Rules |  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of Energy Power Systems EngineeringDepartmentSmartDepartment of1 Ingrid A.C. Kolb,DepartmentEnergy

369

DOE - Office of Legacy Management -- United Nuclear Corp - MO 0-03  

Office of Legacy Management (LM)

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

370

The Next Generation Nuclear The Next Generation Nuclear  

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

Use VHTR technology to: Use VHTR technology to: Produce electricity, and Produce electricity, and Process heat for hydrogen production and other Process heat for...

371

Planning Assistance to States U.S. ARMY CORPS OF ENGINEERS BUILDING STRONG  

E-Print Network [OSTI]

nutrient study for water quality Funding. The Planning Assistance to States program is funded annuallyPlanning Assistance to States U.S. ARMY CORPS OF ENGINEERS BUILDING STRONG® ® States, local governments and Native American Tribes often have needs in planning for water and related resources

US Army Corps of Engineers

372

MODULES UNIVERSELS DE GL3 SUR UN CORPS p-ADIQUE EN CARACTERISTIQUE p  

E-Print Network [OSTI]

MODULES UNIVERSELS DE GL3 SUR UN CORPS p-ADIQUE EN CARACT┬┤ERISTIQUE p par Rachel Ollivier & Vincent the structure of certain mod p universal modules for GL3(F) over the corresponding Hecke algebras. To this end homological coefficient systems on the the affine Bruhat-Tits building of GL3. Suppose that k has cardinality

Paris-Sud XI, Universit├ę de

373

DEPARTMENT OF THE ARMY ER 11-1-XXX U.S. Army Corps of Engineers  

E-Print Network [OSTI]

#12;DEPARTMENT OF THE ARMY ER 11-1-XXX U.S. Army Corps of Engineers CECW-EV Washington, D.C. 20314 Military Sales (FMS), and any other Federal funded programs with a total project cost of $1 million or more

US Army Corps of Engineers

374

Next Generation Nuclear Plant Phenomena  

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

Should that prove to be impractical (e.g. due to excessive heat loss in the intermediate heat transfer loop), an earthen berm separating the two plants may be a suitable...

375

Next Generation Nuclear Plant Phenomena  

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

concern that were identified and categorized as high importance combined with medium to low knowledge follow: * core coolant bypass flows (normal operation), * powerflux...

376

Next Generation Nuclear Plant Phenomena  

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

High- importance phenomena related to the RPV include crack initiation and subcritical crack growth; field fabrication process control; property control in heavy...

377

Request For Records Disposition Authority-Nuclear Weapons | Department...  

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

Authority-Nuclear Weapons Request For Records Disposition Authority-Nuclear Weapons This document identifies the nuclear weapon records generated by the Department of Energy's...

378

U.S. Army Corps of Engineers Bonneville Power Administration  

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

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched Ferromagnetism in Layeredof Energy Two2015 Tyson ResearchO P J IKerosene by7-14

379

Design and Transient Analysis of Passive Safety Cooling Systems for Advanced Nuclear Reactors  

E-Print Network [OSTI]

Advisory Committee and Generation IV International Forum.Nuclear Energy Agency The Generation IV International Forum.Technology Roadmap for Generation IV Nuclear Energy Systems.

Galvez, Cristhian

2011-01-01T23:59:59.000Z

380

Generation IV International Forum Updates Technology Roadmap...  

Office of Environmental Management (EM)

nuclear energy Generation IV International Forum Signs Agreement to Collaborate on Sodium Cooled Fast Reactors China and Russia to Join the Generation IV International Forum...

Note: This page contains sample records for the topic "nuclear generation corp" 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

Final Report Recommended Actions to Reduce Electrical Peak Loads at the Marine Corps Air Station at Camp Pendleton, California  

SciTech Connect (OSTI)

PNNL conducted a walk-through audit of Marine Corps Air Station at Camp Pendleton. The audit inspected a significant portion of the site and identified a large number of similar energy saving opportunities across all building types.

Hail, John C.; Brown, Daryl R.; McCullough, Jeffrey J.; Underhill, Ronald M.

2001-05-08T23:59:59.000Z

382

Registration of Electric Generators (Connecticut)  

Broader source: Energy.gov [DOE]

All electric generating facilities operating in the state, with the exception of hydroelectric and nuclear facilities, must obtain a certificate of registration from the Department of Public...

383

Central Heating Plant site characterization report, Marine Corps Combat Development Command, Quantico, Virginia  

SciTech Connect (OSTI)

This report presents the methodology and results of a characterization of the operation and maintenance (O M) environment at the US Marine Corps (USMC) Quantico, Virginia, Central Heating Plant (CHP). This characterization is part of a program intended to provide the O M staff with a computerized artificial intelligence (AI) decision support system that will assist the plant staff in more efficient operation of their plant. 3 refs., 12 figs.

Not Available

1990-08-01T23:59:59.000Z

384

KWIC [KWiCFinder homepage] [WebKWIC homepage] [WebCorp  

E-Print Network [OSTI]

WEB KWIC WEB WEB KWIC [KWiCFinder homepage] [WebKWIC homepage] [WebCorp homepage] WEB KWIC [ 2003] WEB IDE 32 G KWIC 350G WEB 100 2 cdb 40 KWIC WEB WEB NTCIR Web Retrieval Task 100G 1100 [Eguchi et. al 2002] WEB WEB Yahoo! Japan UNIX GNU Wget WEB html,htm txt robots.txt 3500 1 G G 1 #12;KWIC ( ) 1 40 1TB

Sekine, Satoshi

385

Marines in gray: the birth, life and death of the Confederate States Marine Corps  

E-Print Network [OSTI]

11 strategy considerations played a central role in the creation, maintenance, and employment of the South?s Marines. 12 Endnotes 1 Joseph G. Dawson, III, ?With Fidelity and Effectiveness: Archibald Henderson?s Lasting Legacy..., became increasingly valued by its parent (the Navy) and by the country at large. Capitalizing on the long tenure of its fifth Commandant, Brevet Brigadier General Archibald Henderson, the Marine Corps? operational versatility and proven performance...

Krivdo, Michael E.

2009-05-15T23:59:59.000Z

386

War dogs: the U.S. K-9 Corps in World War II  

E-Print Network [OSTI]

the Marine Corps and Coast Guard also operated dog training facilities. Almost 80 percent of the animals served as sentries in the United States and the balance in combat zones. The canines proved most effective as sentries and silent scouts but the Army... as messengers and sentries during the Civil War. Legislation was intro- Documentation follows the of Militar Histor duced in Congress in 1917 to appropriate funds "for the purchase, train- ing, and maintenance of dogs for military purposes. " The bill died...

Whatley, Donald Alan

1990-01-01T23:59:59.000Z

387

Army Corps of Engineers - Application for Department of the Army Permit |  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublic Utilities Address: 160 East 300AlgoilEnergyElectric Coop Corp Place:Armaec

388

Commercial nuclear power 1990  

SciTech Connect (OSTI)

This report presents the status at the end of 1989 and the outlook for commercial nuclear capacity and generation for all countries in the world with free market economies (FME). The report provides documentation of the US nuclear capacity and generation projections through 2030. The long-term projections of US nuclear capacity and generation are provided to the US Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) for use in estimating nuclear waste fund revenues and to aid in planning the disposal of nuclear waste. These projections also support the Energy Information Administration's annual report, Domestic Uranium Mining and Milling Industry: Viability Assessment, and are provided to the Organization for Economic Cooperation and Development. The foreign nuclear capacity projections are used by the DOE uranium enrichment program in assessing potential markets for future enrichment contracts. The two major sections of this report discuss US and foreign commercial nuclear power. The US section (Chapters 2 and 3) deals with (1) the status of nuclear power as of the end of 1989; (2) projections of nuclear capacity and generation at 5-year intervals from 1990 through 2030; and (3) a discussion of institutional and technical issues that affect nuclear power. The nuclear capacity projections are discussed in terms of two projection periods: the intermediate term through 2010 and the long term through 2030. A No New Orders case is presented for each of the projection periods, as well as Lower Reference and Upper Reference cases. 5 figs., 30 tabs.

Not Available

1990-09-28T23:59:59.000Z

389

Nuclear Energy Research Brookhaven National  

E-Print Network [OSTI]

Nuclear Energy Research Brookhaven National Laboratory William C. Horak, Chair Nuclear Science and Technology Department #12;BNL Nuclear Energy Research Brookhaven Graphite Research Reactor - 1948 National&T Department #12;Nuclear Energy Today 435 Operable Power Reactors, 12% electrical generation (100 in US, 19

Ohta, Shigemi

390

Innovative Regulatory and Technical Approaches for the U.S. Army Corp of Engineers' Linde FUSRAP Site Remediation  

SciTech Connect (OSTI)

The U.S. Department of Energy (USDOE) created the Formerly Utilized Sites Remedial Action Program (FUSRAP) in 1974 to identify, investigate, and cleanup or control radiological contamination at sites used by the Manhattan Engineer District (MED) and the Atomic Energy Commission (AEC) from the 1940s through the 1960s. The USDOE had identified 46 sites in the program and finished remediation at 24 of the smaller ones before the end of 1997. With the passage of the Energy and Water Resources Appropriation Act of 1998 the United States Army Corps of Engineers (USACE) was designated by Congress with responsibility to manage and execute the FUSRAP. The Linde Site located in Tonawanda, New York was operated by the MED from 1942-1946 to extract uranium from several high-grade ores. This natural uranium was subsequently enriched in U-235 elsewhere in the United States and ultimately used to produce energy or weapons. Though in the process of reviewing alternative disposal options by 1995, the USDOE had operated FUSRAP with a strategy requiring virtually all materials remediated be disposed of at only one Nuclear Regulatory Commission licensed facility. The change in management of the FUSRAP in 1997 allowed the disposal policy of low levels of radioactively contaminated materials found at the remaining sites to be reexamined. This paper presents some of the innovative regulatory and technical approaches employed at the Linde Site that are resulting in project cost savings while meeting applicable or relevant and appropriate requirements as well as fulfilling commitments made to the local community.

Pitts, J. T.; Coutts, P. W.; Franz, J.; Boyle, J. D.; Rogers, B. C.

2002-02-27T23:59:59.000Z

391

U.S. Marine Corps Base Camp Pendleton: Using The Sun For Hot Water And Electricity, Federal Energy Management Program (FEMP) (Fact Sheet)  

SciTech Connect (OSTI)

Case study overview of integrated solar hot water/photovoltaic systems at the U.S. Marine Corps Camp Pendleton training pools.

Not Available

2009-09-01T23:59:59.000Z

392

US Synthetic Corp (TRL 4 Component)- The Development of Open, Water Lubricated Polycrystalline Diamond Thrust Bearings for use in Marine Hydrokinetic (MHK) Energy Machines  

Broader source: Energy.gov [DOE]

US Synthetic Corp (TRL 4 Component) - The Development of Open, Water Lubricated Polycrystalline Diamond Thrust Bearings for use in Marine Hydrokinetic (MHK) Energy Machines

393

Vermont Nuclear Profile - Power Plants  

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

mwh)","Share of State nuclear net generation (percent)","Owner" "Vermont Yankee Unit 1",620,"4,782",100.0,"Entergy Nuclear Vermont Yankee" "1 Plant 1 Reactor",620,"4,782",100.0...

394

Massachusetts Nuclear Profile - Power Plants  

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

(percent)","Owner" "Pilgrim Nuclear Power Station Unit 1",685,"5,918",100.0,"Entergy Nuclear Generation Co" "1 Plant 1 Reactor",685,"5,918",100.0 "Note: Totals may not equal...

395

Nuclear Decommissioning Financing Act (Maine)  

Broader source: Energy.gov [DOE]

The Nuclear Decommissioning Financing Act calls for the establishment of a tax-exempt, tax-deductible decommissioning fund by the licensee of any nuclear power generating facility to pay for the...

396

Microsoft PowerPoint - Project Briefing for Nuclear Energy Advisory...  

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

Next Generation Nuclear Plant Next Generation Nuclear Plant . Project Briefing for . Nuclear Energy Advisory Committee uc ea e gy d so y Co ttee Greg Gibbs Director NGNP Project...

397

South Carolina Nuclear Profile - Power Plants  

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

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

398

New York Nuclear Profile - Nine Mile Point Nuclear Station  

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

Nine Mile Point Nuclear Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License...

399

Maryland Nuclear Profile - Calvert Cliffs Nuclear Power Plant  

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

Calvert Cliffs Nuclear Power Plant" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License...

400

New York Nuclear Profile - R E Ginna Nuclear Power Plant  

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

R E Ginna Nuclear Power Plant" "Unit","Summer Capacity (MW)","Net Generation (Thousand MWh)","Summer Capacity Factor (Percent)","Type","Commercial Operation Date","License...

Note: This page contains sample records for the topic "nuclear generation corp" 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

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

E-Print Network [OSTI]

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

Nero, A.V.

2010-01-01T23:59:59.000Z

402

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

E-Print Network [OSTI]

Charges Relating to Nuclear Reactor Safety," 1976, availableissues impor tant to nuclear reactor safety. This report wasstudies of overall nuclear reactor safety have been

Nero, A.V.

2010-01-01T23:59:59.000Z

403

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

E-Print Network [OSTI]

for sabotage of nuclear plants or the potential forAccidents in Large Nuclear Plants" (AEC Report, WASH-/40),YEAR FROM POTENTIAL NUCLEAR PLANT ACCIDENTS(a) Consequence

Nero, A.V.

2010-01-01T23:59:59.000Z

404

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]

Removal Equipment (nuclear plant) Turbine Building ClosedCooling Water System (nuclear plant) SteamReheater (nuclear plant) Inspection Water Induction

Nero, A.V.

2010-01-01T23:59:59.000Z

405

Targeting Net Zero Energy at Marine Corps Base Kaneohe Bay, Hawaii: Assessment and Recommendations  

SciTech Connect (OSTI)

DOD's U.S. Pacific Command has partnered with the U.S. Department of Energy's (DOE) National Renewable Energy Laboratory (NREL) to assess opportunities for increasing energy security through renewable energy and energy efficiency in Hawaii installations. NREL selected Marine Corps Base Hawaii (MCBH), Kaneohe Bay to receive technical support for net zero energy assessment and planning funded through the Hawaii Clean Energy Initiative (HCEI). NREL performed a comprehensive assessment to appraise the potential of MCBH Kaneohe Bay to achieve net zero energy status through energy efficiency, renewable energy, and electric vehicle integration. This report summarizes the results of the assessment and provides energy recommendations.

Burman, K.; Kandt, A.; Lisell, L.; Booth, S.; Walker, A.; Roberts, J.; Falcey, J.

2011-11-01T23:59:59.000Z

406

Army Corps of Engineers - Instructions for Preparing a Department of the  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 NoPublic Utilities Address: 160 East 300AlgoilEnergyElectric Coop Corp Place:ArmaecArmy Permit Application | Open

407

DOE - Office of Legacy Management -- Allegheny-Ludlum Steel Corp - NY 0-02  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou are here Home ┬╗ Sites ┬╗Allegheny-Ludlum Steel Corp

408

DOE - Office of Legacy Management -- Hydroblast Corp - IL 0-03  

Office of Legacy Management (LM)

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

409

DOE - Office of Legacy Management -- Metals Selling Corp - CT 0-01  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou are here HomeGunnison-EngineerSelling Corp - CT 0-01

410

DOE - Office of Legacy Management -- Metals and Controls Corp FSM Dept - MA  

Office of Legacy Management (LM)

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

411

Tri-State Electric Member Corp (North Carolina) | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of InspectorConcentrating SolarElectric Coop, IncTipmontInformationKentucky) JumpCorp (North Carolina) Jump

412

ProtoFlex Corp formerly Alpha Optics Inc | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia: EnergyPotentialUrbanUtilityScalePVCapacity Jump to:USGSMeanReservoirTemp JumpProterra Jump to:ProtoFlex Corp

413

The elements of nuclear power  

SciTech Connect (OSTI)

An introduction to the principles of nuclear fission power generation. Describes the physical processes which occur in a nuclear reactor and discusses the theory behind the calculations. Also covers heat transfer in reactors, thermodynamic power cycles, reactor operators, and radiation shielding. Material covered includes topics on the effects of nuclear radiation on humans, the safety of nuclear reactors and of those parts of the nuclear fuel cycle which deal with fuel element manufacture and the reprocessing of irradiated fuel.

Bennet, D.J.; Thomson, J.R.

1989-01-01T23:59:59.000Z

414

World nuclear outlook 1995  

SciTech Connect (OSTI)

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

NONE

1995-09-29T23:59:59.000Z

415

World nuclear outlook 1994  

SciTech Connect (OSTI)

As part of the EIA program to provide energy information, this analysis report presents the current status and projections through 2010 of nuclear capacity, generation, and fuel cycle requirements for all countries in the world using nuclear power to generate electricity for commercial use. It also contains information and forecasts of developments in the uranium market. Long-term projections of US nuclear capacity, generation, and spent fuel discharges for three different scenarios through 2040 are developed for the Department of Energy`s Office of Civilian Radioactive Waste Management (OCRWM). In turn, the OCRWM provides partial funding for preparation of this report. The projections of uranium requirements are provided to the Organization for Economic Cooperation and Development (OECD) for preparation of the Nuclear Energy Agency/OECD report, Summary of Nuclear Power and Fuel Cycle Data in OECD Member Countries.

NONE

1994-12-01T23:59:59.000Z

416

Future Prospects for Nuclear Power after Fukushima  

E-Print Network [OSTI]

at the FukushimaDaiichi nuclear power plant in Japan has changed the perception of nuclear as a safe energy sourceFuture Prospects for Nuclear Power after Fukushima Nuclear is a highintensity energy source as the next generation of Light Water Reactors. We will also discuss the future prospects of nuclear power

Goldberg, Bennett

417

Comments of the Independent Peer-Review Team for the Arid West Regional Supplement to the 1987 Corps of Engineers Wetlands Delineation  

E-Print Network [OSTI]

Corps of Engineers Wetlands Delineation Manual, and Responses by the Corps of Engineers and Arid West are still very active in professional wetland delineation work which would have clarified original intent. "Further, the Working Group and contributors" included NO private sector wetland scientists much less ones

US Army Corps of Engineers

418

State Nuclear Profiles 2010  

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

60 Vermont Vermont total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 620 55.0 4,782 72.2 Hydro and Pumped Storage 324 28.7 1,347...

419

Missouri Nuclear Profile - Power Plants  

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

total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Callaway Unit 1","1,190","8,996",100.0,"Union...

420

Mississippi Nuclear Profile - Power Plants  

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

total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Grand Gulf Unit 1","1,251","9,643",100.0,"Syste...

Note: This page contains sample records for the topic "nuclear generation corp" 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

Absolute nuclear material assay  

DOE Patents [OSTI]

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

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

2012-05-15T23:59:59.000Z

422

ORDNANCE CORPS  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou$0.C. 20545 OCT 28 1% - :NEW; I.-'7-TAC~$,. ' e' ,id

423

Nuclear Instruments and Methods in Physics Research A 562 (2006) 401406 Generating a multi-line neutron beam using an electron  

E-Print Network [OSTI]

Polytechnic Institute, Troy, New York 12180, USA Received 3 January 2006; received in revised form 20 February discrete energy lines in the range 34┬ş6200 eV is produced by using a 238 U filter in conjunction beams of discrete energies can be generated by using an electron linear accelerator in combination

Danon, Yaron

424

DIAGNOSTIC D'UN FAISCEAU DE PLASMA AUTOUR D'UN CORPS POSITIF ET APPLICATION A LA SONDE DE SAYERS  

E-Print Network [OSTI]

341 DIAGNOSTIC D'UN FAISCEAU DE PLASMA AUTOUR D'UN CORPS POSITIF ET APPLICATION A LA SONDE DE par rapport au potentiel plasma. Entre les grilles est appliqu├ęe une tension alternative de pulsation cons- tante m sup├ęrieure ├á la pulsation plasma cop. La mesure du courant entre les grilles fournit la

Boyer, Edmond

425

MARCH 2007 IEEE Robotics & Automation Magazine 351070-9932/07/$25.002007 IEEE iSWOOP, COREL CORP.  

E-Print Network [OSTI]

MARCH 2007 IEEE Robotics & Automation Magazine 351070-9932/07/$25.00┬ę2007 IEEE ┬ę iSWOOP, COREL CORP. S ocially intelligent robotics is the pursuit of creating robots capable of exhibiting natur- al on the use of the robot's physical embodiment to communicate and interact with users in a social and engaging

Paris-Sud XI, Universit├ę de

426

H:/fctshts/rad_fs.ppt U.S. Army Corps of Engineers Buffalo District April, 1998  

E-Print Network [OSTI]

exposure to ionizing radiation cannot be avoided. Exposures can be natural or man-made. Natural sources include cosmic rays and naturally-occurring radionuclides in the earth and air, and are consideredH:/fctshts/rad_fs.ppt Fact Sheet Radiation U.S. Army Corps of Engineers ┬ĚBuffalo District ┬ĚApril

US Army Corps of Engineers

427

Report of the Independent Scientific Advisory Board Review of the U.S. Army Corps of Engineers'  

E-Print Network [OSTI]

Report of the Independent Scientific Advisory Board Review of the U.S. Army Corps of Engineers Report 99-4 February 16, 1999 #12;ISAB Report 99-4, Page 1 February 16, 1999 CONTENTS CONTENTS .............................................................................................. 10 PURPOSE OF THE REPORT

428

U.S. ARMY CORPS OF ENGINEERS HURRICANE SANDY COASTAL MANAGEMENT DIVISION 130 Wainwright Dr. Fort Hamilton, NY 11209  

E-Print Network [OSTI]

future sea level rise and climate change scenarios, to reduce risk to vulnerable population, property August 2013 U.S. ARMY CORPS OF ENGINEERS BUILDING STRONG® The North Atlantic Coast Comprehensive Study will identify existing green/nature-based infrastructure, include an evaluation of the performance of green

US Army Corps of Engineers

429

METHODOLOGIES FOR REVIEW OF THE HEALTH AND SAFETY ASPECTS OF PROPOSED NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL SITES AND FACILITIES. VOLUME 9 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network [OSTI]

emergencies, Le. , accidents at nuclear facilities, there isas a result of nuclear accidents; these are the Protectiveassociated with a nuclear accident is of greater importance

Nero, A.V.

2010-01-01T23:59:59.000Z

430

applied nuclear research: Topics by E-print Network  

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

2011-01-01 2 he students, faculty, and research staff of the MIT Department of Nuclear Science and Engineering (NSE) generate, control, and apply nuclear Environmental Sciences...

431

National Nuclear Data Center Nuclear Data Portal www.nndc.bnl.gov  

E-Print Network [OSTI]

National Nuclear Data Center #12;Nuclear Data Portal www.nndc.bnl.gov Nuclear Data Portal New generation of nuclear data services, using modern and powerful DELL servers, Sybase relational database software, Linux operating system, and Java programming language. The Portal includes nuclear structure

Ohta, Shigemi

432

Targeting Net Zero Energy at Marine Corps Base Hawaii, Kaneohe Bay: Preprint  

SciTech Connect (OSTI)

This paper summarizes the results of an NREL assessment of Marine Corps Base Hawaii (MCBH), Kaneohe Bay to appraise the potential of achieving net zero energy status through energy efficiency, renewable energy, and hydrogen vehicle integration. In 2008, the U.S. Department of Defense's U.S. Pacific Command partnered with the U.S. Department of Energy's (DOE's) National Renewable Energy Laboratory (NREL) to assess opportunities for increasing energy security through renewable energy and energy efficiency at Hawaii military installations. DOE selected Marine Corps Base Hawaii (MCBH), Kaneohe Bay, to receive technical support for net zero energy assessment and planning funded through the Hawaii Clean Energy Initiative (HCEI). NREL performed a comprehensive assessment to appraise the potential of MCBH Kaneohe Bay to achieve net zero energy status through energy efficiency, renewable energy, and hydrogen vehicle integration. This paper summarizes the results of the assessment and provides energy recommendations. The analysis shows that MCBH Kaneohe Bay has the potential to make significant progress toward becoming a net zero installation. Wind, solar photovoltaics, solar hot water, and hydrogen production were assessed, as well as energy efficiency technologies. Deploying wind turbines is the most cost-effective energy production measure. If the identified energy projects and savings measures are implemented, the base will achieve a 96% site Btu reduction and a 99% source Btu reduction. Using excess wind and solar energy to produce hydrogen for a fleet and fuel cells could significantly reduce energy use and potentially bring MCBH Kaneohe Bay to net zero. Further analysis with an environmental impact and interconnection study will need to be completed. By achieving net zero status, the base will set an example for other military installations, provide environmental benefits, reduce costs, increase energy security, and exceed its energy goals and mandates.

Burman, K.; Kandt, A.; Lisell, L.; Booth, S.

2012-05-01T23:59:59.000Z

433

Diophantine Generation,  

E-Print Network [OSTI]

Diophantine Generation, Horizontal and Vertical Problems, and the Weak Vertical Method Alexandra Shlapentokh Diophantine Sets, Definitions and Generation Diophantine Sets Diophantine Generation Properties of Diophantine Generation Diophantine Family of Z Diophantine Family of a Polynomial Ring Going Down Horizontal

Shlapentokh, Alexandra

434

Steam generator support system  

DOE Patents [OSTI]

A support system for connection to an outer surface of a J-shaped steam generator for use with a nuclear reactor or other liquid metal cooled power source is disclosed. The J-shaped steam generator is mounted with the bent portion at the bottom. An arrangement of elongated rod members provides both horizontal and vertical support for the steam generator. The rod members are interconnected to the steam generator assembly and a support structure in a manner which provides for thermal distortion of the steam generator without the transfer of bending moments to the support structure and in a like manner substantially minimizes forces being transferred between the support structure and the steam generator as a result of seismic disturbances. 4 figs.

Moldenhauer, J.E.

1987-08-25T23:59:59.000Z

435

Steam generator support system  

DOE Patents [OSTI]

A support system for connection to an outer surface of a J-shaped steam generator for use with a nuclear reactor or other liquid metal cooled power source. The J-shaped steam generator is mounted with the bent portion at the bottom. An arrangement of elongated rod members provides both horizontal and vertical support for the steam generator. The rod members are interconnected to the steam generator assembly and a support structure in a manner which provides for thermal distortion of the steam generator without the transfer of bending moments to the support structure and in a like manner substantially minimizes forces being transferred between the support structure and the steam generator as a result of seismic disturbances.

Moldenhauer, James E. (Simi Valley, CA)

1987-01-01T23:59:59.000Z

436

Ashland oil, Inc. v. Sonford Products Corp., Kelley v. Tiscornia, and United States v. Fleet Factors Corp.: Upholding EPA`s lender liability rule  

SciTech Connect (OSTI)

John Grisham`s novel The Firm relates the story of Mitchell McDeere, a young law school graduate who believes that he is joining a {open_quotes}white shoe{close_quotes} Memphis, Tennessee, firm but discovers that the firm is controlled by the Mob. A similar, but different, {open_quotes}surprise{close_quotes} has befallen banks as a result of toxic waste cleanup cost claims. When the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA or Superfund) was passed in 1980, banks had no cause for alarm because the Act provided an exemption from its ownership-based liability for any lender holding {open_quotes}indicia of ownership primarily to protect his security interest{close_quotes} in a hazardous waste facility. Based on the statutory language, it seemed reasonably clear that Congress did not intend to impose liability on secured creditors merely for securing a debt with a deed of trust or mortgage. Unfortunately, lender liability for CERCLA claims arose in the mid-1980s out of two lower federal court decisions and the Eleventh Circuit`s controversial, to say the least, 1990 decision in United States v. Fleet Factors Corp (Fleet Factors II). The major issues currently confronting lenders under CERCLA are (1) the extent to which a secured creditor may involve itself in the debtor`s operations, especially during a loan workout program, without becoming liable for cleanup costs as a CERCLA {open_quotes}owner or operator{close_quotes} and (2) whether a lender who forecloses on collateral and takes title is liable under CERCLA. 94 refs.

Evans, W.D. Jr. [San Francisco`s Graham & James, Washington, DC (United States)

1993-12-31T23:59:59.000Z

437

Temperature & Nuclear Fusion 4 October 2011  

E-Print Network [OSTI]

Temperature & Nuclear Fusion 4 October 2011 Goals ┬Ě Review temperature in stars ┬Ě Practice using the important energy scales for nuclear fusion Temperature 1. For each relation we regularly use in class-Boltzmann equation: L = 4R2 T4 . (d) In fusion energy generation: T . #12;temperature & nuclear fusion 2 Nuclear

Militzer, Burkhard

438

Nuclear Resonance Fluorescence for Nuclear Materials Assay  

E-Print Network [OSTI]

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

Quiter, Brian Joseph

2010-01-01T23:59:59.000Z

439

PROGRESS TOWARDS NEXT GENERATION, WAVEFORM BASED THREE-DIMENSIONAL MODELS AND METRICS TO IMPROVE NUCLEAR EXPLOSION MONITORING IN THE MIDDLE EAST  

SciTech Connect (OSTI)

Efforts to update current wave speed models of the Middle East require a thoroughly tested database of sources and recordings. Recordings of seismic waves traversing the region from Tibet to the Red Sea will be the principal metric in guiding improvements to the current wave speed model. Precise characterizations of the earthquakes, specifically depths and faulting mechanisms, are essential to avoid mapping source errors into the refined wave speed model. Errors associated with the source are manifested in amplitude and phase changes. Source depths and paths near nodal planes are particularly error prone as small changes may severely affect the resulting wavefield. Once sources are quantified, regions requiring refinement will be highlighted using adjoint tomography methods based on spectral element simulations [Komatitsch and Tromp (1999)]. An initial database of 250 regional Middle Eastern events from 1990-2007, was inverted for depth and focal mechanism using teleseismic arrivals [Kikuchi and Kanamori (1982)] and regional surface and body waves [Zhao and Helmberger (1994)]. From this initial database, we reinterpreted a large, well recorded subset of 201 events through a direct comparison between data and synthetics based upon a centroid moment tensor inversion [Liu et al. (2004)]. Evaluation was done using both a 1D reference model [Dziewonski and Anderson (1981)] at periods greater than 80 seconds and a 3D model [Kustowski et al. (2008)] at periods of 25 seconds and longer. The final source reinterpretations will be within the 3D model, as this is the initial starting point for the adjoint tomography. Transitioning from a 1D to 3D wave speed model shows dramatic improvements when comparisons are done at shorter periods, (25 s). Synthetics from the 1D model were created through mode summations while those from the 3D simulations were created using the spectral element method. To further assess errors in source depth and focal mechanism, comparisons between the three methods were made. These comparisons help to identify problematic stations and sources which may bias the final solution. Estimates of standard errors were generated for each event's source depth and focal mechanism to identify poorly constrained events. A final, well characterized set of sources and stations will be then used to iteratively improve the wave speed model of the Middle East. After a few iterations during the adjoint inversion process, the sources will be reexamined and relocated to further reduce mapping of source errors into structural features. Finally, efforts continue in developing the infrastructure required to 'quickly' generate event kernels at the n-th iteration and invert for a new, (n+1)-th, wave speed model of the Middle East. While development of the infrastructure proceeds, initial tests using a limited number of events shows the 3D model, while showing vast improvement compared to the 1D model, still requires substantial modifications. Employing our new, full source set and iterating the adjoint inversions at successively shorter periods will lead to significant changes and refined wave speed structures of the Middle East.

Savage, B; Peter, D; Covellone, B; Rodgers, A; Tromp, J

2009-07-02T23:59:59.000Z

440

An extremely radioresistant green eukaryote for radionuclide bio-decontamination in the nuclear  

E-Print Network [OSTI]

of adaptation to extreme environments. Introduction Nuclear energy technologies generate radioactiveAn extremely radioresistant green eukaryote for radionuclide bio-decontamination in the nuclear Blignyabcd Nuclear activities generate radioactive elements which require processes for their decontamination

Boyer, Edmond

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


441

Construction or Extended Operation of Nuclear Plant (Vermont)  

Broader source: Energy.gov [DOE]

Any petition for approval of construction of a nuclear energy generating plant within the state, or any petition for approval of the operation of a nuclear energy generating plant beyond the date...

442

Nuclear Nonproliferation  

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

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

443

Nuclear Engineering Nuclear Criticality Safety  

E-Print Network [OSTI]

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

Kemner, Ken

444

1. Generation 1 1. Generation  

E-Print Network [OSTI]

1. Generation 1 _________________________________________________________________________ 1. Generation Sound and vibrations or, in more general terms, oscillations of matter (solids or fluids) are generated in many different dynamic processes. The basic mechanisms which underlie these oscillations

Berlin,Technische Universit├Ąt

445

Nuclear Physics  

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

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

446

Nuclear Energy  

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

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

447

Targeting Net Zero Energy at Marine Corps Air Station Miramar: Assessment and Recommendations  

SciTech Connect (OSTI)

The U.S. Department of Defense (DoD) is the largest energy consumer in the U.S. government. Present energy use impacts DoD global operations by constraining freedom of action and self-sufficiency, demanding enormous economic resources, and putting many lives at risk in logistics support for deployed environments. There are many opportunities for DoD to more effectively meet energy requirements through a combination of human actions, energy efficiency technologies, and renewable energy resources. In 2008, a joint initiative was formed between DoD and the U.S. Department of Energy (DOE) to address military energy use. This initiative created a task force comprised of representatives from each branch of the military, the Office of the Secretary of Defense (OSD), the Federal Energy Management Program (FEMP), and the National Renewable Energy Laboratory (NREL) to examine the potential for ultra high efficiency military installations. This report presents an assessment of Marine Corps Air Station (MCAS) Miramar, selected by the task force as the initial prototype installation based on its strong history of energy advocacy and extensive track record of successful energy projects.

Booth, S.; Barnett, J.; Burman, K.; Hambrick, J.; Helwig, M.; Westby, R.

2010-12-01T23:59:59.000Z

448

OXY (Occidental Petroleum Corp. ) units plan U. K. work worth $1. 5 billion  

SciTech Connect (OSTI)

Occidental Refineries Ltd., an Occidental Petroleum Corp. subsidiary, plans to spend about $500,000 to build a 60,000 bbl/day hydrocracker on Canvey Island near London to produce aviation fuel, naphtha, and gasoline. Occidental hopes to deflect criticism by environmentalists, concerned about the concentration of petroleum facilities in the area, by installing a minimum amount of LPG storage and not using hydrogen sulfide on the site. During the 1970's, Occidental had prepared the site for the construction of a 125,000 bbl/day refinery, plans for which were scrapped after the demand for product compounds decreased. Occidental Chemical Co., another Occidental Petroleum subsidiary, plans to spend about $500,000 to build a 300,000 ton/yr ethylene plant at Peterhead, Scotl. The cracker would take part of the output from the de-ethanizer at the St. Fergus terminal for the proposed U.K. gas-gathering pipeline. Both projects would require about 3-4 yr to complete. Esso Chemical Ltd. will build a 550,000 ton/yr ethylene plant near the Mossmoran gas liquids plant in Fife, Scotl.

Not Available

1980-09-15T23:59:59.000Z

449

Nuclear Waste and the Distant Future Nuclear Waste and the Distant Future  

E-Print Network [OSTI]

Nuclear Waste and the Distant Future 1 Nuclear Waste and the Distant Future PER F. PETERSON WILLIAM://www.issues.org/22.4/peterson.html Regulation of nuclear hazards must be consistent with rules governing other of the radioactive material generated by nuclear energy decays away over short times ranging from minutes to several

Kammen, Daniel M.

450

Radioactive target needs for nuclear reactor physics and nuclear astrophysics , G. Barreau1  

E-Print Network [OSTI]

Radioactive target needs for nuclear reactor physics and nuclear astrophysics B.Jurado1* , G Gradignan, France 2 IPN, CNRS/IN2P3, Univ. Paris-Sud, 91405 Orsay, France Abstract: Nuclear reaction cross sections of short-lived nuclei are key inputs for new generation nuclear reactor simulations and for models

Boyer, Edmond

451

E-Print Network 3.0 - army veterinary corps Sample Search Results  

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

our Biology graduates over the last Summary: in the US Army Medical Technologists Middle School Science Teachers... Nuclear Medical Technologists Optometrists Park...

452

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]

nuclear, geothermal, and fossil-fuel power plants. However,power plants, which are reviewed and licensed by the Nuclear Regulatory Commission (NRC), and relatively few areas of geothermal and

Nero, A.V.

2010-01-01T23:59:59.000Z

453

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

E-Print Network [OSTI]

Nuclear Power Reactors PROTECTION AGAINST SABOTAGE Protection Against Industrial Sabotage I1C-4 Decominarion and Decommissioning

Nero, A.V.

2010-01-01T23:59:59.000Z

454

Nuclear Matter and Nuclear Dynamics  

E-Print Network [OSTI]

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

M Colonna

2009-02-26T23:59:59.000Z

455

Reporting of Nuclear Incidents (Connecticut)  

Broader source: Energy.gov [DOE]

Each operator of a nuclear power generating facility shall notify the Commissioner of Environmental Protection or his designee, which may be another State Agency, as soon as possible but in all...

456

New Hampshire Nuclear Profile - Power Plants  

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

total reactors","Summer capacity (nw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Seabrook Unit 1","1,247","10,910",100.0,"NextEr...

457

Changes in the Economic Value of Variable Generation at High Penetration Levels: A Pilot Case Study of California  

E-Print Network [OSTI]

the small amount of incumbent coal generation, and increasedamount of incumbent coal generation is also displaced by VG.including incumbent coal and nuclear generation. Expanding

Mills, Andrew

2013-01-01T23:59:59.000Z

458

State Nuclear Profiles 2010  

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

Pennsylvania total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 9,540 20.9 77,828 33.9 Coal 18,481 40.6 110,369 48.0 Hydro and...

459

State Nuclear Profiles 2010  

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

5 Maryland Maryland total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 1,705 13.6 13,994 32.1 Coal 4,886 39.0 23,668 54.3 Hydro and...

460

State Nuclear Profiles 2010  

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

5 Iowa Iowa total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 601 4.1 4,451 7.7 Coal 6,956 47.7 41,283 71.8 Hydro and Pumped Storage...

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


461

State Nuclear Profiles 2010  

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

8 Virginia Virginia total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 3,501 14.5 26,572 36.4 Coal 5,868 24.3 25,459 34.9 Hydro and...

462

State Nuclear Profiles 2010  

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

Wisconsin Wisconsin total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 1,584 8.9 13,281 20.7 Coal 8,063 45.2 40,169 62.5 Hydro and...

463

State Nuclear Profiles 2010  

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

7 Illinois Illinois total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 11,441 25.9 96,190 47.8 Coal 15,551 35.2 93,611 46.5 Hydro and...

464

State Nuclear Profiles 2010  

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

Arkansas Arkansas total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 1,835 11.5 15,023 24.6 Coal 4,535 28.4 28,152 46.2 Hydro and...

465

State Nuclear Profiles 2010  

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

Minnesota Minnesota total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 1,594 10.8 13,478 25.1 Coal 4,789 32.5 28,083 52.3 Hydro and...

466

State Nuclear Profiles 2010  

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

South Carolina total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 6,486 27.0 51,988 49.9 Coal 7,230 30.1 37,671 36.2 Hydro and...

467

State Nuclear Profiles 2010  

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

North Carolina total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 4,958 17.9 40,740 31.7 Coal 12,766 46.1 71,951 55.9 Hydro and...

468

State Nuclear Profiles 2010  

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

New Hampshire total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 1,247 29.8 10,910 49.2 Coal 546 13.1 3,083 13.9 Hydro and...

469

State Nuclear Profiles 2010  

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

7 Nebraska Nebraska total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 1,245 15.8 11,054 30.2 Coal 3,932 50.0 23,363 63.8 Hydro and...

470

State Nuclear Profiles 2010  

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

Alabama Alabama total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 5,043 15.6 37,941 24.9 Coal 11,441 35.3 63,050 41.4 Hydro and...

471

State Nuclear Profiles 2010  

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

Connecticut total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 2,103 25.4 16,750 50.2 Coal 564 6.8 2,604 7.8 Hydro and Pumped...

472

State Nuclear Profiles 2010  

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

3 Georgia Georgia total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 4,061 11.1 33,512 24.4 Coal 13,230 36.1 73,298 53.3 Hydro and...

473

State Nuclear Profiles 2010  

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

Arizona Arizona Total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 3,937 14.9 31,200 27.9 Coal 6,233 23.6 43,644 39.1 Hydro and...

474

State Nuclear Profiles 2010  

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

Massachusetts total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 685 5.0 5,918 13.8 Coal 1,669 12.2 8,306 19.4 Hydro and Pumped...

475

State Nuclear Profiles 2010  

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

Tennessee Tennessee total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 3,401 15.9 27,739 33.7 Coal 8,805 41.1 43,670 53.0 Hydro and...

476

State Nuclear Profiles 2010  

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

3 New York New York total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 5,271 13.4 41,870 30.6 Coal 2,781 7.1 13,583 9.9 Hydro and...

477

State Nuclear Profiles 2010  

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

7 Michigan Michigan total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 3,947 13.2 29,625 26.6 Coal 11,531 38.7 65,604 58.8 Hydro and...

478

State Nuclear Profiles 2010  

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

1 Missouri Missouri total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 1,190 5.5 8,996 9.7 Coal 12,070 55.5 75,047 81.3 Hydro and...

479

State Nuclear Profiles 2010  

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

6 Texas Texas total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 4,966 4.6 41,335 10.0 Coal 22,335 20.6 150,173 36.5 Hydro and Pumped...

480

State Nuclear Profiles 2010  

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

California total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 4,390 6.5 32,201 15.8 Coal 374 0.6 2,100 1.0 Hydro and Pumped...

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481

State Nuclear Profiles 2010  

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

1 Florida Florida total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 3,924 6.6 23,936 10.4 Coal 9,975 16.9 59,897 26.1 Hydro and...

482

State Nuclear Profiles 2010  

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

Louisiana Louisiana total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 2,142 8.0 18,639 18.1 Coal 3,417 12.8 23,924 23.3 Hydro and...

483

State Nuclear Profiles 2010  

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

6 Ohio Ohio total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 2,134 6.5 15,805 11.0 Coal 21,360 64.6 117,828 82.1 Hydro and Pumped...

484

Quality site seasonal report, Tucson Job Corps Center, SFBP (Solar in Federal Buildings Program) 1751, November 1984 through July 1985  

SciTech Connect (OSTI)

The active solar Domestic Hot Water (DHW) system at the Tucson Job Corps Center was designed and constructed as part of the Solar in Federal Buildings Program (SFBP). This retrofitted system is one of eight of the systems in the SFBP selected for quality monitoring. The purpose of this monitoring effort is to document the performance of quality state-of-the-art solar systems in large Federal buildings. The systems are unique prototypes. Design errors and system faults discovered during the monitoring period could not always be corrected. Therefore, the aggregated overall performance is often considerably below what might be expected had similar systems been constructed consecutively with each repetition incorporating corrections and improvements. The solar collector system is installed on a two story dormitory at the Job Corps Center. The solar system preheats hot water for about two hundred students. The solar system provided about 50% of the energy needed for water heating in the winter and nearly 100% of the water heating needs in the summer. There are about 70,000 gallons of water used per month. There are seventy-nine L.O.F. panels or 1659 square feet of collectors (1764 square feet before freeze damage occurred) mounted in two rows on the south facing roof. Collected solar energy is stored in the 2200-gallon storage tank. The control system is by Johnson Controls. City water is piped directly to the storage tank and is circulated in the collectors. Freeze protection is provided by recirculation of storage water. There is an auxiliary gas fired boiler and 750 gallon DHW storage tank to provide backup for the solar system. Highlights of the performance monitoring from the solar collection system at the Tucson Job Corps Center during the November 1984 through July 1985 monitoring period are presented in this report.

Logee, T.L.

1987-10-15T23:59:59.000Z

485

A review of "A Court in Exile: The Stuarts in France, 1689-1718" by Edward Corp.  

E-Print Network [OSTI]

of History at the University of Toulouse. In addition to producing an impressive array of ar- ticles, Corp has curated and written the catalogs of two major exhibitions, La Cour des Stuarts ? Saint-Germain-en-Laye au temps de Louis XIV (1992) and The King... of Saint- Germain. In Chapter 1, Edward Gregg provides a detailed account of the activities of the exiled Stuarts from the Revolution of 1688-89 to the Treaty of Utrecht in 1713. He suggests that James II and Louis XIV were not friends until after...

Molly McClain

2004-01-01T23:59:59.000Z

486

Nuclear Energy Governance and the Politics of Social Justice: Technology, Public Goods, and Redistribution in Russia and France  

E-Print Network [OSTI]

Energy Policy, Vol. 34 Generation IV International Forum. ôIntroduction to Generation IV Nuclear Energy Systems and theIII Plus 2030-onward ľ Generation IV 2030-onward 2030-onward

Grigoriadis, Theocharis N

2009-01-01T23:59:59.000Z

487

Distributed Generation  

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

come a long way in addressing interconnection standards for distributed generation, utilities have largely overlooked the untapped potential of these resources. Under certain...

488

Nuclear Engineer (Nuclear Safety Specialist)  

Broader source: Energy.gov [DOE]

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

489

Generation-IV Roadmap Report of the Fuel Cycle Crosscut Group...  

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

Charter of the Generation IV Roadmap Fuel Cycle Crosscut Group (FCCG) is to (1) examine the fuel cycle implications for alternative nuclear power scenarios in terms of Generation...

490

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]

generate steam to drive a steam turbine, giving rise to theValves and Pi~ing STEAM TURBINE COMPONENT OUTAGE CAUSESbasically of a steam-driven turbine, an electric generator

Nero, A.V.

2010-01-01T23:59:59.000Z

491

ARMY, MARINE CORPS, NAVY, AIR FORCE MULTI-SERVICE TACTICS, TECHNIQUES, AND PROCEDURES  

E-Print Network [OSTI]

) environment. It is the intent of this document to inform the combatant commanders (CCDRs), joint force environment. On future battlefields, failure to properly plan and execute CBRN defensive operations may result, BIOLOGICAL, RADIOLOGICAL, AND NUCLEAR ENVIRONMENT FM 4-02.7 MCRP 4-11.1F NTTP 4-02.7 AFTTP 3-42.3 JULY 2009

US Army Corps of Engineers

492

Thermoelectric Generators 1. Thermoelectric generator  

E-Print Network [OSTI]

. Cold Hot I - -- - - - - -- Figure 1 Electron concentration in a thermoelectric material. #12;2 A large1 Thermoelectric Generators HoSung Lee 1. Thermoelectric generator 1.1 Basic Equations In 1821 on the direction of current and material [3]. This is called the Thomson effect (or Thomson heat). These three

Lee, Ho Sung

493

www.inl.gov A Future of Nuclear Energy  

E-Print Network [OSTI]

www.inl.gov A Future of Nuclear Energy: The Nuclear Renaissance, the Role of INL, and Potential in Nuclear Energy ┬Ě Electrical Generation Supply/Demand ┬Ě Global Warming, Greenhouse Gas Emissions/kilowatt-hour) Facts regarding nuclear energy in the US #12;┬Ě Standardized designs based on modularization producing

494

Identification of nuclear weapons  

DOE Patents [OSTI]

A method and apparatus for non-invasively indentifying different types of nuclear weapons is disclosed. A neutron generator is placed against the weapon to generate a stream of neutrons causing fissioning within the weapon. A first detects the generation of the neutrons and produces a signal indicative thereof. A second particle detector located on the opposite side of the weapon detects the fission particles and produces signals indicative thereof. The signals are converted into a detected pattern and a computer compares the detected pattern with known patterns of weapons and indicates which known weapon has a substantially similar pattern. Either a time distribution pattern or noise analysis pattern, or both, is used. Gamma-neutron discrimination and a third particle detector for fission particles adjacent the second particle detector are preferably used. The neutrons are generated by either a decay neutron source or a pulled neutron particle accelerator.

Mihalczo, J.T.; King, W.T.

1987-04-10T23:59:59.000Z

495

U.S. ARMY CORPS OF ENGINEERS HEADQUARTERS 441 G. Street, N.W., Washington, D.C. 20314-1000  

E-Print Network [OSTI]

variety of activities such as mooring buoys, residential developments, utility lines, road crossings energy. Concurrent with the Federal Register notice, districts issued local public notices to solicit, and are informed by extensive feedback from the public and key stakeholders. The Corps is reissuing 48 permits

US Army Corps of Engineers

496

design and development. The Corps is striving to be a leader in the sustainability movement, building to the USGBC Leadership in Energy and Environmental Design  

E-Print Network [OSTI]

design and development. The Corps is striving to be a leader in the sustainability movement and development in the areas of infrastructure and environmental sustainability. This regularly leads to new the principles of sustainable design and development in all engineering and construction activities to minimize

US Army Corps of Engineers

497

Hybrid Al/SiC Composite Optics for IFE Applications W. Kowbel, MER Corp., Tucson, AZ And M. Tillack, UCSD, La Jolla, CA  

E-Print Network [OSTI]

Hybrid Al/SiC Composite Optics for IFE Applications W. Kowbel, MER Corp., Tucson, AZ And M. Tillack support of the mirror is a SiC composite. The SiC composite is chosen for the following reasons: 1) VeryC-SiC composite. Subsequently, either CVD or PVD Si is deposited as the optical quality layer. The Si coating

Tillack, Mark

498

S. Guha, J. Yang, A. Banerjee, K. Hoffman, S. Sugiyama, and J. Call United Solar Systems Corp., Troy, Michigan 48084 USA  

E-Print Network [OSTI]

Conversion Devices, Inc., Troy, Michigan 48084 USA spectral-splitting, triple-junction a-S alloy solar cellS. Guha, J. Yang, A. Banerjee, K. Hoffman, S. Sugiyama, and J. Call United Solar Systems Corp., Troy, Michigan 48084 USA S. J. Jones, X. Deng, J. Doehler, M. lzu, and H. 6. Ovshinsky Energy

Deng, Xunming

499

Nuclear Counterterrorism  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

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

2013-08-26T23:59:59.000Z

500

NYPA, Entergy begin nuclear management services plan  

SciTech Connect (OSTI)

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

NONE

1996-10-01T23:59:59.000Z