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Note: This page contains sample records for the topic "nuclear generation hydroelectric" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
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We encourage you to perform a real-time search of NLEBeta
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1

Microsoft PowerPoint - AECC Hydroelectric Generation 2010.pptx  

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

Electric Cooperative Corporation Cooperative Corporation AECC H d l i AECC Hydroelectric Generation Facilities Generation Facilities Arkansas Electric Cooperative Corporation...

2

Grid-Connected Renewable Energy Generation Toolkit-Hydroelectric | Open  

Open Energy Info (EERE)

Grid-Connected Renewable Energy Generation Toolkit-Hydroelectric Grid-Connected Renewable Energy Generation Toolkit-Hydroelectric Jump to: navigation, search Tool Summary Name: Grid-Connected Renewable Energy Generation Toolkit-Hydroelectric Agency/Company /Organization: United States Agency for International Development Sector: Energy Resource Type: Training materials Website: www.energytoolbox.org/gcre/mod_4/index.shtml Grid-Connected Renewable Energy Generation Toolkit-Hydroelectric Screenshot References: Grid-Connected Renewable Energy Generation Toolkit-Hydroelectric[1] Logo: Grid-Connected Renewable Energy Generation Toolkit-Hydroelectric GCREhydro.JPG References ↑ "Grid-Connected Renewable Energy Generation Toolkit-Hydroelectric" Retrieved from "http://en.openei.org/w/index.php?title=Grid-Connected_Renewable_Energy_Generation_Toolkit-Hydroelectric&oldid=375082

3

Electromagnetic Analysis of Rotating Permanent Magnet Exciters for Hydroelectric Generators.  

E-Print Network (OSTI)

??The purpose of this project is to analyse different design possibilities for a rotating permanent magnet exciter for a hydroelectric generator. This is done through… (more)

Nöland, Jonas

2013-01-01T23:59:59.000Z

4

Design of MIDA, a Web-Based Diagnostic Application for Hydroelectric Generators  

Science Conference Proceedings (OSTI)

Up to 95% of Hydro-Québec’s electrical power is produced by hydroelectric generators. The remainder comes from conventional thermal and nuclear generators and wind turbines. Implementing a cost-effective general maintenance program for generators ... Keywords: evolutionary prototyping, software development methodology, object-oriented prototyping tool

Luc Vouligny; Claude Hudon; Duc Ngoc Nguyen

2009-08-01T23:59:59.000Z

5

Market Offering Strategies for Hydroelectric Generators  

Science Conference Proceedings (OSTI)

This paper considers the problem of offering electricity produced by a series of hydroelectric reservoirs to a pool-type central market. The market model is a simplified version of the New Zealand wholesale electricity market, with prices modelled by ... Keywords: Dynamic programming: finite state, markov, Natural resources: energy, water resources, Probability: markov processes

G. Pritchard; G. Zakeri

2003-07-01T23:59:59.000Z

6

The frequency that wouldn't die hydroelectric generators  

Science Conference Proceedings (OSTI)

North America's Niagara River is the site of operating 25 hertz hydroelectric generators that date to the dawn of the electrical age. The reasons why 25 Hz was chosen for such a large block of power and why that obsolete frequency has lived on for the ...

R. D. Barnett

1990-10-01T23:59:59.000Z

7

Microsoft PowerPoint - AECC Hydroelectric Generation 2010.pptx  

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

Electric Electric Cooperative Corporation Cooperative Corporation AECC H d l i AECC Hydroelectric Generation Facilities Generation Facilities Arkansas Electric Cooperative Corporation Cooperative Corporation * Generation and Transmission Cooperative headquartered in Little Rock * Wholesale power provider for 16 distribution cooperatives * Serves about 62% of Arkansas with over 400,000 consumers O b 2 600 MW f i 12 * Owns about 2,600 MW of generation at 12 different facilities. Arkansas Electric Cooperative Corporation Cooperative Corporation 2009 G i b S f A CC 2009 Generation by Energy Source for AECC Owned and Co-Owned Plants * Natural Gas and Oil 4.0% * Wyoming Coal 88.8% * Water 7.2% Water 7.2% Arkansas Electric Cooperative Corporation Cooperative Corporation E i ti H d l t i Existing Hydroelectric Generating Resources

8

Model documentation report: Short-Term Hydroelectric Generation Model  

DOE Green Energy (OSTI)

The purpose of this report is to define the objectives of the Short- Term Hydroelectric Generation Model (STHGM), describe its basic approach, and to provide details on the model structure. This report is intended as a reference document for model analysts, users, and the general public. Documentation of the model is in accordance with the Energy Information Administration`s (AYE) legal obligation to provide adequate documentation in support of its models (Public Law 94-385, Section 57.b.2). The STHGM performs a short-term (18 to 27- month) forecast of hydroelectric generation in the United States using an autoregressive integrated moving average (UREMIA) time series model with precipitation as an explanatory variable. The model results are used as input for the short-term Energy Outlook.

Not Available

1993-08-01T23:59:59.000Z

9

Short-term hydroelectric generation model. Model documentation report  

DOE Green Energy (OSTI)

The purpose of this report is to define the objectives of the Energy Information Administration`s (EIA) Short-Term Hydroelectric Generation Model (STHGM), describe its basic approach, and to provide details on the model structure. This report is intended as a reference document for model analysts, users, and the general public. Documentation of the model is in accordance with the EIA`s legal obligation to provide adequate documentation in support of its models.

NONE

1996-12-01T23:59:59.000Z

10

Design of a SOA-oriented E-diagnostics system for hydroelectric generating sets  

Science Conference Proceedings (OSTI)

In order to resolve existing problems such as low efficiency, high cost and lack of technical resource in current maintenance, it is necessary to realize remote diagnosis for hydroelectric generating sets (HGSs). In this work, basing on the Service-Oriented ... Keywords: E-diagnostics system, SOA, hydroelectric generating sets, web services

Liangliang Zhan; Yongchuan Zhang; Jianzhong Zhou; Yucheng Peng; Zheng Li

2007-06-01T23:59:59.000Z

11

Mechanisms for Evaluating the Role of Hydroelectric Generation in Ancillary Service Markets  

Science Conference Proceedings (OSTI)

New opportunities to provide system support and ancillary services are attracting the interest of hydroelectric generators. This research focuses primarily on three classes of reserve service (regulation, spinning, and supplemental reserves) and their relation to real power production planning.

1998-12-16T23:59:59.000Z

12

Manual of small-scale hydroelectric generation in South Dakota  

SciTech Connect

This document contains a preliminary inventory of small scale hydroelectric potential in South Dakota and a simplified methodology for calculating economic feasibility of a project. In addition, the various technologies presently on the market, sources of technical and financial assistance and the various permits required for development are also discussed.

1980-01-01T23:59:59.000Z

13

List of Small Hydroelectric Incentives | Open Energy Information  

Open Energy Info (EERE)

Hydroelectric Incentives Hydroelectric Incentives Jump to: navigation, search The following contains the list of 1253 Small Hydroelectric Incentives. CSV (rows 1-500) CSV (rows 501-1000) CSV (rows 1001-1253) Incentive Incentive Type Place Applicable Sector Eligible Technologies Active 401 Certification (Vermont) Environmental Regulations Vermont Utility Industrial Biomass/Biogas Coal with CCS Geothermal Electric Hydroelectric energy Small Hydroelectric Nuclear Yes APS - Renewable Energy Incentive Program (Arizona) Utility Rebate Program Arizona Commercial Residential Anaerobic Digestion Biomass Daylighting Geothermal Electric Ground Source Heat Pumps Landfill Gas Other Distributed Generation Technologies Photovoltaics Small Hydroelectric Solar Pool Heating Solar Space Heat Solar Thermal Process Heat

14

Review of Pacific Northwest Laboratory research on aquatic effects of hydroelectric generation and assessment of research needs  

DOE Green Energy (OSTI)

This report is an overview of Pacific Northwest Laboratory's (PNL) research on how hydroelectric generation affects aquatic biota and environments. The major accomplishments of this research are described, and additional work needed to permit optimal use of available data is identified. The research goals are to: (1) identify impacts of hydroelectric generation, (2) provide guidance in allocating scarce water resources, and (3) develop techniques to avoid or reduce the impacts on aquatic communities or to compensate for unavoidable impacts. Through laboratory and field experiments, an understanding is being developed of the generic impacts of hydrogeneration. Because PNL is located near the Columbia River, which is extensively developed for hydroelectric generation, it is used as a natural laboratory for studying a large-scale operating system. Although the impacts studied result from a particular system of dams and operating procedures and occur within a specific ecosystem, the results of these studies have application at hydroelectric generating facilities throughout the United States.

Fickeisen, D.H.; Becker, C.D.; Neitzel, D.A.

1981-05-01T23:59:59.000Z

15

"1. Grand Coulee","Hydroelectric","U S Bureau of Reclamation",7079  

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

Washington" Washington" "1. Grand Coulee","Hydroelectric","U S Bureau of Reclamation",7079 "2. Chief Joseph","Hydroelectric","USCE-North Pacific Division",2456 "3. Transalta Centralia Generation","Coal","TransAlta Centralia Gen LLC",1596 "4. Rocky Reach","Hydroelectric","PUD No 1 of Chelan County",1254 "5. Columbia Generating Station","Nuclear","Energy Northwest",1097 "6. Wanapum","Hydroelectric","PUD No 2 of Grant County",1059 "7. Boundary","Hydroelectric","Seattle City of",1040 "8. Priest Rapids","Hydroelectric","PUD No 2 of Grant County",932

16

HYDROELECTRIC SYSTEM DESIGN.  

E-Print Network (OSTI)

??Hydroelectric power generation is not a viable option as a prime source of electrical energy for the Pico Blanco Boy Scout Camp, as determined by… (more)

Brown, Timothy McDonnell

2010-01-01T23:59:59.000Z

17

Feasibility determination for hydroelectric development at Thermalito Afterbay with STRAFLO turbine-generators. Final report  

DOE Green Energy (OSTI)

This study addresses the development of the Thermalito Afterbay, in California. Presently, the outlet of the afterbay dissipates the afterbay's useful energy through five radial gates into the Feather River complex. The feasibility of constructing a hydroelectric facility to recover this wasted energy through the use of STRAFLO hydro turbines is appraised, and data relevant to the future economic benefits of such a facility as compared to alternate energy alternatives are presented. In addition, the regulatory, ecological, and socio-institutional impacts which form additional considerations to a future thermalito afterbay site development are summarized. The study shows an annual generation potential of 48.82 GWh. The cost of developing the site is estimated to be $23.5 million. Social and environmental effects would be minimal. The final feasibility of development is contingent on power contracts which the state of California will be negotiating in 1983. (LCL)

Mueller, B.L.

1979-06-01T23:59:59.000Z

18

THE DEVELOPMENT OF HYDROELECTRIC POWER In the early 1880s the first central power-generating station  

E-Print Network (OSTI)

fostered the growth of power companies interested in potential profits. Earlier advances in dam materialsTHE DEVELOPMENT OF HYDROELECTRIC POWER In the early 1880s the first central power-generating station opened in New York City, and a plant in Appleton, Wisconsin, first utilized falling water

US Army Corps of Engineers

19

Pumped Hydroelectricity and Utility-Scale Batteries for Reserve Electricity Generation in New Zealand.  

E-Print Network (OSTI)

??Non-pumped hydroelectricity-based energy storage in New Zealand has only limited potential to expand to meet projected growth in electricity demand. Seasonal variations of hydro inflows… (more)

Kear, Gareth

2011-01-01T23:59:59.000Z

20

Implications of Energy and Ancillary Service Market Structure for Hydroelectric Generation: A Survey of U.S. ISOs  

Science Conference Proceedings (OSTI)

Hydroelectric's superior technical capabilities -- flexibility, fast response, efficiency -- make it especially well suited to providing reserve services in restructured and deregulated markets. A generating unit providing reserves in a deregulated market must understand not only the energy market, but also the interrelated markets for several different classes of reserve services. This report investigates how five U.S. independent service providers (IPOs) provide reserve services.

2001-08-22T23:59:59.000Z

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

The role of hydroelectric generation in electric power systems with large scale wind generation.  

E-Print Network (OSTI)

??An increasing awareness of the operational challenges created by intermittent generation of electricity from policy-mandated renewable resources, such as wind and solar, has led to… (more)

Hagerty, John Michael

2012-01-01T23:59:59.000Z

22

The role of hydroelectric generation in electric power systems with large scale wind generation  

E-Print Network (OSTI)

An increasing awareness of the operational challenges created by intermittent generation of electricity from policy-mandated renewable resources, such as wind and solar, has led to increased scrutiny of the public policies ...

Hagerty, John Michael

2012-01-01T23:59:59.000Z

23

Small-hydroelectric-turbine generating system. Final report, June 30, 1981-December 31, 1982  

DOE Green Energy (OSTI)

The historical development of the Pelton waterwheel and the basics of impulse turbines are reviewed. A guide is given for do-it-yourself construction of small hydroelectric plants. Steps to follow in determining the requirements for a do-it-yourself plant are outlined. Final considerations are also given. (DLC)

Kennedy, B.W.

1983-03-15T23:59:59.000Z

24

Hydroelectric power resources form regional clusters - Today ...  

U.S. Energy Information Administration (EIA)

Hydroelectric power generation resources are spread unevenly across North America. Some regions, like the Pacific Northwest, generate a significant amount of their ...

25

Illinois Nuclear Profile - Dresden Generating Station  

U.S. Energy Information Administration (EIA)

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

26

"1. PSEG Salem Generating Station","Nuclear","PSEG Nuclear LLC...  

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

Jersey" "1. PSEG Salem Generating Station","Nuclear","PSEG Nuclear LLC",2370 "2. PSEG Linden Generating Station","Gas","PSEG Fossil LLC",1587 "3. Bergen Generating...

27

Electric generator dispatch depends on system demand and the ...  

U.S. Energy Information Administration (EIA)

The type of generators with the lowest variable costs are nuclear, hydroelectric, and renewable power (wind and solar). For economic and technical reasons, ...

28

List of Hydroelectric Incentives | Open Energy Information  

Open Energy Info (EERE)

Hydroelectric Incentives Hydroelectric Incentives Jump to: navigation, search The following contains the list of 1298 Hydroelectric Incentives. CSV (rows 1-500) CSV (rows 501-1000) CSV (rows 1001-1298) Incentive Incentive Type Place Applicable Sector Eligible Technologies Active 401 Certification (Vermont) Environmental Regulations Vermont Utility Industrial Biomass/Biogas Coal with CCS Geothermal Electric Hydroelectric energy Small Hydroelectric Nuclear Yes Abatement of Air Pollution: Control of Carbon Dioxide Emissions/Carbon Dioxide Budget Trading Program (Connecticut) Environmental Regulations Connecticut Agricultural Commercial Construction Fed. Government Fuel Distributor General Public/Consumer Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government

29

Underground pumped hydroelectric storage  

DOE Green Energy (OSTI)

Underground pumped hydroelectric energy storage was conceived as a modification of surface pumped storage to eliminate dependence upon fortuitous topography, provide higher hydraulic heads, and reduce environmental concerns. A UPHS plant offers substantial savings in investment cost over coal-fired cycling plants and savings in system production costs over gas turbines. Potential location near load centers lowers transmission costs and line losses. Environmental impact is less than that for a coal-fired cycling plant. The inherent benefits include those of all pumped storage (i.e., rapid load response, emergency capacity, improvement in efficiency as pumps improve, and capacity for voltage regulation). A UPHS plant would be powered by either a coal-fired or nuclear baseload plant. The economic capacity of a UPHS plant would be in the range of 1000 to 3000 MW. This storage level is compatible with the load-leveling requirements of a greater metropolitan area with population of 1 million or more. The technical feasibility of UPHS depends upon excavation of a subterranean powerhouse cavern and reservoir caverns within a competent, impervious rock formation, and upon selection of reliable and efficient turbomachinery - pump-turbines and motor-generators - all remotely operable.

Allen, R.D.; Doherty, T.J.; Kannberg, L.D.

1984-07-01T23:59:59.000Z

30

NUCLEAR FLASH TYPE STEAM GENERATOR  

DOE Patents (OSTI)

A nuclear steam generating apparatus is designed so that steam may be generated from water heated directly by the nuclear heat source. The apparatus comprises a pair of pressure vessels mounted one within the other, the inner vessel containing a nuclear reactor heat source in the lower portion thereof to which water is pumped. A series of small ports are disposed in the upper portion of the inner vessel for jetting heated water under pressure outwardly into the atmosphere within the interior of the outer vessel, at which time part of the jetted water flashes into steam. The invention eliminates the necessity of any intermediate heat transfer medium and components ordinarily required for handling that medium. (AEC)

Johns, F.L.; Gronemeyer, E.C.; Dusbabek, M.R.

1962-09-01T23:59:59.000Z

31

The Next Generation Nuclear Plant  

DOE Green Energy (OSTI)

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

Dr. David A. Petti

2009-01-01T23:59:59.000Z

32

Analysis of the tradeoff between irrigated agriculure and hydroelectric power in the Pacific Northwest. [Base-line estimate of the effects of agricultural irrigation on the hydroelectric power generating potential projected for the year 2020  

DOE Green Energy (OSTI)

Hydrogeneration and irrigated agriculture are major competing users of the waters of the Columbia River and its tributaries. Irrigated agriculture requires the diversion of large amounts of water from the rivers, only part of which returns. As a result, streamflow is reduced and the generation potential of dams located downstream from points of irrigation diversion is reduced. In addition, irrigated agriculture involves the direct consumption of electricity to pump irrigation water and to apply it to crops in the field. The purpose of this report is to make a baseline estimate of the impact on the electrical generation system in the region of the level of irrigation development projected for year 2020 by the states of Oregon, Washington, and Idaho. This baseline estimate reflects the assumption that current conditions will prevail in the future. The results, therefore, provide a standard against which the impacts of changes in current conditions can be measured. It is estimated that the projected development level of 11.4 million acres of irrigated agriculture in Oregon, Washington, and Idaho by year 2020 would result in foregone hydroelectric generation potential of approximately 17.8 million megawatt-hours (MWh) annually and direct consumption of electric power for pumping and application of approximately 10.3 million MWh's annually. Thus, a total of 28.1 million MWh's of electric power generation will have to be traded off each year if irrigated agriculture is to be conducted on the projected scale. (ERB)

Davis, A. E.

1979-01-01T23:59:59.000Z

33

U.S. Nuclear Generation of Electricity  

U.S. Energy Information Administration (EIA)

U.S. Nuclear Generation: 1957 to latest available EIA final data information in the Annual Energy Review, table 9.2. U. S. Nuclear power plants ...

34

Factors affecting the failure of copper connectors brazed to copper bus bar segments on a 615-MVA hydroelectric generator at Grand Coulee Dam  

DOE Green Energy (OSTI)

On March 21, 1986, the United States Bureau of Reclamation experienced a ground fault in the main parallel ring assembly of Unit G19 - a 615-MVA hydroelectric generator - at Grand Coulee Dam, Washington. Inspection of the unit revealed that the ground fault had been induced by fracture of one or more of the copper connectors used to join adjacent segments of one of the bus bars in the north half of the assembly. Various experimental techniques were used to detect and determine the presence of cracks, crack morphology, corrosion products, and material microstructure and/or embrittlement. The results of these inspections and recommendations are given. 7 refs., 27 figs.

Atteridge, D.G.; Klein, R.F.; Layne, R.; Anderson, W.E.; Correy, T.B.

1988-01-01T23:59:59.000Z

35

Small Hydroelectric | Open Energy Information  

Open Energy Info (EERE)

Hydroelectric Jump to: navigation, search TODO: Add description List of Small Hydroelectric Incentives Retrieved from "http:en.openei.orgwindex.php?titleSmallHydroelectric&ol...

36

Normanskill Hydroelectric Facility Feasibility Assessment  

DOE Green Energy (OSTI)

A study was conducted to determine the feasibility of installing a hydroelectric generating facility at an existing dam of the Normanskill Reservoir in NY. Evaluation of the hydrologic, technical, economic, legal, instrumental and environmental factors led to the conclusion that the project is feasible and advantageous. The proposed project has a present worth net cost of $3,099,800. The benefit cost ratio is 2.36. It is estimated that the proposed hydroelectric generating facility at the French's Mills site, City of Watervliet Reservoir will replace approximately 6,000 barrels of foreign oil per year. (LCL)

Besha, J.A.

1979-01-01T23:59:59.000Z

37

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...

38

Developing an acoustic discharge measurement technique for hydroelectric performance testing.  

E-Print Network (OSTI)

??The efficient operation of hydroelectric generating plants requires an accurate definition of the performance relationships of each turbine/generator unit. Of the information obtained by performance… (more)

Gawne, Kevin D.

1997-01-01T23:59:59.000Z

39

Sanderson, P., Memisevic, R., & Wong, B.-L. W. (2004). Analysing cognitive work of hydroelectricity generation in a dynamic deregulated market. Paper to be published in Proceedings of the 48th  

E-Print Network (OSTI)

electrical generation in the developed world is now conducted within deregulated energy markets, providing. The market component of the work domain analysis appears not to be readily amendable to breakdown); (Vicente, 1999) for hydroelectricity generation in a deregulated market in a way that usefully informs

Queensland, University of

40

Energy 101: Hydroelectric Power | Department of Energy  

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

Energy 101: Hydroelectric Power Energy 101: Hydroelectric Power Energy 101: Hydroelectric Power August 13, 2013 - 2:27pm Addthis Learn how hydroelectric power, or hydropower, captures the kinetic energy of flowing water and turns it into electricity for our homes and businesses. Humans have been using water to generate power for thousands of years. Hydroelectric power, or hydropower, captures the kinetic energy of flowing water and turns it into electricity, which is then fed into the electrical grid to be used in homes and businesses. This edition of Energy 101 shows how the Energy Department is supporting the development of new hydropower technologies to produce clean, renewable, and reliable power here in the United States. For more information on hydropower from the Office of Energy Efficiency and

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

U.S. Nuclear Generation of Electricity  

U.S. Energy Information Administration (EIA)

U.S. Nuclear Generation: 1957 to latest available EIA final data information in the Annual Energy Review, table 9.2. U. S. Nuclear power plants projected electricity

42

WEB RESOURCE: Generation IV Nuclear Energy Systems  

Science Conference Proceedings (OSTI)

Feb 16, 2007 ... This web site provides offers a broad overview of the Department of Energy's activities in exploring the development of next generation nuclear ...

43

AN ALGORITHM FOR THE GENERATION OF NUCLEAR SPIN SPECIES AND NUCLEAR SPIN STATISTICAL WEIGHTS  

E-Print Network (OSTI)

Chemistry AN ALGORITHM FOR THE GENERATION OF NUCLEAR SPINSPECIES AND NUCLEAR SPIN STATISTICAL WEIGHTS K.for the Generation of Nuclear Spin and Nuclear Spin

Balasubramanian, K.

2013-01-01T23:59:59.000Z

44

Operating strategy generators for nuclear reactors  

Science Conference Proceedings (OSTI)

Operating strategy generators, i.e., the software intended for increasing the efficiency of work of nuclear power plant operators, are discussed. The possibilities provided by the domestic and foreign operating-strategy generators are analyzed.

Solovyev, D. A., E-mail: and@est.mephi.ru; Semenov, A. A.; Shchukin, N. V. [National Research Nuclear University MEPhI (Russian Federation)

2011-12-15T23:59:59.000Z

45

U.S. Nuclear Generation of Electricity  

Annual Energy Outlook 2012 (EIA)

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

46

"1. Braidwood Generation Station","Nuclear","Exelon Nuclear",2330  

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

Illinois" Illinois" "1. Braidwood Generation Station","Nuclear","Exelon Nuclear",2330 "2. Byron Generating Station","Nuclear","Exelon Nuclear",2300 "3. LaSalle Generating Station","Nuclear","Exelon Nuclear",2238 "4. Baldwin Energy Complex","Coal","Dynegy Midwest Generation Inc",1785 "5. Quad Cities Generating Station","Nuclear","Exelon Nuclear",1774 "6. Dresden Generating Station","Nuclear","Exelon Nuclear",1734 "7. Powerton","Coal","Midwest Generations EME LLC",1538 "8. Elwood Energy LLC","Gas","Dominion Elwood Services Co",1350

47

Northwest hydroelectric output above five-year range for much ...  

U.S. Energy Information Administration (EIA)

The 2011 hydro season began earlier and lasted significantly longer than in recent years, well into the summer months (see chart above). Hydroelectric generation in ...

48

Repurposing a Hydroelectric Plant.  

E-Print Network (OSTI)

??This thesis project explores repurposing a hydroelectric plant along Richmond Virginia's Canal Walk. The building has been redesigned to create a community-oriented space programmed as… (more)

Pritcher, Melissa

2008-01-01T23:59:59.000Z

49

Hydroelectric energy | Open Energy Information  

Open Energy Info (EERE)

Querying Get Involved Help Apps Datasets Community Login | Sign Up Search Page Edit History Facebook icon Twitter icon Hydroelectric energy (Redirected from Hydroelectric)...

50

Small Hydroelectric | Open Energy Information  

Open Energy Info (EERE)

Page Edit History Facebook icon Twitter icon Small Hydroelectric (Redirected from Hydroelectric (Small)) Jump to: navigation, search TODO: Add description List of Small...

51

THE BIRTH OF NUCLEAR-GENERATED ELECTRICITY  

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

BIRTH OF NUCLEAR-GENERATED ELECTRICITY BIRTH OF NUCLEAR-GENERATED ELECTRICITY The first time that electricity was generated from nuclear energy occurred in an experimental breeder reactor in Idaho in 1951. The idea for a breeder reactor (a reactor that could produce more fuel than it uses) first occurred to scientists working on the nation's wartime atomic energy program in the early 1940's. Experimental evidence indicated that the breeding of nuclear fuel was possible in a properly designed reactor, but time and resources were not then available to pursue the idea After the war, the newly established Atomic Energy Commission (now the Department of Energy) assigned some of the nation's nuclear skills and resources to developing peaceful uses of the atom. The large bodies of uranium ore found in the 1950's were

52

The Fourth Generation of Nuclear Power  

SciTech Connect

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: • Nuclear power must remain economically competitive, • The public must remain confident in the safety of the plants and the fuel cycle. • Nuclear wastes and spent fuel must be managed and the ultimate disposition pathways for nuclear wastes must be politically settled. • The proliferation potential of the commercial nuclear fuel cycle must continue to be minimized, and • 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

53

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

U.S. Energy Information Administration (EIA)

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

54

STEAM GENERATOR FOR NUCLEAR REACTOR  

DOE Patents (OSTI)

The steam generator described for use in reactor powergenerating systems employs a series of concentric tubes providing annular passage of steam and water and includes a unique arrangement for separating the steam from the water. (AEC)

Kinyon, B.W.; Whitman, G.D.

1963-07-16T23:59:59.000Z

55

Case Study: Darlington Nuclear Generating Station  

Science Conference Proceedings (OSTI)

Darlington is a four-reactor nuclear plant east of Toronto. It is operated by Ontario Hydro. Each reactor has two independent shutdown systems: SDS1 drops neutron-absorbing rods into the core, while SDS2 injects liquid poison into the moderator. Both ... Keywords: Atomic Energy Control Board of Canada, Canada, Darlington nuclear generating station, Ontario Hydro, case study, certification, code quality, decision-making logic, documentation, fission reactor core control and monitoring, fission reactor safety, formal methods, formal model-based inspection, formal specification, licensing, liquid poison injection, neutron-absorbing rods, nuclear engineering computing, nuclear plant, safety, safety-critical systems, software driven shutdown systems, software reliability, specifications

Dan Craigen; Susan Gerhart; Ted Ralston

1994-01-01T23:59:59.000Z

56

Impact of High Wind Power Penetration on Hydroelectric Unit Operations: Preprint  

DOE Green Energy (OSTI)

This paper examines the impact of this large amount of wind penetration on hydroelectric unit operations. Changes in hydroelectric unit operating unit patterns are examined for an aggregation of all hydro generators.

Hodge, B. M.; Lew, D.; Milligan, M.

2011-10-01T23:59:59.000Z

57

Impact of High Wind Power Penetration on Hydroelectric Unit Operations in the WWSIS  

DOE Green Energy (OSTI)

This report examines the impact of this large amount of wind penetration on hydroelectric unit operations. Changes in hydroelectric unit operating patterns are examined both for an aggregation of all hydro generators and for select individual plants.

Hodge, B.-M.; Lew, D.; Milligan, M.

2011-07-01T23:59:59.000Z

58

Hydroelectric Plants (Iowa)  

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

A permit is required from the Executive Council of Iowa for the construction, maintenance, or operation of any hydroelectric facility. All applications will be subject to a public hearing.

59

Definition: Hydroelectric power | Open Energy Information  

Open Energy Info (EERE)

power power Jump to: navigation, search Dictionary.png Hydroelectric power The use of flowing water to power a turbine to produce electrical energy.[1] View on Wikipedia Wikipedia Definition Hydroelectricity is the term referring to electricity generated by hydropower; the production of electrical power through the use of the gravitational force of falling or flowing water. It is the most widely used form of renewable energy, accounting for 16 percent of global electricity generation - 3,427 terawatt-hours of electricity production in 2010, and is expected to increase about 3.1% each year for the next 25 years. Hydropower is produced in 150 countries, with the Asia-Pacific region generating 32 percent of global hydropower in 2010. China is the largest hydroelectricity producer, with 721 terawatt-hours of production in 2010,

60

Tribal Renewable Energy Foundational Course: Hydroelectric |...  

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

Hydroelectric Tribal Renewable Energy Foundational Course: Hydroelectric Watch the U.S. Department of Energy Office of Indian Energy foundational course webinar on hydroelectric...

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

"1. Robert Moses Niagara","Hydroelectric","New York Power Authority",2353  

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

York" York" "1. Robert Moses Niagara","Hydroelectric","New York Power Authority",2353 "2. Ravenswood","Gas","TC Ravenswood LLC",2330 "3. Nine Mile Point Nuclear Station","Nuclear","Nine Mile Point Nuclear Sta LLC",1773 "4. Oswego Harbor Power","Petroleum","NRG Oswego Harbor Power Operations Inc",1648 "5. Northport","Gas","National Grid Generation LLC",1569 "6. Astoria Generating Station","Gas","U S Power Generating Company LLC",1315 "7. Roseton Generating Station","Gas","Dynegy Northeast Gen Inc",1212 "8. Blenheim Gilboa","Pumped Storage","New York Power Authority",1160

62

Steam Generator Tube Integrity Facilities - Nuclear Engineering...  

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

Nuclear Safety Materials Disposition Decontamination & Decommissioning Nuclear Criticality Safety Nuclear Data Program Nuclear Waste Form Modeling Departments Engineering...

63

Hydroelectric | OpenEI  

Open Energy Info (EERE)

Hydroelectric Hydroelectric Dataset Summary Description This dataset presents summary information related to world hydropower. It is part of a supporting dataset for the book World On the Edge: How to Prevent Environmental and Economic Collapse by Lester R. Source Earth Policy Institute Date Released January 12th, 2011 (3 years ago) Date Updated Unknown Keywords Hydro Hydroelectric Data application/vnd.ms-excel icon book_wote_energy_hydro.xls (xls, 83.5 KiB) Quality Metrics Level of Review Some Review Comment Temporal and Spatial Coverage Frequency Time Period License License Open Data Commons Attribution License Comment "Reuse of our data is permitted. We merely ask that wherever it is listed, it be appropriately cited" Rate this dataset Usefulness of the metadata

64

Analyzing auxiliary system in nuclear generating stations  

Science Conference Proceedings (OSTI)

The design for most nuclear generating stations took place before the widespread use of computerized engineering tools. The manual design basis calculations that were performed vary in quantity from only a few feet of shelf space for some of the first stations to bookcases full for stations that are now receiving their operating licenses. Some of the following issues may apply to the manual calculation files of any nuclear station: Errors and lack of detail in hand calculations; Calculations that may not document the required safety functions; Calculations that lag behind the as-built condition of the station; Documentation that does not add up to a coherent whole; and incomplete auditability and traceability of data. The increasing use of computerized tools in nuclear generating station analysis has helped address the hand-calculation problems. The use of a master system model to study various scenarios also ensures that uniform assumptions are being used for all related analyses. This article presents an overview of how computerized tools are being used for both ac and dc auxiliary system calculations. Problems that may be created by the use of these tools are discussed, along with a review of those issues specific to nuclear generating stations.

Jancauskas, J.R. (Gilber/Commonwealth (US))

1992-07-01T23:59:59.000Z

65

THE NEXT GENERATION NUCLEAR PLANT GRAPHITE PROGRAM  

Science Conference Proceedings (OSTI)

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

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

2008-09-01T23:59:59.000Z

66

Hydroelectric reservoir optimization in a pool market  

Science Conference Proceedings (OSTI)

For a price-taking generator operating a hydro-electric reservoir in a pool electricity market, the optimal stack to offer in each trading period over a planning horizon can be computed using dynamic programming. However, the market trading period (usually ...

G. Pritchard; A. B. Philpott; P. J. Neame

2005-07-01T23:59:59.000Z

67

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

U.S. Energy Information Administration (EIA)

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

68

Microstructural Characterization of Next Generation Nuclear Graphites  

Science Conference Proceedings (OSTI)

This article reports the microstructural characteristics of various petroleum and pitch based nuclear graphites (IG-110, NBG-18, and PCEA) that are of interest to the next generation nuclear plant program. Bright-field transmission electron microscopy imaging was used to identify and understand the different features constituting the microstructure of nuclear graphite such as the filler particles, microcracks, binder phase, rosette-shaped quinoline insoluble (QI) particles, chaotic structures, and turbostratic graphite phase. The dimensions of microcracks were found to vary from a few nanometers to tens of microns. Furthermore, the microcracks were found to be filled with amorphous carbon of unknown origin. The pitch coke based graphite (NBG-18) was found to contain higher concentration of binder phase constituting QI particles as well as chaotic structures. The turbostratic graphite, present in all of the grades, was identified through their elliptical diffraction patterns. The difference in the microstructure has been analyzed in view of their processing conditions.

Karthik Chinnathambi; Joshua Kane; Darryl P. Butt; William E. Windes; Rick Ubic

2012-04-01T23:59:59.000Z

69

Nuclear Georeactor Generation of Earth's Geomagnetic Field  

E-Print Network (OSTI)

The purpose of this communication is to suggest that the mechanism for generating the geomagnetic field and the energy source for powering it are one and the same, a nuclear georeactor at the center of the Earth. Toward this end, I: i) Present evidence that the nuclear georeactor fission-product sub-shell is fluid; ii)Suggest that the geomagnetic field is generated within the georeactor sub-shell, rather than within Earth's iron-alloy fluid core; iii) Describe why convection appears more feasible within the georeactor sub-shell than within the iron-alloy core; iv) Disclose additional relative physical advantages for georeactor sub-shell dynamo operation; and, v) Outline briefly the research that should be conducted to advance the state of knowledge of georeactor-geomagnetic field generation. The concept of geomagnetic field production by the nuclear georeactor is presented specifically for the Earth. The concepts and principles, however, are generally applicable to planetary magnetic field production.

Herndon, J Marvin

2007-01-01T23:59:59.000Z

70

Nuclear Georeactor Generation of Earth's Geomagnetic Field  

E-Print Network (OSTI)

The purpose of this communication is to suggest that the mechanism for generating the geomagnetic field and the energy source for powering it are one and the same, a nuclear georeactor at the center of the Earth. Toward this end, I: i) Present evidence that the nuclear georeactor fission-product sub-shell is fluid; ii)Suggest that the geomagnetic field is generated within the georeactor sub-shell, rather than within Earth's iron-alloy fluid core; iii) Describe why convection appears more feasible within the georeactor sub-shell than within the iron-alloy core; iv) Disclose additional relative physical advantages for georeactor sub-shell dynamo operation; and, v) Outline briefly the research that should be conducted to advance the state of knowledge of georeactor-geomagnetic field generation. The concept of geomagnetic field production by the nuclear georeactor is presented specifically for the Earth. The concepts and principles, however, are generally applicable to planetary magnetic field production.

J. Marvin Herndon

2007-07-19T23:59:59.000Z

71

Canton hydroelectric project: feasibility study. Final report, appendices  

DOE Green Energy (OSTI)

These appendices contain legal, environmental, regulatory, technical and economic information used in evaluating the feasibility of redeveloping the hydroelectric power generating facilities at the Upper and Lower Dams of the Farmington River at Collinsville, CT. (LCL)

Not Available

1979-05-01T23:59:59.000Z

72

Nuclear power generation and fuel cycle report 1996  

SciTech Connect

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

73

NIST Processes to Help Build Next-Generation Nuclear Power ...  

Science Conference Proceedings (OSTI)

NIST Processes to Help Build Next-Generation Nuclear Power Plants. From NIST Tech Beat: June 2, 2009. ...

2011-04-04T23:59:59.000Z

74

Arizona Public Service Co., Palo Verde Nuclear Generating ...  

Science Conference Proceedings (OSTI)

Arizona Public Service Co., Palo Verde Nuclear Generating Station. NVLAP Lab Code: 100536-0. Address and Contact Information: ...

2013-08-23T23:59:59.000Z

75

Mechanical Performance for Current and Next-Generation Nuclear ...  

Science Conference Proceedings (OSTI)

About this Symposium. Meeting, 2010 TMS Annual Meeting & Exhibition. Symposium, Mechanical Performance for Current and Next-Generation Nuclear ...

76

Nuclear power generation and fuel cycle report 1997  

SciTech Connect

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.

1997-09-01T23:59:59.000Z

77

Incentive Cost Recovery Rule for Nuclear Power Generation (Louisiana) |  

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

You are here You are here Home » Incentive Cost Recovery Rule for Nuclear Power Generation (Louisiana) Incentive Cost Recovery Rule for Nuclear Power Generation (Louisiana) < Back Eligibility Commercial Construction Industrial Utility Program Info State Louisiana Program Type Fees Generating Facility Rate-Making Provider Louisiana Public Service Commission 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 supplements the Louisiana Public Service Commission's 1983 General Order for the acquisition of nuclear generation resources. The goal of the rule is to provide a transparent process that identifies the responsibilities parties in the regulatory

78

Nuclear Power Generating Facilities (Maine) | Department of Energy  

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

Nuclear Power Generating Facilities (Maine) Nuclear Power Generating Facilities (Maine) Nuclear Power Generating Facilities (Maine) < Back Eligibility Agricultural Commercial Construction Fed. Government Fuel Distributor General Public/Consumer Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Low-Income Residential Multi-Family Residential Municipal/Public Utility Nonprofit Residential Retail Supplier Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Program Info State Maine Program Type Siting and Permitting Provider Radiation Control Program 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 Maine. The Legislature

79

NNSA Next Generation Safeguards Initiative | National Nuclear...  

National Nuclear Security Administration (NNSA)

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

80

The northeast Georgia hydroelectric plants.  

E-Print Network (OSTI)

??The Northeast Georgia hydroelectric plants are important cultural resources to the state of Georgia and the communities immediately adjacent. If the early technology of these… (more)

Kelly, Nancy Elizabeth

2005-01-01T23:59:59.000Z

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

Hydroelectric energy | Open Energy Information  

Open Energy Info (EERE)

Add description List of Hydroelectric Incentives Retrieved from "http:en.openei.orgwindex.php?titleHydroelectricenergy&oldid277908" Category: Articles with outstanding...

82

Environmental requirements at hydroelectric power plants  

DOE Green Energy (OSTI)

Hydroelectric power is the most mature and widely implemented of the renewable energy technologies. The energy of flowing water has been used to perform work directly since ancient times, and the use of hydropower turbines to generate electricity traces back to the 19th century. Two commonly used turbine types, the Francis and Kaplan turbines, are essentially refinements of the simple reaction turbine of Hero of Alexandria, dating from about 100 B.C. (NAS 1976). Hydroelectric power production provides over 10% of the net electrical generation in the US, more than petroleum or natural gas and far more than the other renewable energy technologies combined. On a regional basis, hydroelectric power represents 14% of the net electrical power generation in the Rocky Mountain states and nearly 63% along the Pacific Coast. Those states that have the largest percentages of their electricity generated by hydropower (e.g., Idaho, Oregon, Montana, and Washington) also tend to have the lowest average cost of electricity per kilowatt-hour.

Cada, G.F. [Oak Ridge National Lab., TN (United States). Environmental Sciences Div.; Francfort, J.E. [Idaho National Engineering Lab., Idaho Falls, ID (United States)

1993-12-31T23:59:59.000Z

83

Blasting aids in the reconstruction of a hydroelectric plant  

SciTech Connect

The replacement of failed impeller chambers in a hydroelectric plant is described in this article. The emphasis of the article is on the use of a blast-generating unit (BGU) for crushing reinforced concrete. The BGU feeds kerosene and nitrogen tetroxide from separate tanks to form a jet of liquid explosive mixture. The BGU performed safely and efficiently, and has been recommended for use at other hydroelectric plants. 1 ref., 1 fig., 1 tab.

Benderskii, L.F.; Evlikov, A.A.; Stupel`, R.O. [and others

1995-01-01T23:59:59.000Z

84

NNSA Launches Next Generation Safeguards Initiative | National Nuclear  

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

Next Generation Safeguards Initiative | National Nuclear Next Generation Safeguards Initiative | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our History > NNSA Timeline > NNSA Launches Next Generation Safeguards Initiative NNSA Launches Next Generation Safeguards Initiative September 09, 2008 Washington, DC NNSA Launches Next Generation Safeguards Initiative

85

Marine Hydroelectric Company | Open Energy Information  

Open Energy Info (EERE)

Marine Hydroelectric Company Jump to: navigation, search Name Marine Hydroelectric Company Address 24040 Camino Del Avion A 107 Place Monarch Beach Sector Marine and Hydrokinetic...

86

Power generation from nuclear reactors in aerospace applications  

SciTech Connect

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

87

Power generation from nuclear reactors in aerospace applications  

SciTech Connect

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

88

Bush Administration Moves Forward to Develop Next Generation Nuclear Energy  

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

Moves Forward to Develop Next Generation Moves Forward to Develop Next Generation Nuclear Energy Systems Bush Administration Moves Forward to Develop Next Generation Nuclear Energy Systems February 28, 2005 - 10:33am Addthis WASHINGTON, DC-The Bush Administration today took a major step in advancing international efforts to develop the next generation of clean, safe nuclear energy systems. Secretary of Energy Samuel W. Bodman joined representatives from Canada, France, Japan, and the United Kingdom to sign the first multilateral agreement in history aimed at the development of next generation nuclear energy systems. The work of the Generation IV International Forum (GIF) is essential to advancing an important component of the Bush Administration's comprehensive energy strategy in the development of next generation nuclear energy technologies.

89

Arrangement for hydroelectric power plants  

SciTech Connect

Hydroelectric power plant contains a flow tube for the water, an inlet tube leading to the flow tube and a discharge tube leading from the flow tube. In the flow tube a turbine is arranged to be driven by the flowing water and which via a drive shaft drives an electric generator. Accentuated sub-divisioning as between mechanical unit and portions of an installation nature is provided. The turbine and generator are located in the direct vicinity of each other and together with the drive shaft form a unit which in its entirety is situate in the flow tube and arranged to be traversed by flowing water. The unit is so arranged that the turbine can be in contact with the water flow while the generator has a watertight enclosure into which the drive shaft extends through a watertight bushing. Furthermore an electric cable for transmitting the electricity produced is connected. The installation components, the said tubes, are made from prefabricated concrete components. The flow tube is essentially vertical and exhibits a support for the unit and, at its upper end, an aperture through which the unit can be lowered.

Osterberg, T.V.

1984-03-13T23:59:59.000Z

90

Figure 38. Levelized costs of nuclear electricity generation in ...  

U.S. Energy Information Administration (EIA)

Sheet3 Sheet2 Sheet1 Figure 38. Levelized costs of nuclear electricity generation in two cases, 2025 (2011 dollars per megawatthour) Reference Small Modular Reactor

91

Some noise control problems peculiar to nuclear generating facilities  

Science Conference Proceedings (OSTI)

The ability to confidently predict the noise environment in a nuclear generating facility presently under construction is complicated by the design constraints of physical layout

Robert A. Putnam

1977-01-01T23:59:59.000Z

92

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

U.S. Energy Information Administration (EIA)

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

93

Spark Plasma Sintering of Next Generation Nuclear Materials  

Science Conference Proceedings (OSTI)

... Spark Plasma Sintering of Next Generation Nuclear Materials. Author(s), Daniel Osterberg, Jeff Perkins, Matt Luke, Brian Jaques, Michael F Hurley, Darryl Butt.

94

Energy Department Invests $60 Million to Train Next Generation Nuclear  

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

60 Million to Train Next Generation 60 Million to Train Next Generation Nuclear Energy Leaders, Pioneer Advanced Nuclear Technology Energy Department Invests $60 Million to Train Next Generation Nuclear Energy Leaders, Pioneer Advanced Nuclear Technology September 20, 2013 - 1:00pm Addthis News Media Contact (202) 586-4940 WASHINGTON - Building on President Obama's Climate Action Plan to continue America's leadership in clean energy innovation, the Energy Department announced today more than $60 million in nuclear energy research awards and improvements to university research reactors and infrastructure. The 91 awards announced today will help train and educate the next generation of leaders in America's nuclear industry as well as support new and advanced nuclear technologies from reactor materials to innovative

95

Energy Department Invests $60 Million to Train Next Generation Nuclear  

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

Energy Department Invests $60 Million to Train Next Generation Energy Department Invests $60 Million to Train Next Generation Nuclear Energy Leaders, Pioneer Advanced Nuclear Technology Energy Department Invests $60 Million to Train Next Generation Nuclear Energy Leaders, Pioneer Advanced Nuclear Technology September 20, 2013 - 1:00pm Addthis News Media Contact (202) 586-4940 WASHINGTON - Building on President Obama's Climate Action Plan to continue America's leadership in clean energy innovation, the Energy Department announced today more than $60 million in nuclear energy research awards and improvements to university research reactors and infrastructure. The 91 awards announced today will help train and educate the next generation of leaders in America's nuclear industry as well as support new and advanced nuclear technologies from reactor materials to innovative

96

Industry Participation Sought for Design of Next Generation Nuclear Plant |  

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

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

97

Applications of Wavelet-Packet in Fault Analysis of Hydroelectric Sets  

Science Conference Proceedings (OSTI)

This paper presents a new method using wavelet packet transform to fault diagnosis of the hydroelectric generating. The use of wavelet packet analysis unit to achieve multi-level vibration signals of wavelet packet decomposition, the analysis provides ... Keywords: wavelet packet, fault diagnosis, hydroelectric generating sets

Liu Haiying; Dai Luping

2010-06-01T23:59:59.000Z

98

Evaluating Wind-Following and Ecosystem Services for Hydroelectric Dams in PJM  

Science Conference Proceedings (OSTI)

Hydropower can provide inexpensive, flexible fill-in power to compensate for intermittent renewable generation. We model the decision of a hydroelectric generator to shift power capacity away from the day-ahead energy market into a "wind-following" service ... Keywords: Hydroelectric power, wind, PJM, drought, energy policy

Alisha Fernandez; Seth Blumsack; Patrick Reed

2012-01-01T23:59:59.000Z

99

SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT  

E-Print Network (OSTI)

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

Dear Mr. Sorensen; Roger D. Lanksbury

2001-01-01T23:59:59.000Z

100

Next Generation Nuclear Plant GAP Analysis Report  

DOE Green Energy (OSTI)

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

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

2008-12-01T23:59:59.000Z

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

Figure 9.1 Nuclear Generating Units - U.S. Energy Information ...  

U.S. Energy Information Administration (EIA)

Figure 9.1 Nuclear Generating Units Operable Units,1 1957-2011 Nuclear Net Summer Capacity Change, 1950-2011 Status of All Nuclear Generating Units, ...

102

Potential for hydroelectric development in Alaska  

Science Conference Proceedings (OSTI)

Testimony concerning Alaskan hydroelectricity development is presented. Various public and private organizations were represented.

Not Available

1981-01-01T23:59:59.000Z

103

Nuclear Power Plant Emergency Diesel Generator Tanks 1  

E-Print Network (OSTI)

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

unknown authors

2006-01-01T23:59:59.000Z

104

Observations on A Technology Roadmap for Generation IV Nuclear Energy  

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

Observations on A Technology Roadmap for Generation IV Nuclear Observations on A Technology Roadmap for Generation IV Nuclear Energy Systems: Technical Roadmap Report Observations on A Technology Roadmap for Generation IV Nuclear Energy Systems: Technical Roadmap Report 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 installations in the short term. DOE needs to give those immediate objectives the highest priority and any additional support they require to assure their success. DOE is pursuing two initiatives to encourage a greater use of nuclear energy systems. The initiatives have been reviewed by NERAC Subcommittee on Generation IV Technology Planning (GRNS) and they are: * A Near Term Development (NTD) Roadmap which is in the process of being

105

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...

106

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...

107

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...

108

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"...

109

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...

110

Nuclear Power Generation and Fuel Cycle Report  

Reports and Publications (EIA)

Final issue. This report provides information and forecasts important to the domestic and world nuclear and uranium industries. 1997 represents the most recent publication year.

Dr. Zdenek D.

1997-09-01T23:59:59.000Z

111

Shares of electricity generation from renewable energy sources ...  

U.S. Energy Information Administration (EIA)

Non-hydroelectric renewable generation has increased in many states over the past decade. In 2011, Maine had the highest percentage of non-hydroelectric renewable ...

112

Nuclear Maintenance Applications Center: Generator Maintenance Guide for Emergency Diesel Generators  

Science Conference Proceedings (OSTI)

The Electric Power Research Institute (EPRI) developed this report to address maintenance and improve long-term reliability and availability of generators within nuclear power plant emergency diesel generator (EDG) systems.

2010-12-11T23:59:59.000Z

113

Impact of High Wind Power Penetration on Hydroelectric Unit Operations  

SciTech Connect

The Western Wind and Solar Integration Study (WWSIS) investigated the operational impacts of very high levels of variable generation penetration rates (up to 35% by energy) in the western United States. This work examines the impact of this large amount of wind penetration on hydroelectric unit operations. Changes in hydroelectric unit operating unit patterns are examined for an aggregation of all hydro generators. The cost impacts of maintaining hydro unit flexibility are assessed and compared for a number of different modes of system operation.

Hodge, B. M.; Lew, D.; Milligan, M.

2011-01-01T23:59:59.000Z

114

Generation IV (Gen IV) - Nuclear Engineering Division (Argonne)  

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

Generation IV (Gen Generation IV (Gen IV) Generation IV Overview Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Major Programs Generation IV (Gen IV) Development of next generation nuclear systems featuring significant advances in sustainability, economics, safety, reliability, proliferation resistance and physical protection. Bookmark and Share Generation IV Fact Sheet (73 KB) Overview Generation IV nuclear energy systems target significant advances over current-generation and evolutionary systems in the areas of sustainability, safety and reliability, and economics. These systems are to be deployable by 2030 in both industrialized and developing countries. Development of Generation IV systems is an international initiative. A

115

Bangor Hydro-Electric Co | Open Energy Information  

Open Energy Info (EERE)

Bangor Hydro-Electric Co Bangor Hydro-Electric Co Jump to: navigation, search Name Bangor Hydro-Electric Co Place Maine Service Territory Maine Website www.bhe.com/ Green Button Landing Page secure.bhe.com/webPortal/ Green Button Reference Page www.bhe.com/about-us/news Green Button Implemented Yes Utility Id 1179 Utility Location Yes Ownership I NERC Location NPCC NERC NPCC Yes ISO NE Yes Operates Generating Plant Yes Activity Generation Yes Activity Transmission Yes Activity Distribution Yes References EIA Form EIA-861 Final Data File for 2010 - File1_a[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Utility Rate Schedules Grid-background.png 9 (General Service Rate) Commercial Commercial space heating- Single meter Commercial

116

Training the Next Generation of Nuclear Energy Leaders | Department of  

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

Training the Next Generation of Nuclear Energy Leaders Training the Next Generation of Nuclear Energy Leaders Training the Next Generation of Nuclear Energy Leaders May 8, 2012 - 3:06pm Addthis University of Idaho professor Supathorn Phongikaroon works with a graduate student in the radiochemistry lab at the Center for Advanced Energy Studies in Idaho Falls, Idaho. Phongikaroon has received $820,000 from DOE to study an applied technology to remotely analyze spent nuclear fuel. | Photo courtesy of the University of Idaho. University of Idaho professor Supathorn Phongikaroon works with a graduate student in the radiochemistry lab at the Center for Advanced Energy Studies in Idaho Falls, Idaho. Phongikaroon has received $820,000 from DOE to study an applied technology to remotely analyze spent nuclear fuel. | Photo

117

Training the Next Generation of Nuclear Energy Leaders | Department of  

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

the Next Generation of Nuclear Energy Leaders the Next Generation of Nuclear Energy Leaders Training the Next Generation of Nuclear Energy Leaders May 8, 2012 - 3:06pm Addthis University of Idaho professor Supathorn Phongikaroon works with a graduate student in the radiochemistry lab at the Center for Advanced Energy Studies in Idaho Falls, Idaho. Phongikaroon has received $820,000 from DOE to study an applied technology to remotely analyze spent nuclear fuel. | Photo courtesy of the University of Idaho. University of Idaho professor Supathorn Phongikaroon works with a graduate student in the radiochemistry lab at the Center for Advanced Energy Studies in Idaho Falls, Idaho. Phongikaroon has received $820,000 from DOE to study an applied technology to remotely analyze spent nuclear fuel. | Photo

118

The Next Generation Nuclear Plant (NGNP) Project  

DOE Green Energy (OSTI)

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

F. H. Southworth; P. E. MacDonald

2003-11-01T23:59:59.000Z

119

Small-Scale Hydroelectric Power Demonstration Project  

DOE Green Energy (OSTI)

The US Department of Energy Field Office, Idaho, Small-Scale Hydroelectric Power Program was initiated in conjunction with the restoration of three power generating plants in Idaho Falls, Idaho, following damage caused by the Teton Dam failure on June 5, 1976. There were many parties interested in this project, including the state and environmental groups, with different concerns. This report was prepared by the developer and describes the design alternatives the applicant provided in an attempt to secure the Federal Energy Regulatory Commission license. Also included are correspondence between the related parties concerning the project, major design alternatives/project plan diagrams, the license, and energy and project economics.

Gleeson, L.

1991-12-01T23:59:59.000Z

120

Program on Technology Innovation: Nuclear Power Generation Technologies  

Science Conference Proceedings (OSTI)

The United States and other countries are currently planning to expand their nuclear power electrical generation base in order to provide energy security and price stability while reducing greenhouse gas emissions. Since the existing fleet of nuclear plants was built during or before the 1970s, new plants will incorporate more advanced designs. This report documents the current status and potential for advanced nuclear power technology development and/or commercialization over the next 5 to 15 years.

2007-06-20T23:59:59.000Z

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


121

Decommissioning San Onofre Nuclear Generating Station Unit 1 (SONGS-1)  

Science Conference Proceedings (OSTI)

Decommissioning a nuclear power plant and termination of the plant license requires the removal of highly activated materials from inside the nuclear reactor pressure vessel (RPV). Such a task presents a major challenge in terms of technology, project management, and worker exposure. This report documents the approach taken by Southern California Edison (SCE) in their highly successful reactor vessel internals (RVI) segmentation of San Onofre Nuclear Generating Station Unit 1 (SONGS-1). The report detail...

2005-12-12T23:59:59.000Z

122

Rancho Seco Nuclear Generating Station Decommissioning Experience Report  

Science Conference Proceedings (OSTI)

Several U.S. nuclear power plants entered decommissioning in the 1990s. Based on current information, the next group of plants whose license will expire will not begin decommissioning for nearly a decade. This report provides detailed information on the decommissioning of one plant, the Rancho Seco Nuclear Generating Station, in order to capture its experience for future plants.

2007-12-19T23:59:59.000Z

123

Program on Technology Innovation: The Next Generation Nuclear Plant  

Science Conference Proceedings (OSTI)

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

2008-12-15T23:59:59.000Z

124

Hydroelectric Conventional | OpenEI  

Open Energy Info (EERE)

Hydroelectric Conventional Hydroelectric Conventional Dataset Summary Description Provides annual consumption (in quadrillion Btu) of renewable energy by energy use sector (residential, commercial, industrial, transportation and electricity) and by energy source (e.g. solar, biofuel) for 2004 through 2008. Original sources for data are cited on spreadsheet. Also available from: www.eia.gov/cneaf/solar.renewables/page/trends/table1_2.xls Source EIA Date Released August 01st, 2010 (4 years ago) Date Updated Unknown Keywords annual energy consumption biodiesel Biofuels biomass energy use by sector ethanol geothermal Hydroelectric Conventional Landfill Gas MSW Biogenic Other Biomass renewable energy Solar Thermal/PV Waste wind Wood and Derived Fuels Data application/vnd.ms-excel icon RE Consumption by Energy Use Sector, Excel file (xls, 32.8 KiB)

125

Washington Nuclear Profile - Columbia Generating Station  

U.S. Energy Information Administration (EIA)

snpt3wa371 1,097 9,241 96.2 BWR Columbia Generating Station Unit Type Data for 2010 BWR = Boiling Water Reactor. Note: Totals may not equal sum of components due to ...

126

Kansas Nuclear Profile - Wolf Creek Generating Station  

U.S. Energy Information Administration (EIA)

snpt3ks210 1,160 9,556 94.0 PWR Wolf Creek Generating Station Unit Type Data for 2010 PWR = Pressurized Light Water Reactor. Note: Totals may not ...

127

Optimization Online - Managing Hydroelectric Reservoirs over an ...  

E-Print Network (OSTI)

Jul 7, 2013 ... Managing Hydroelectric Reservoirs over an Extended Planning Horizon using a Benders Decomposition Algorithm Exploiting a Memory Loss ...

128

Advances in Hydroelectric Turbine Manufacturing and Repair  

Science Conference Proceedings (OSTI)

About this Symposium. Meeting, Materials Science & Technology 2013. Symposium, Advances in Hydroelectric Turbine Manufacturing and Repair. Sponsorship ...

129

Materials Science and Technology in Hydroelectricity  

Science Conference Proceedings (OSTI)

About this Abstract. Meeting, Materials Science & Technology 2013. Symposium, Advances in Hydroelectric Turbine Manufacturing and Repair. Presentation ...

130

Nuclear Power Generation and Fuel Cycle Report 1997  

Gasoline and Diesel Fuel Update (EIA)

7) 7) Distribution Category UC-950 Nuclear Power Generation and Fuel Cycle Report 1997 September 1997 Energy Information Administration Office of Coal, Nuclear, Electric and Alternate Fuels U.S. Department of Energy Washington, DC 20585 This report was prepared by the Energy Information Administration, the independent statistical and analytical agency within the Department of Energy. The information contained herein should not be construed as advocating or reflecting any policy position of the Department of Energy or of any other organization. Contacts Energy Information Administration/ Nuclear Power Generation and Fuel Cycle Report 1997 ii The Nuclear Power Generation and Fuel Cycle Report is prepared by the U.S. Department of Energy's Energy Information Administration. Questions and comments concerning the contents of the report may be directed to:

131

Generation Risk Assessment (GRA) at Cooper Nuclear Station  

Science Conference Proceedings (OSTI)

A previous EPRI guide described how generating plants can implement various forms of component and system models for generation risk assessment (GRA). This report describes a trial application of GRA modeling at the Cooper Nuclear Station and evaluates the usefulness and accuracy of the EPRI GRA guide.

2005-12-06T23:59:59.000Z

132

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

133

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

134

An Integrated Safety Assessment Methodology for Generation IV Nuclear Systems  

SciTech Connect

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 “toolkit” 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

135

Optimizing profits from hydroelectricity production  

Science Conference Proceedings (OSTI)

This paper presents a deterministic and a stochastic mathematical model for maximizing the profits obtained by selling electricity produced through a cascade of dams and reservoirs in a deregulated market. The first model is based on deterministic electricity ... Keywords: Hydroelectricity, Market, Mathematical programming, Production, Stochastic programming

Daniel De Ladurantaye; Michel Gendreau; Jean-Yves Potvin

2009-02-01T23:59:59.000Z

136

POWER GENERATION FROM LIQUID METAL NUCLEAR FUEL  

DOE Patents (OSTI)

A nuclear reactor system is described wherein the reactor is the type using a liquid metal fuel, such as a dispersion of fissile material in bismuth. The reactor is designed ln the form of a closed loop having a core sectlon and heat exchanger sections. The liquid fuel is clrculated through the loop undergoing flssion in the core section to produce heat energy and transferrlng this heat energy to secondary fluids in the heat exchanger sections. The fission in the core may be produced by a separate neutron source or by a selfsustained chain reaction of the liquid fuel present in the core section. Additional auxiliary heat exchangers are used in the system to convert water into steam which drives a turbine.

Dwyer, O.E.

1958-12-23T23:59:59.000Z

137

International Energy Statistics  

U.S. Energy Information Administration (EIA)

Nuclear: Renewables: Total Fossil Fuels: Hydroelectric Pumped Storage: Total Net Generation: Hydroelectric: Non-Hydroelectric Renewables: Total: Geothermal: Wind

138

International Energy Statistics - U.S. Energy Information ...  

U.S. Energy Information Administration (EIA)

Nuclear: Renewables: Total Fossil Fuels: Hydroelectric Pumped Storage: Total Net Generation: Hydroelectric: Non-Hydroelectric Renewables: Total: Geothermal: Wind

139

Nuclear Maintenance Applications Center: Generator Maintenance Guide for Emergency Diesel Generators (Japanese Version)  

Science Conference Proceedings (OSTI)

This report is a Japanese translation of Electric Power Research Institute (EPRI) Technical Report 1021479. EPRI developed this report to address maintenance and improve long-term reliability and availability of generators within nuclear power plant emergency diesel generator (EDG) systems. Maintenance of generator stators and rotors is the focus of this report, which highlights maintenance tasks and strategies that can be performed to identify generator degradation and prevent unforeseen failures. This ...

2012-03-21T23:59:59.000Z

140

Nuclear steam-generator transplant total rises  

Science Conference Proceedings (OSTI)

Several utilities with pressurized water reactors (PWRs) are replacing leaking and corroded steam generators. Over half the PWRs face corrosion problems that will cost $50 million to $100 million per unit to correct. An alternative approach of installing new tube sleeves has only had one application. Corrosion prevention still eludes utilities, whose problems differ. Westinghouse units were the first to experience corrosion problems because they have almost all operated for a decade or more. Some advances in condenser and steam-generator technology should extend the component life of younger units, and some leaking PWR tubes can be plugged. Operating differences may explain why PWRs have operated for over 20 years on submarines using phosphate water chemistry, while the use of de-aerators in the secondary-systems of foreign PWRs may explain their better performance. Among the corrective steps recommended by Stone and Webster are tighter chemistry control, better plant layup practices, revamping secondary-system hardware, condensate polishing, and de-aerators. Research continues to find the long-term preventative. 2 tables. (DCK)

Smock, R.

1982-09-01T23:59:59.000Z

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

Nuclear Power Generation and Fuel Cycle Report 1996  

Gasoline and Diesel Fuel Update (EIA)

6) 6) Distribution Category UC-950 Nuclear Power Generation and Fuel Cycle Report 1996 October 1996 Energy Information Administration Office of Coal, Nuclear, Electric and Alternate Fuels U.S. Department of Energy Washington, DC 20585 This report was prepared by the Energy Information Administration, the independent statistical and analytical agency within the Department of Energy. The information contained herein should not be construed as advocating or reflecting any policy position of the Department of Energy or of any other organization. Energy Information Administration/ Nuclear Power Generation and Fuel Cycle Report 1996 ii Contacts This report was prepared in the Office of Coal, Nuclear, report should be addressed to the following staff Electric and Alternate Fuels by the Analysis and Systems

142

ADVANCED CERAMIC MATERIALS FOR NEXT-GENERATION NUCLEAR APPLICATIONS  

SciTech Connect

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

143

Hydroelectric plant construction cost and annual production expenses. Eighteenth annual supplement, 1974. [1974 data  

SciTech Connect

Tabulated data are presented on the generating capacity, construction costs, and production expenses for each of 432 conventional or pumped storage hydroelectric power plants in the U.S. (LCL)

1976-11-01T23:59:59.000Z

144

BRUSLIB and NETGEN: the Brussels nuclear reaction rate library and nuclear network generator for astrophysics  

E-Print Network (OSTI)

Nuclear reaction rates are quantities of fundamental importance in astrophysics. Substantial efforts have been devoted in the last decades to measure or calculate them. The present paper presents for the first time a detailed description of the Brussels nuclear reaction rate library BRUSLIB and of the nuclear network generator NETGEN so as to make these nuclear data packages easily accessible to astrophysicists for a large variety of applications. BRUSLIB is made of two parts. The first one contains the 1999 NACRE compilation based on experimental data for 86 reactions with (mainly) stable targets up to Si. The second part of BRUSLIB concerns nuclear reaction rate predictions calculated within a statistical Hauser-Feshbach approximation, which limits the reliability of the rates to reactions producing compound nuclei with a high enough level density. These calculations make use of global and coherent microscopic nuclear models for the quantities entering the rate calculations. The use of such models is utterly important, and makes the BRUSLIB rate library unique. A description of the Nuclear Network Generator NETGEN that complements the BRUSLIB package is also presented. NETGEN is a tool to generate nuclear reaction rates for temperature grids specified by the user. The information it provides can be used for a large variety of applications, including Big Bang nucleosynthesis, the energy generation and nucleosynthesis associated with the non-explosive and explosive hydrogen to silicon burning stages, or the synthesis of the heavy nuclides through the s-, alpha- and r-, rp- or p-processes.

M. Aikawa; M. Arnould; S. Goriely; A. Jorissen; K. Takahashi

2005-06-24T23:59:59.000Z

145

Nuclear Maintenance Applications Center: Clearance and Tagging Guideline for Nuclear Electric Generating Stations, Revision 1  

Science Conference Proceedings (OSTI)

Clearance and tagging programs at nuclear electric generating facilities serve to protect personnel from injury and to protect equipment from damage. These programs are thus of vital importance from both a worker safety standpoint and an operations and maintenance cost standpoint. This guideline presents a clearance and tagging approach, developed with broad industry input, that nuclear electric generating companies can use as a basis for comparison with their own programs.

2010-02-01T23:59:59.000Z

146

Regional comparison of nuclear and fossil electric power generation costs  

SciTech Connect

Nuclear's main disadvantages are its high capital investment cost and uncertainty in schedule compared with alternatives. Nuclear plant costs continue to rise whereas coal plant investment costs are staying relative steady. Based on average experience, nuclear capital investment costs are nearly double those of coal-fired generation plants. The capital investment cost disadvantage of nuclear is balanced by its fuel cost advantages. New base load nuclear power plants were projected to be competitive with coal-fired plants in most regions of the country. Nuclear power costs wre projected to be significantly less (10% or more) than coal-fired power costs in the South Atlantic region. Coal-fired plants were projected to have a significant economic advantage over nuclear plants in the Central and North Central regions. In the remaining seven regions, the levelized cost of power from either option was projected to be within 10%. Uncertainties in future costs of materials, services, and financing affect the relative economics of the nuclear and coal options significantly. 10 figures.

Bowers, H.I.

1984-01-01T23:59:59.000Z

147

Active Interrogation Using Electronic Neutron Generators for Nuclear Safeguards Applications  

SciTech Connect

Active interrogation, a measurement technique which uses a radiation source to probe materials and generate unique signatures useful for characterizing those materials, is a powerful tool for assaying special nuclear material. The most commonly used technique for performing active interrogation is to use an electronic neutron generator as the probe radiation source. Exploiting the unique operating characteristics of these devices, including their monoenergetic neutron emissions and their ability to operate in pulsed modes, presents a number of options for performing prompt and delayed signature analyses using both photon and neutron sensors. A review of literature in this area shows multiple applications of the active neutron interrogation technique for performing nuclear nonproliferation measurements. Some examples include measuring the plutonium content of spent fuel, assaying plutonium residue in spent fuel hull claddings, assaying plutonium in aqueous fuel reprocessing process streams, and assaying nuclear fuel reprocessing facility waste streams to detect and quantify fissile material. This paper discusses the historical use of this technique and examines its context within the scope and challenges of next-generation nuclear fuel cycles and advanced concept nuclear fuel cycle facilities.

David L. Chichester; Edward H. Seabury

2008-08-01T23:59:59.000Z

148

Nuclear Maintenance Applications Center: Emergency Diesel Generator Condition- Based Maintenance  

Science Conference Proceedings (OSTI)

Condition-based maintenance practices that were developed in the United States in the 1990s for emergency diesel generators (EDGs) have not been fully adopted by international nuclear plant operators. To encourage broader use of such practices, NMAC formed a technical advisory group of international utilities interested in learning more about condition-based EDG maintenance practices.

2008-12-19T23:59:59.000Z

149

San Onofre Nuclear Generating Station - Unit 1 Decommissioning Experience Report  

Science Conference Proceedings (OSTI)

This report provides detailed information on the successful decommissioning activities of San Onofre Nuclear Generating Station, Unit 1 (SONGS 1). The report describes their experiences and lessons learned for managers of US and international plants beginning or currently engaged in decommissioning.

2008-12-04T23:59:59.000Z

150

Hydrogen Production from the Next Generation Nuclear Plant  

DOE Green Energy (OSTI)

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

M. Patterson; C. Park

2008-03-01T23:59:59.000Z

151

Storing hydroelectricity to meet peak-hour demand  

Science Conference Proceedings (OSTI)

This paper reports on pumped storage plants which have become an effective way for some utility companies that derive power from hydroelectric facilities to economically store baseload energy during off-peak hours for use during peak hourly demands. According to the Electric Power Research Institute (EPRI) in Palo Alto, Calif., 36 of these plants provide approximately 20 gigawatts, or about 3 percent of U.S. generating capacity. During peak-demand periods, utilities are often stretched beyond their capacity to provide power and must therefore purchase it from neighboring utilities. Building new baseload power plants, typically nuclear or coal-fired facilities that run 24 hours per day seven days a week, is expensive, about $1500 per kilowatt, according to Robert Schainker, program manager for energy storage at the EPRI. Schainker the that building peaking plants at $400 per kilowatt, which run a few hours a day on gas or oil fuel, is less costly than building baseload plants. Operating them, however, is more expensive because peaking plants are less efficient that baseload plants.

Valenti, M.

1992-04-01T23:59:59.000Z

152

Executive Summary: Research in Nuclear Power—Workshop on the Needs of the Next Generation of Nuclear Power Technology  

Science Conference Proceedings (OSTI)

Technical Paper / NSF Workshop on the Research Needs of the Next Generation Nuclear Power Technology / Fission Reactor

A. David Rossin; Kunmo Chung; K. L. Peddicord

153

National need for utilizing nuclear energy for process heat generation  

DOE Green Energy (OSTI)

Nuclear reactors are potential sources for generating process heat, and their applications for such use economically competitive. They help satisfy national needs by helping conserve and extend oil and natural gas resources, thus reducing energy imports and easing future international energy concerns. Several reactor types can be utilized for generating nuclear process heat; those considered here are light water reactors (LWRs), heavy water reactors (HWRs), gas-cooled reactors (GCRs), and liquid metal reactors (LMRs). LWRs and HWRs can generate process heat up to 280/sup 0/C, LMRs up to 540/sup 0/C, and GCRs up to 950/sup 0/C. Based on the studies considered here, the estimated process heat markets and the associated energy markets which would be supplied by the various reactor types are summarized.

Gambill, W.R.; Kasten, P.R.

1984-01-01T23:59:59.000Z

154

"1. Oahe","Hydroelectric","USCE-Missouri River District",714  

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

Dakota" Dakota" "1. Oahe","Hydroelectric","USCE-Missouri River District",714 "2. Big Bend","Hydroelectric","USCE-Missouri River District",520 "3. Big Stone","Coal","Otter Tail Power Co",476 "4. Fort Randall","Hydroelectric","USCE-Missouri River District",360 "5. Angus Anson","Gas","Northern States Power Co - Minnesota",338 "6. Buffalo Ridge II LLC","Other Renewables","Iberdrola Renewables Inc",210 "7. Groton Generating Station","Gas","Basin Electric Power Coop",169 "8. MinnDakota Wind LLC","Other Renewables","Iberdrola Renewables Inc",150

155

Hydroelectric Webinar Presentation Slides and Text Version  

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

Download presentation slides and a text version of the audio from the DOE Office of Indian Energy webinar on hydroelectric renewable energy. 

156

Report on siphon penstocks for hydroelectric projects  

DOE Green Energy (OSTI)

This report on the use of siphon penstocks for hydroelectric installations has been prepared under DOE Contract AC07-82ID12356 by Acres International Corporation and draws extensively on the information and data assembled by the following organizations: CHI Engineering Services; Clearwater Hydro; Gannett Fleming Water Resources Engineers, Inc.; Harza Engineering Company; J. Kenneth Fraser and Associates, P.C.; Mead and Hunt, Inc.; TKO Power--Ott Water Engineers, Inc.; and Williams and Broome, Inc. The purpose of the study was to review the design, construction, operation, and maintenance considerations for siphon penstocks. The discussions, data, and information presented are based on experiences with the following operational siphon penstock plants: Columbia Mills Hydroelectric Plant, Virginia; Jim Falls Minimum Flow Unit Hydro Development, Wisconsin; Lac Courte Oreilles Hydro Development, Wisconsin; Ontelaunee Hydroelectric Project, Pennsylvania; Pine Grove Dam Hydroelectric Station, Pennsylvania; Pocono Lake Hydroelectric Project, Pennsylvania; Schaads Reservoir Hydroelectric Project, California; Second Broad River Hydroelectric Project, North Carolina; Superior Dam Power Station, Michigan; Tierckenkill Falls Hydroelectric Project, New York; and Traicao Hydroelectric Project, Brazil. 71 figs., 12 tabs.

Not Available

1989-02-01T23:59:59.000Z

157

Next Generation Nuclear Plant Materials Selection and Qualification Program Plan  

SciTech Connect

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

R. Doug Hamelin; G. O. Hayner

2004-11-01T23:59:59.000Z

158

Next Generation Nuclear Plant Materials Research and Development Program Plan  

DOE Green Energy (OSTI)

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

G. O. Hayner; E.L. Shaber

2004-09-01T23:59:59.000Z

159

Miniature Hydroelectric Power Plant : EnergySmart School Inventors  

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

Miniature Hydroelectric Power Plant EnergySmart School Inventors EnergySmart School Inventors Miniature Hydroelectric Power Plant Michael Torrey Inventor: Michael Torrey The...

160

Water-Power Development, Conservation of Hydroelectric Power...  

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

Water-Power Development, Conservation of Hydroelectric Power Dams and Works (Virginia) Water-Power Development, Conservation of Hydroelectric Power Dams and Works (Virginia)...

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


161

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

SciTech Connect

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

162

Salt disposal of heat-generating nuclear waste.  

SciTech Connect

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

163

Small scale hydroelectric power potential in Nevada: a preliminary reconnaissance survey  

DOE Green Energy (OSTI)

This preliminary reconnaissance survey is intended to: develop a first estimate as to the potential number, location and characteristics of small-scale (50 kW to 15 MW) hydroelectric sites in Nevada; provide a compilation of various Federal and state laws and regulations, including tax and financing regulations, that affect small-scale hydroelectric development and provide information on sources of small-scale hydroelectric generation hardware and consultants/ contractors who do small scale hydroelectric work. The entire survey has been conducted in the office working with various available data bases. The site survey and site evaluation methods used are described, and data are tabulated on the flow, power potential, predicted capital expenditures required, etc. for 61 potential sites with measured flows and for 77 sites with derived flows. A map showing potential site locations is included. (LCL)

Cochran, G.F.; Fordham, J.W.; Richard, K.; Loux, R.

1981-04-01T23:59:59.000Z

164

HIGH EFFICIENCY GENERATION OF HYDROGEN FUELS USING NUCLEAR POWER  

SciTech Connect

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

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

2003-06-01T23:59:59.000Z

165

HIGH EFFICIENCY GENERATION OF HYDROGEN FUELS USING NUCLEAR POWER  

DOE Green Energy (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

166

Human Reliability for the Next Generation of Nuclear Experts  

Science Conference Proceedings (OSTI)

As the nuclear renaissance progresses and today s nuclear and radiological experts retire, a new generation of experts will ultimately be recruited, trained, and replace the old guard. Selecting individuals who have the attitudes and values appropriate to work in the nuclear industry and who have the best qualifications for the position will be a key to the success of this renaissance. In a world with deep divisions on political and social issues; how a State, agency, or company assures that those hired can be trusted with the access to, and responsibilities for, nuclear and/or radiological materials is an important consideration. Human interactions invariably rely on the offering of assurance and the receipt of trust. A fundamental element in any human relationship is knowing when to trust and when to doubt. When are assurances to be believed or questioned? Human reliability programs (HRP) are used to assure a person s truthfulness and loyalty to the State. An HRP program has a number of elements and may not fit all cultures in the same form. An HRP can vary in scope from simple background checks of readily available data to full field investigations and testing. This presentation discusses possible elements for an HRP from regulation to implementation and the issues related to each element. The effects of an HRP on potential recruits will be discussed.

Coates, Cameron W [ORNL; Eisele, Gerhard R [ORNL

2010-01-01T23:59:59.000Z

167

What is the role of hydroelectric power in the United States?  

Reports and Publications (EIA)

The importance of hydropower as a source of electricity generation varies by geographic region. While hydropower accounted for 6% of total U.S. electricity generation in 2010, it provided over half of the electricity in the Pacific Northwest. Because hydroelectric generation relies on precipitation, it varies widely from month to month and year to year.

2011-11-26T23:59:59.000Z

168

Potential Benefits from Improved Energy Efficiency of Key Electrical Products: The Case of India  

E-Print Network (OSTI)

generation, including hydroelectric and nuclear (which havefor nuclear and hydroelectric generation were assumed to belignite and 34% from hydroelectric, with the balance coming

McNeil, Michael; Iyer, Maithili; Meyers, Stephen; Letschert, Virginie; McMahon, James E.

2005-01-01T23:59:59.000Z

169

Fish and hydroelectricity; Engineering a better coexistence  

Science Conference Proceedings (OSTI)

This paper reports on the problems that hydroelectric plants have regarding fish populations. The utilities that operate these plants are finding that accommodating migrating fish presents unique engineering challenges, not the least of which involves designing and building systems to protect fish species whose migratory behavior remains something of a mystery. Where such systems cannot be built, the status of hydroelectric dams may be in doubt, as is now the case with several dams in the United States. A further twist in some regions in the possibility that certain migratory fish will be declared threatened or endangered-a development that could wreak havoc on the hydroelectric energy supply in those regions.

Zorpette, G.

1990-12-01T23:59:59.000Z

170

Pumped storage provides grid reliability even with net generation ...  

U.S. Energy Information Administration (EIA)

tags: electricity generation capacity hydroelectric storage. Email Updates. RSS Feeds. Facebook. Twitter. YouTube. Add us to your site.

171

Life Cycle Management Plan for Main Generator and Exciter at Palo Verde Nuclear Generating Station: Generic Version  

Science Conference Proceedings (OSTI)

As the electric power industry becomes more competitive, life cycle management (LCM) of systems, structures, and components (SSCs) becomes more important to keep nuclear power plants economically viable throughout their remaining licensed operating terms, whether 40 or 60 years. This report provides an optimized LCM plan for the main generators and exciters at the Palo Verde Nuclear Generating Station (PVNGS).

2003-09-30T23:59:59.000Z

172

International Energy Outlook 2001 - Hydroelectricity and Other...  

Gasoline and Diesel Fuel Update (EIA)

4 years to complete. Mexico Renewable energy sources remain only a small part of the energy mix in Mexico. Hydroelectricity and other renewables accounted for only 7 percent of...

173

Hydroelectric Resources on State Lands (Montana)  

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

This chapter authorizes the leasing of state lands for the development of hydroelectric resources. It provides regulations for the granting and duration of leases, as well as for the inspection of...

174

Potential hydroelectric power Mora Canal Drop. Final report  

DOE Green Energy (OSTI)

The feasibility of installing a hydroelectric power plant on the Mora Canal Drop site in Idaho was studied. It was recommended that a 1900 kW unit be installed to generate 8,113,000 kWh per year. The project should cost approximately $1.8 million. The generating cost would be between 20.3 and 22.2 mills/kWh. A local utility has offered to buy all power produced at 26 mills/kWh. No adverse environment, safety, or socio-economic effects are foreseen. (LCL)

Willer, D.C.

1978-12-01T23:59:59.000Z

175

"1. Vermont Yankee","Nuclear","Entergy Nuclear Vermont Yankee",620  

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

Vermont" Vermont" "1. Vermont Yankee","Nuclear","Entergy Nuclear Vermont Yankee",620 "2. J C McNeil","Other Renewables","City of Burlington-Electric",52 "3. Bellows Falls","Hydroelectric","TransCanada Hydro Northeast Inc.,",48 "4. Wilder","Hydroelectric","TransCanada Hydro Northeast Inc.,",41 "5. Harriman","Hydroelectric","TransCanada Hydro Northeast Inc.,",41 "6. Berlin 5","Petroleum","Green Mountain Power Corp",35 "7. Vernon","Hydroelectric","TransCanada Hydro Northeast Inc.,",34 "8. Sheldon Springs Hydroelectric","Hydroelectric","Sheldon Vermont Hydro Co., Inc.",24

176

Impact of U.S. Nuclear Generation on Greenhouse Gas Emissions  

Gasoline and Diesel Fuel Update (EIA)

Impact of U.S. Nuclear Generation Impact of U.S. Nuclear Generation on Greenhouse Gas Emissions Ronald E. Hagen, John R. Moens, and Zdenek D. Nikodem Energy Information Administration U.S. Department of Energy International Atomic Energy Agency Vienna, Austria November 6-9, 2001 iii Energy Information Administration/ Impact of U.S. Nuclear Generation on Greenhouse Gas Emissions Contents Page I. The Electric Power Industry and the Greenhouse Gas Issue . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 II. The Current Role of the U.S. Nuclear Industry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 III. The Future Role of the U.S. Nuclear Industry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 IV. Factors That Affect Nuclear Expansion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 V. Conclusion

177

Jackson Bluff Hydroelectric Project. Feasibility assessment report  

DOE Green Energy (OSTI)

A feasibility assessment study was conducted to determine if it is economical to reinstall hydroelectric generating units at the existing Jackson Bluff Dam on the Ochlockonee River in Florida. The studies and investigations have included site reconnaissance, system loads, growth rate, site hydrology, conceptual project arrangements and layouts, power output, estimates of construction costs and annual costs, economic analyses, development of a design and construction schedule and a preliminary environmental review of the proposed Project. It was concluded that the Project poses no unusual technical problems and no significant adverse environmental effects are anticipated. It shows sufficient promise of technical, economic and financial feasibility, to justify the City entering into the next phase of work, the FERC License Application, as soon as possible. The site can be restored for an investment of $9.9 to $10.4 million to establish 8.8 MW of capacity and produce 24,920 MWh of electrical energy annually, and in 10 years would save over $4 million as compared with current fuel costs for operating an oil-fueled power plant. (LCL)

Not Available

1979-03-01T23:59:59.000Z

178

Tuttle Creek Hydroelectric Project feasibility assessment report  

DOE Green Energy (OSTI)

The results are presented of a feasibility assessment study to determine if hydroelectric generation could be developed economically at the Corps of Engineers' Tuttle Creek Dam, an existing flood control structure on the Big Blue River near Manhattan, Kansas. The studies and investigations included site reconnaissance, system load characteristics, site hydrology, conceptual project arrangements and layouts, power studies, estimates of construction costs, development of capital costs, economic feasibility, development of a design and construction schedule and preliminary environmental review of the proposed Project. The dependable capacity of the Project as delivered into the existing transmission and distribution network is 12,290 kW and the average annual energy is 56,690 MWh. For the scheduled on-line date of July 1984, the Project is estimated to have a Total Investment Cost of $19,662,000 (equal to $1333/kW installed at that time frame) with an estimated annual cost for the first year of operation of $2,696,000, assuming REA financing at 9.5% interest rate. The Project is considered technically feasible and without any major environmental issues. It shows economic feasibility providing satisfactory financing terms are available. (LCL)

None

1979-03-01T23:59:59.000Z

179

Hoopa Valley Small Scale Hydroelectric Feasibility Project  

Science Conference Proceedings (OSTI)

This study considered assessing the feasibility of developing small scale hydro-electric power from seven major tributaries within the Hoopa Valley Indian Reservation of Northern California (http://www.hoopa-nsn.gov/). This study pursued the assessment of seven major tributaries of the Reservation that flow into the Trinity River. The feasibility of hydropower on the Hoopa Valley Indian Reservation has real potential for development and many alternative options for project locations, designs, operations and financing. In order to realize this opportunity further will require at least 2-3 years of intense data collection focusing on stream flow measurements at multiple locations in order to quantify real power potential. This also includes on the ground stream gradient surveys, road access planning and grid connectivity to PG&E for sale of electricity. Imperative to this effort is the need for negotiations between the Hoopa Tribal Council and PG&E to take place in order to finalize the power rate the Tribe will receive through any wholesale agreement that utilizes the alternative energy generated on the Reservation.

Curtis Miller

2009-03-22T23:59:59.000Z

180

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

DOE Green Energy (OSTI)

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

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

2009-03-01T23:59:59.000Z

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

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

SciTech Connect

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

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

2011-01-01T23:59:59.000Z

182

Indian River Hydroelectric Project Grant  

Science Conference Proceedings (OSTI)

This Final Technical Report provides a concise retrospective and summary of all facets of the Sheldon Jackson College electrical Infrastructure Renovation portion of the Indian River Hydroelectric Project Grant of the City and Borough of Sitka, Alaska. The Project Overview describes the origins of the project, the original conditions that provided the impetus for the grant funding, how the grant amendment was developed, the conceptual design development, and the actual parameters of the final project as it went out to bid. The Project Overview also describes the ''before and after'' conditions of the project. The Objectives division of this Final Technical Report describes the amendment-funded goals of the project. It also describes the milestones of project development and implementation, as well as, the rationale behind the milestone array. The Description of Activities Performed division of this report provides an in-depth chronological analysis of progressive project implementation. Photographs will provide further illustration of particular functional aspects of the renovation project within project parameters. The Conclusions and Recommendations division of this report provides a comprehensive retrospective analysis of the project.

Rebecca Garrett

2005-04-29T23:59:59.000Z

183

NEXT GENERATION NUCLEAR PLANT LICENSING BASIS EVENT SELECTION WHITE PAPER  

SciTech Connect

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

Mark Holbrook

2010-09-01T23:59:59.000Z

184

Next Generation Nuclear Plant Resilient Control System Functional Analysis  

SciTech Connect

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

Lynne M. Stevens

2010-07-01T23:59:59.000Z

185

Property exempt from taxation: nuclear generation facility property...  

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

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....

186

Global nuclear generation capacity totaled more than 370 gigawatts ...  

U.S. Energy Information Administration (EIA)

China—where plans for large increases in nuclear capacity had been announced—instituted a temporary moratorium on new approvals for nuclear power ...

187

Investing in the Next Generation of U.S. Nuclear Energy Leaders |  

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

the Next Generation of U.S. Nuclear Energy Leaders the Next Generation of U.S. Nuclear Energy Leaders Investing in the Next Generation of U.S. Nuclear Energy Leaders August 9, 2011 - 5:12pm Addthis Assistant Secretary Lyons Assistant Secretary Lyons Assistant Secretary for Nuclear Energy As part of the Energy Department's Nuclear Energy University Programs (NEUP) annual workshop, I met today with professors from across the country and announced awards of up to $39 million for research projects aimed at developing cutting-edge nuclear energy technologies. The awards will also help train and educate the next generation of nuclear industry leaders in the U.S. These projects, led by 31 universities in more than 20 states, will help to enable the safe, secure and sustainable expansion of nuclear energy in the United States.

188

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

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

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

189

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

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

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

190

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

SciTech Connect

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

Dr. Mark Schanfein; Philip Casey Durst

2012-07-01T23:59:59.000Z

191

ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology  

SciTech Connect

We describe the next generation general purpose Evaluated Nuclear Data File, ENDF/B-VII.0, of recommended nuclear data for advanced nuclear science and technology applications. The library, released by the U.S. Cross Section Evaluation Working Group (CSEWG) in December 2006, contains data primarily for reactions with incident neutrons, protons, and photons on almost 400 isotopes. The new evaluations are based on both experimental data and nuclear reaction theory predictions. The principal advances over the previous ENDF/B-VI library are the following: (1) New cross sections for U, Pu, Th, Np and Am actinide isotopes, with improved performance in integral validation criticality and neutron transmission benchmark tests; (2) More precise standard cross sections for neutron reactions on H, {sup 6}Li, {sup 10}B, Au and for {sup 235,238}U fission, developed by a collaboration with the IAEA and the OECD/NEA Working Party on Evaluation Cooperation (WPEC); (3) Improved thermal neutron scattering; (4) An extensive set of neutron cross sections on fission products developed through a WPEC collaboration; (5) A large suite of photonuclear reactions; (6) Extension of many neutron- and proton-induced reactions up to an energy of 150 MeV; (7) Many new light nucleus neutron and proton reactions; (8) Post-fission beta-delayed photon decay spectra; (9) New radioactive decay data; and (10) New methods developed to provide uncertainties and covariances, together with covariance evaluations for some sample cases. The paper provides an overview of this library, consisting of 14 sublibraries in the same, ENDF-6 format, as the earlier ENDF/B-VI library. We describe each of the 14 sublibraries, focusing on neutron reactions. Extensive validation, using radiation transport codes to simulate measured critical assemblies, show major improvements: (a) The long-standing underprediction of low enriched U thermal assemblies is removed; (b) The {sup 238}U, {sup 208}Pb, and {sup 9}Be reflector biases in fast systems are largely removed; (c) ENDF/B-VI.8 good agreement for simulations of highly enriched uranium assemblies is preserved; (d) The underprediction of fast criticality of {sup 233,235}U and {sup 239}Pu assemblies is removed; and (e) The intermediate spectrum critical assemblies are predicted more accurately. We anticipate that the new library will play an important role in nuclear technology applications, including transport simulations supporting national security, nonproliferation, advanced reactor and fuel cycle concepts, criticality safety, medicine, space applications, nuclear astrophysics, and nuclear physics facility design. The ENDF/B-VII.0 library is archived at the National Nuclear Data Center, BNL. The complete library, or any part of it, may be retrieved from www.nndc.bnl.gov.

Chadwick, M B; Oblozinsky, P; Herman, M; Greene, N M; McKnight, R D; Smith, D L; Young, P G; MacFarlane, R E; Hale, G M; Haight, R C; Frankle, S; Kahler, A C; Kawano, T; Little, R C; Madland, D G; Moller, P; Mosteller, R; Page, P; Talou, P; Trellue, H; White, M; Wilson, W B; Arcilla, R; Dunford, C L; Mughabghab, S F; Pritychenko, B; Rochman, D; Sonzogni, A A; Lubitz, C; Trumbull, T H; Weinman, J; Brown, D; Cullen, D E; Heinrichs, D; McNabb, D; Derrien, H; Dunn, M; Larson, N M; Leal, L C; Carlson, A D; Block, R C; Briggs, B; Cheng, E; Huria, H; Kozier, K; Courcelle, A; Pronyaev, V; der Marck, S

2006-10-02T23:59:59.000Z

192

Laser Inertial Fusion-based Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System  

E-Print Network (OSTI)

and Hydroelectric 1.1.3 Nuclear Energy . . . . . . . . .Gain GNEP Global Nuclear Energy Partnership HEU HighlyIn Progress in Nuclear Energy, 17. Pergamon Press, 1986.

Kramer, Kevin James

2010-01-01T23:59:59.000Z

193

Long-term outlook for nuclear generation depends on lifetime of ...  

U.S. Energy Information Administration (EIA)

These projects are currently under construction. Overall generation from nuclear power grows by 14.3% from 2011 through 2040 (see chart below).

194

Next Generation Nuclear Plant Materials Research and Development Program Plan  

SciTech Connect

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

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

2005-09-01T23:59:59.000Z

195

Microsoft PowerPoint - Why Nuclear Energy New Template  

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

Why Nuclear Energy? Why Nuclear Energy? Why Nuclear Energy? Nuclear energy already meets a significant share of the world's energy needs * There are 441 nuclear reactors in operation in 31 countries * These plants generate electricity for nearly a billion people, and account for 17% of the world's electricity production * The U.S. has 103 operating reactors producing 20% of the nation's electricity * Illinois leads all states with the highest share of nuclear (51%) * Technology significantly developed at Argonne forms the basis of all nuclear energy systems used worldwide Nuclear power is reliable and economical * In 2001, U.S. nuclear plants produced electricity for 1.68 cents per kilowatt-hour on average, second only to hydroelectric power among baseload generation options * U.S. nuclear power plant performance has steadily

196

Main Generator Seal Oil Supply Reliability Improvements at Southern California Edison's San Onofre Nuclear Generating Station  

Science Conference Proceedings (OSTI)

This paper presents the justification for the approach, details and results of the Main Generator Seal Oil System reliability enhancements on the San Onofre Nuclear Generating Station, SONGS. The SONGS, Unit 3 experienced substantial turbine damage in early 2001 after the turbine bearings lubrication oil supply failed. During a loss of off-site power incident, power was lost to the two AC powered turbine lubrication oil pumps due to a breaker failure in the switchgear and the DC powered emergency bearing lubricating oil pump failed to start due to a breaker trip. The SONGS turbine generators coasted down from full speed to a full stop without lubricating oil. This resulted in significant bearing, journal and steam path damage that required a four-month duration repair outage during a time period where electricity was in short supply in the State of California. The generator hydrogen sealing system remained operable during this event, however it was recognized during the event follow up investigation that this system had vulnerabilities to failure similar to the bearing lubrication system. In order to prevent a reoccurrence of this extremely costly event, SONGS has taken actions to modify both of these critical turbine generator systems by adding additional, continuously operating pumps with a new, independent power source and independently routed cables. The main challenge was to integrate the additional equipment into the existing lubrication and seal oil systems. The lubrication Oil System was the first system to be retro-fitted and these results already have been presented. Reference 2. This paper provides the result of the reliability enhancements for the Main Generator Seal Oil System, which concludes the turbine/generator critical oil systems reliability improvements, performed by SONGS. It is worth noting that the design team discovered and corrected a number of other significant operational issues, which had been present from the early days and also learned a great deal of detailed information about this vital system during the project. The SONGS approach and findings are discussed in this paper, as well as a summary of the work performed. This technical paper will be of interest to utilities with a need to improve turbine generator reliability issues. (authors)

Simma, Fred Y.; Chetwynd, Russell J. [Southern California Edison, P.O. Box 800, Rosemead, CA 91770 (United States); Rowe, Stuart A. [Alstom Power Service (United States)

2006-07-01T23:59:59.000Z

197

Risk Framework for the Next Generation Nuclear Power Plant Construction  

E-Print Network (OSTI)

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

Yeon, Jaeheum 1981-

2012-12-01T23:59:59.000Z

198

Next Generation Nuclear Plant Research and Development Program Plan  

DOE Green Energy (OSTI)

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

None

2005-01-01T23:59:59.000Z

199

Assessment of next generation nuclear plant intermediate heat exchanger design.  

DOE Green Energy (OSTI)

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

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

2008-10-17T23:59:59.000Z

200

Paving the path for next-generation nuclear energy | Department of Energy  

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

Paving the path for next-generation nuclear energy Paving the path for next-generation nuclear energy Paving the path for next-generation nuclear energy May 6, 2013 - 2:26pm Addthis Renewed energy and enhanced coordination are on the horizon for an international collaborative that is advancing new, safer nuclear energy systems. Renewed energy and enhanced coordination are on the horizon for an international collaborative that is advancing new, safer nuclear energy systems. Deputy Assistant Secretary Kelly Deputy Assistant Secretary Kelly Deputy Assistant Secretary for Nuclear Reactor Technologies Nuclear power reactors currently under construction worldwide boast modern safety and operational enhancements that were designed by the global nuclear energy industry and enhanced through research and development (R&D)

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201

Small-Scale Hydroelectric Power Demonstration Project. Pennsylvania Hydroelectric Development Corporation Flat Rock Dam: Project summary report  

DOE Green Energy (OSTI)

The US Department of Energy Field Office, Idaho, Small-Scale Hydroelectric Power Program was initiated in conjunction with the restoration of three power generating plants in Idaho Falls, Idaho, following damage caused by the Teton Dam failure on June 5, 1976. There were many parties interested in this project, including the state and environmental groups, with different concerns. This report was prepared by the developer and describes the design alternatives the applicant provided in an attempt to secure the Federal Energy Regulatory Commission license. Also included are correspondence between the related parties concerning the project, major design alternatives/project plan diagrams, the license, and energy and project economics.

Gleeson, L.

1991-12-01T23:59:59.000Z

202

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

Science Conference Proceedings (OSTI)

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

L.E. Demick

2011-10-01T23:59:59.000Z

203

Next Generation Nuclear Plant Methods Technical Program Plan  

Science Conference Proceedings (OSTI)

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

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

2010-12-01T23:59:59.000Z

204

Next Generation Nuclear Plant Methods Technical Program Plan  

Science Conference Proceedings (OSTI)

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

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

2007-01-01T23:59:59.000Z

205

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

Science Conference Proceedings (OSTI)

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

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

2010-09-01T23:59:59.000Z

206

A knowledge representation model for the nuclear power generation domain  

Science Conference Proceedings (OSTI)

A knowledge representation model for the nuclear power field is proposed. The model is a generalized production rule function inspired by a neural network approach that enables the representation of physical systems of nuclear power plants. The article ... Keywords: Knowledge representation, Nuclear power plant, Physical systems, Production rules

Thiago Tinoco Pires

2007-11-01T23:59:59.000Z

207

"1. Palo Verde","Nuclear","Arizona Public Service Co",3937 "2. Navajo","Coal","Salt River Project",2250  

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

Arizona" Arizona" "1. Palo Verde","Nuclear","Arizona Public Service Co",3937 "2. Navajo","Coal","Salt River Project",2250 "3. Gila River Power Station","Gas","Gila River Power Station LP",2060 "4. Springerville","Coal","Tucson Electric Power Co",1618 "5. Glen Canyon Dam","Hydroelectric","U S Bureau of Reclamation",1312 "6. Santan","Gas","Salt River Project",1227 "7. Mesquite Generating Station","Gas","Mesquite Power LLC",1073 "8. Harquahala Generating Project","Gas","New Harquahala Generating Co, LLC",1054 "9. Hoover Dam","Hydroelectric","U S Bureau of Reclamation",1040

208

Nuclear Maintenance Applications Center: Emergency Diesel Generator Single Component Vulnerability Review Guidance.  

Science Conference Proceedings (OSTI)

This report provides guidance to owners and operators of nuclear power plants on performing emergency diesel generator (EDG) system single component vulnerability reviews. This guidance was developed based on a recommendation from the nuclear industry’s EDG Technical Advisory Committee (TAC) that plants perform a single component vulnerability review as discussed in the Institute of Nuclear Power Operations’ Industry Experience Report ...

2013-11-01T23:59:59.000Z

209

Next Generation Nuclear Plant Research and Development Program Plan  

DOE Green Energy (OSTI)

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

P. E. MacDonald

2005-01-01T23:59:59.000Z

210

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

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

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

211

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

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

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

212

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...

213

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...

214

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...

215

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

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

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

216

A Technology Roadmap for Generation IV Nuclear Energy Systems Executive Summary  

SciTech Connect

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.

2003-03-01T23:59:59.000Z

217

Aging of nuclear station diesel generators: Evaluation of operating and expert experience: Workshop  

Science Conference Proceedings (OSTI)

Pacific Northwest Laboratory (PNL) evaluated operational and expert experience pertaining to the aging degradation of diesel generators in nuclear service. The research, sponsored by the US Nuclear Regulatory Commission (NRC), identified and characterized the contribution of aging to emergency diesel generator failures. This report, Volume II, reports the results of an industry-wide workshop held on May 28 and 29, 1986, to discuss the technical issues associated with aging of nuclear service emergency diesel generators. The technical issues discussed most extensively were: man/machine interfaces, component interfaces, thermal gradients of startup and cooldown and the need for an accurate industry database for trend analysis of the diesel generator system.

Hoopingarner, K.R.; Vause, J.W.

1987-08-01T23:59:59.000Z

218

Electricity generation from coal and natural gas both increased ...  

U.S. Energy Information Administration (EIA)

Coal generation shares declined in some regions ... the share of natural gas-fired power generation is most influenced by the availability of hydroelectric power, ...

219

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

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

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

220

The development and use of radionuclide generators in nuclear medicine -- recent advances and future perspectives  

SciTech Connect

Although the trend in radionuclide generator research has declined, radionuclide generator systems continue to play an important role in nuclear medicine. Technetium-99m obtained from the molybdenum-99/technetium-99m generator system is used in over 80% of all diagnostic clinical studies and there is increasing interest and use of therapeutic radioisotopes obtained from generator systems. This paper focuses on a discussion of the major current areas of radionuclide generator research, and the expected areas of future research and applications.

Knapp, F.F. Jr.

1998-03-01T23:59:59.000Z

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

Membranes for H2 generation from nuclear powered thermochemical cycles.  

DOE Green Energy (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

222

Table 9.1 Nuclear Generating Units, 1955-2011  

U.S. Energy Information Administration (EIA)

1 Data in columns 1–3 are based on the U.S. Nuclear Regulatory Commission (NRC) regulation 10 CFR Part 50. Data in columns 4–6 are based on the NRC regulation 10 ...

223

Observations on A Technology Roadmap for Generation IV Nuclear...  

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

the U.S. will depend greatly on the continued success of currently operating light water nuclear power plants and the ordering of new installations in the short term. DOE needs to...

224

Nuclear economics 2000: Deterministic and probabilistic projections of nuclear and coal electric power generation costs for the year 2000  

SciTech Connect

The total busbar electric generating costs were estimated for locations in ten regions of the United States for base-load nuclear and coal-fired power plants with a startup date of January 2000. For the Midwest region a complete data set that specifies each parameter used to obtain the comparative results is supplied. When based on the reference set of input variables, the comparison of power generation costs is found to favor nuclear in most regions of the country. Nuclear power is most favored in the northeast and western regions where coal must be transported over long distances; however, coal-fired generation is most competitive in the north central region where large reserves of cheaply mineable coal exist. In several regions small changes in the reference variables could cause either option to be preferred. The reference data set reflects the better of recent electric utility construction cost experience (BE) for nuclear plants. This study assumes as its reference case a stable regulatory environment and improved planning and construction practices, resulting in nuclear plants typically built at the present BE costs. Today's BE nuclear-plant capital investment cost model is then being used as a surrogate for projected costs for the next generation of light-water reactor plants. An alternative analysis based on today's median experience (ME) nuclear-plant construction cost experience is also included. In this case, coal is favored in all ten regions, implying that typical nuclear capital investment costs must improve for nuclear to be competitive.

Williams, K.A.; Delene, J.G.; Fuller, L.C.; Bowers, H.I.

1987-06-01T23:59:59.000Z

225

Installation of a Low Flow Unit at the Abiquiu Hydroelectric Facility  

Science Conference Proceedings (OSTI)

Final Technical Report for the Recovery Act Project for the Installation of a Low Flow Unit at the Abiquiu Hydroelectric Facility. The Abiquiu hydroelectric facility existed with two each 6.9 MW vertical flow Francis turbine-generators. This project installed a new 3.1 MW horizontal flow low flow turbine-generator. The total plant flow range to capture energy and generate power increased from between 250 and 1,300 cfs to between 75 and 1,550 cfs. Fifty full time equivalent (FTE) construction jobs were created for this project - 50% (or 25 FTE) were credited to ARRA funding due to the ARRA 50% project cost match. The Abiquiu facility has increased capacity, increased efficiency and provides for an improved aquatic environment owing to installed dissolved oxygen capabilities during traditional low flow periods in the Rio Chama. A new powerhouse addition was constructed to house the new turbine-generator equipment.

Jack Q. Richardson

2012-06-28T23:59:59.000Z

226

Hydroelectric power provides a cheap source of electricity with few carbon emissions. Yet, reservoirs are not operated sustainably, which we define as meeting societal needs for water and power while protecting long-term health of the river ecosystem. Reservoirs that generate hydropower are typically operated with the goal of maximizing energy reve  

Science Conference Proceedings (OSTI)

Hydroelectric power provides a cheap source of electricity with few carbon emissions. Yet, reservoirs are not operated sustainably, which we define as meeting societal needs for water and power while protecting long-term health of the river ecosystem. Reservoirs that generate hydropower are typically operated with the goal of maximizing energy revenue, while meeting other legal water requirements. Reservoir optimization schemes used in practice do not seek flow regimes that maximize aquatic ecosystem health. Here, we review optimization studies that considered environmental goals in one of three approaches. The first approach seeks flow regimes that maximize hydropower generation, while satisfying legal requirements, including environmental (or minimum) flows. Solutions from this approach are often used in practice to operate hydropower projects. In the second approach, flow releases from a dam are timed to meet water quality constraints on dissolved oxygen (DO), temperature and nutrients. In the third approach, flow releases are timed to improve the health of fish populations. We conclude by suggesting three steps for bringing multi-objective reservoir operation closer to the goal of ecological sustainability: (1) conduct research to identify which features of flow variation are essential for river health and to quantify these relationships, (2) develop valuation methods to assess the total value of river health and (3) develop optimal control softwares that combine water balance modelling with models that predict ecosystem responses to flow.

Jager, Yetta [ORNL; Smith, Brennan T [ORNL

2008-02-01T23:59:59.000Z

227

Lessons Learned: Pangue Hydroelectric | Open Energy Information  

Open Energy Info (EERE)

Lessons Learned: Pangue Hydroelectric Lessons Learned: Pangue Hydroelectric Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Lessons Learned: Pangue Hydroelectric Agency/Company /Organization: International Finance Corporation Sector: Energy Focus Area: Renewable Energy, Hydro Topics: Background analysis Resource Type: Lessons learned/best practices Website: www.ifc.org/ifcext/sustainability.nsf/AttachmentsByTitle/p_pangue_summ Country: Chile UN Region: Latin America and the Caribbean Coordinates: -35.675147°, -71.542969° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":-35.675147,"lon":-71.542969,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

228

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

Science Conference Proceedings (OSTI)

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

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

2011-05-01T23:59:59.000Z

229

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

230

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

SciTech Connect

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

John Collins

2009-01-01T23:59:59.000Z

231

Design Features and Technology Uncertainties for the Next Generation Nuclear Plant  

Science Conference Proceedings (OSTI)

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

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

2004-06-01T23:59:59.000Z

232

Sharing the burden of climate change stabilization: An energy sector perspective  

E-Print Network (OSTI)

Diesel Nat. Gas Nuclear Hydroelectric. Biomass Wind Solar (electricity generation from hydroelectric power plants, windWe also observe more hydroelectric power being used in the

Wagner, Fabian; Sathaye, Jayant

2006-01-01T23:59:59.000Z

233

The Natural Number of Forward Markets for Electricity  

E-Print Network (OSTI)

is generated from hydroelectric resources, supply of whichsuch as nuclear and hydroelectric plants whose availabilityrelevance are the hydroelectric units, which serve 40% of

Suenaga, Hiroaki; Williams, Jeffrey

2005-01-01T23:59:59.000Z

234

Data collection and analysis in support of risk assessment for hydroelectric stations  

DOE Green Energy (OSTI)

This project is to provide the U.S. Army Corps of Engineers with a risk analysis that evaluates the non-routine closure of water flow through the turbines of powerhouses along the Columbia and Snake Rivers. The project is divided into four phases. Phase 1 efforts collected and analyzed relevant plant failure data for hydroelectric generating stations in the United States and Canada. Results from the Phase 1 efforts will be used to assess the risk (probability times consequences) associated with non-routine shut down of hydroelectric stations, which will be performed in the remaining phases of the project. Results of this project may be used to provide policy recommendations regarding operation and maintenance of hydroelectric stations. The methodology used to complete the Phase 1 of the project is composed of data collection and analysis activities. Data collection included performing site visits, conducting a data survey of hydroelectric stations, conducting an expert panel workshop, and reviewing and tabulating failure data from generic sources. Data analysis included estimating failure rates obtained from the survey data, expert judgment elicitation process, generic data, and combining these failure rates to produce final failure rate parameters. This paper summarizes the data collection analysis, results and discussions for the Phase 1 efforts.

Vo, T.V.; Mitts, T.M.; Phan, H.K.; Blackburn, T.R.; Casazza, L.O.

1995-10-01T23:59:59.000Z

235

Fourth generation nuclear weapons: Military effectiveness and collateral effects, Report ISRI-05-03  

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-charge jets and forged fragments, enhanced prompt radiation effects, reduced collateral damage and residual radioactivity, etc.

Andre Gsponer

2005-01-01T23:59:59.000Z

236

Asia Power Leibo Hydroelectricity Co Ltd | Open Energy Information  

Open Energy Info (EERE)

Sichuan Province, China Sector Hydro Product China-based developer and operator of small hydro plants. References Asia Power (Leibo) Hydroelectricity Co Ltd1 LinkedIn...

237

Today in Energy - Seasonal hydroelectric output drives down ...  

U.S. Energy Information Administration (EIA)

Increased hydroelectric output in the Pacific Northwest drove daily, on-peak prices of electricity below $10 per megawatthour in late April (see chart above) at the ...

238

DOE Office of Indian Energy Foundational Course: Hydroelectric  

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

produce enough electricity for a home, farm, ranch, or village. Source: http:www1.eere.energy.govwaterhydroplanttypes.html Types of Hydroelectric Power 9 * Waterwheels, used...

239

Feasibility study for Boardman River hydroelectric power. Final report  

DOE Green Energy (OSTI)

The feasibility of generating additional hydroelectric power from five consecutive existing dams located on the Boardman River in Grand Traverse County and Traverse City, Michigan, was investigated. The potential hydropower production capabilities, in terms of base load power and peak load power, the legal-institutional-environmental constraints, and the economic feasibility, including capital investment, operating costs and maintenance costs, were evaluated for each of the five dam sites individually and as a series of co-dependent facilities. The impact of installing fish passages at each site was analyzed separately. The feasibility assessment utilized the present worth analytical method, considering revenue based on thirty mills/kWh for power, 0.4% general economy escalation rate, and a 6% net income to the municipal utility. The sensitivity of fuel costs increasing at a different rate than the general price-escalation was tested by allowing the increase in fuel costs to vary from 3 to 8% per year. Assuming fuel costs increase at the same rate as the general economy, it is feasible to update, retrofit, renovate, and install hydroelectric generating capacity at Sabin, Boardman and Brown Bridge. Rehabilitation of Union Street and Keystone is also feasible but somewhat less attractive. Operating the dams as a co-dependent system has environmental advantages and can provide additional revenue through peak load power rates. A development plan to implement the above is outlined utilizing an ownership arrangement whereby Grand Traverse County provides easements for Sabin and Boardman Dams. The plan calls for operation of the system by Traverse City.

None

1979-02-22T23:59:59.000Z

240

Next Generation CANDU Technology: Competitive Design for the Nuclear Renaissance  

SciTech Connect

AECL has developed the design for a next generation of CANDU{sup R} plants by marrying a set of enabling technologies to well-established successful CANDU features. The basis for the design is to replicate or adapt existing CANDU components for a new core design. By adopting slightly enriched uranium fuel, a core design with light water coolant, heavy water moderator and reflector has been defined, based on the existing CANDU fuel channel module. This paper summarizes the main features and characteristics of the reference next-generation CANDU design. The progress of the next generation of CANDU design program in meeting challenging cost, schedule and performance targets is described. AECL's cost reduction methodology is summarized as an integral part of the design optimization process. Examples are given of cost reduction features together with enhancement of design margins. (authors)

Hopwood, J.M.; Hedges, K.R.; Pakan, M. [Atomic Energy of Canada Ltd., Ontario (Canada)

2002-07-01T23:59:59.000Z

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

Temporary Grounding and Bonding Practices in Nuclear Electric Generating Stations  

Science Conference Proceedings (OSTI)

Correct written temporary grounding practices inside generating stations are an important industrial safety issue, as well as an important plant status control issue. An extraordinary amount of regulations, standards, and information is available for temporary grounding practices in transmission and delivery (T&D), but very little is written about inside plant practices.

2008-12-22T23:59:59.000Z

242

PP-89-1 Bangor Hydro-Electric Company | Department of Energy  

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

PP-89-1 Bangor Hydro-Electric Company PP-89-1 Bangor Hydro-Electric Company Presidental permit authorizing Bangor Hydro-Electric Company to construc, operate and maintain electric...

243

PP-89-1 Bangor Hydro-Electric Company | Department of Energy  

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

-1 Bangor Hydro-Electric Company PP-89-1 Bangor Hydro-Electric Company Presidental permit authorizing Bangor Hydro-Electric Company to construc, operate and maintain electric...

244

Solar nuclear energy generation and the chlorine solar neutrino experiment  

E-Print Network (OSTI)

The study of solar neutrinos may provide important insights into the physics of the central region of the Sun. Four solar neutrino experiments have confirmed the solar neutrino problem but do not clearly indicate whether solar physics, nuclear physics, or neutrino physics have to be improved to solve it. Nonlinear relations among the different neutrino fluxes are imposed by two coupled systems of differential equations governing the internal structure and time evolution of the Sun. We assume that the results of the four neutrino experiments are correct and are concerned not with the discrepancy between the average rate and the predicted rate, but with a possible time dependence of the argon production rate as revealed in the Homestake experiment over a time period of 20 years. Based on the subtlety of the solar neutrino problem we review here quantitatively the physical laws employed for understanding the internal solar structure and conjecture that the interlink between specific nuclear reactions of the PPIII-branch of the proton-proton chain may allow the high-energy solar neutrino flux to vary over time.

H. J. Haubold; A. M. Mathai

1994-05-18T23:59:59.000Z

245

SOLAR NUCLEAR ENERGY GENERATION AND THE CHLORINE SOLAR NEUTRINO EXPERIMENT  

E-Print Network (OSTI)

The study of solar neutrinos may provide important insights into the physics of the central region of the Sun. Four solar neutrino experiments have confirmed the solar neutrino problem but do not clearly indicate whether solar physics, nuclear physics, or neutrino physics have to be improved to solve it. Nonlinear relations among the different neutrino fluxes are imposed by two coupled systems of differential equations governing the internal structure and time evolution of the Sun. We assume that the results of the four neutrino experiments are correct and are concerned not with the discrepancy between the average rate and the predicted rate, but with a possible time dependence of the argon production rate as revealed in the Homestake experiment over a time period of 20 years. Based on the subtlety of the solar neutrino problem we review here qualitatively the physical laws employed for understanding the internal solar structure and conjecture that the interlink between specific nuclear reactions of the PPIII-branch of the proton-proton chain may allow

H. J. Haubold

1994-01-01T23:59:59.000Z

246

Aging of nuclear station diesel generators: Evaluation of operating and expert experience: Phase 1, Study  

Science Conference Proceedings (OSTI)

Pacific Northwest Laboratory evaluated operational and expert experience pertaining to the aging degradation of diesel generators in nuclear service. The research, sponsored by the US Nuclear Regulatory Commission (NRC), identified and characterized the contribution of aging to emergency diesel generator failures. This report, Volume I, reviews diesel-generator experience to identify the systems and components most subject to aging degradation and isolates the major causes of failure that may affect future operational readiness. Evaluations show that as plants age, the percent of aging-related failures increases and failure modes change. A compilation is presented of recommended corrective actions for the failures identified. This study also includes a review of current, relevant industry programs, research, and standards. Volume II reports the results of an industry-wide workshop held on May 28 and 29, 1986 to discuss the technical issues associated with aging of nuclear service emergency diesel generators.

Hoopingarner, K.R.; Vause, J.W.; Dingee, D.A.; Nesbitt, J.F.

1987-08-01T23:59:59.000Z

247

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

Science Conference Proceedings (OSTI)

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

2013-03-27T23:59:59.000Z

248

Nuclear Maintenance Applications Center: Emergency Diesel Generator Control Systems  

Science Conference Proceedings (OSTI)

Emergency diesel generators (EDGs) have been a subject of industry attention since the 1980s because of their importance to plant safety, and a key point of focus has been their control systems. To support long-term reliability and availability of EDG control systems, the Electric Power Research Institute (EPRI) has developed this report, which highlights maintenance tasks and strategies that can reduce failures of control system components. The report draws from the knowledge of industry EDG experts and...

2012-08-06T23:59:59.000Z

249

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

E-Print Network (OSTI)

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

unknown authors

2005-01-01T23:59:59.000Z

250

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

SciTech Connect

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

251

Potential growth of nuclear and coal electricity generation in the US  

SciTech Connect

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

252

ORIGINAL ARTICLE Ecosystem services and hydroelectricity in Central America  

E-Print Network (OSTI)

addresses only those measures that affect the operation of the Northwest's hydroelectric power system of the hydroelectric power system. Some energy is lost when it is spilled and some energy is shifted out of winter to maintain current river operations. However, as more information is gathered and more research is conducted

Paris-Sud XI, Université de

253

Maintaining and Monitoring Dissolved Oxygen at Hydroelectric Projects: Status Report  

Science Conference Proceedings (OSTI)

This report is an update of EPRI's 1990 report, "Assessment and Guide for Meeting Dissolved Oxygen Water Quality Standards for Hydroelectric Plant Discharges" (GS-7001). The report provides an updated review of technologies and techniques for enhancing dissolved oxygen (DO) levels in reservoirs and releases from hydroelectric projects and state-of-the-art methods, equipment, and techniques for monitoring DO.

2002-05-28T23:59:59.000Z

254

Interactive Trouble Condition Sign Discovery for Hydroelectric Power Plants  

Science Conference Proceedings (OSTI)

Kyushu Electric Power Co.,Inc. collects different sensor data and weather information (hereafter, operation data) to maintain the safety of hydroelectric power plants while the plants are running. It is very rare to occur trouble condition in the plants. ... Keywords: Data Mining, Hydroelectric Power Plant, Support Vector Machine, Trouble Condition Detection

Takashi Onoda; Norihiko Ito; Hironobu Yamasaki

2009-07-01T23:59:59.000Z

255

On construction sequence optimization of cascaded hydroelectric stations  

Science Conference Proceedings (OSTI)

In basin planning, many hydroelectric stations are to be constructed in a river in order to develop the water energy cascadedly. If there were no constraints on financial resources, material resources, and manpower, all the stations would be constructed ... Keywords: algorithm, hydroelectric station, optimization, profits

Xingming Sun; Huowang Chen; Jianping Yin; Xinhai Jin; Aiming Yang; Changyun Li

2002-01-01T23:59:59.000Z

256

Electricity generation from coal and natural gas both ...  

U.S. Energy Information Administration (EIA)

Energy use in homes, commercial buildings, ... the share of natural gas-fired power generation is most influenced by the availability of hydroelectric power, ...

257

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

258

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

259

Nuclear Maintenance Applications Center: Post-Trip Voltage Prediction at Nuclear and Other Generating Stations  

Science Conference Proceedings (OSTI)

The objective of this Electric Power Research Institute (EPRI) project is to investigate the possibility of predicting the switchyard voltage in a nuclear power plant (NPP) following a trip of a nuclear unit. Two methods of post-trip voltage prediction are investigated. The first method, called the V-Q method, uses minimal local plant information (such as unit operating conditionsactive and reactive power output and pre-trip voltage) to predict post-trip voltage based on the sensitivity of voltage to the...

2009-06-30T23:59:59.000Z

260

"1. Chalk Point LLC","Coal","Mirant Chalk Point LLC",2347 "2. Calvert Cliffs Nuclear Power Plant","Nuclear","Calvert Cliffs Nuclear PP Inc",1705  

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

Maryland" Maryland" "1. Chalk Point LLC","Coal","Mirant Chalk Point LLC",2347 "2. Calvert Cliffs Nuclear Power Plant","Nuclear","Calvert Cliffs Nuclear PP Inc",1705 "3. Morgantown Generating Plant","Coal","Mirant Mid-Atlantic LLC",1477 "4. Brandon Shores","Coal","Constellation Power Source Gen",1273 "5. Herbert A Wagner","Coal","Constellation Power Source Gen",976 "6. Dickerson","Coal","Mirant Mid-Atlantic LLC",844 "7. NAEA Rock Springs LLC","Gas","NAEA Rock Springs LLC",652 "8. Conowingo","Hydroelectric","Exelon Power",572

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

Nuclear electric generation: Political, social, and economic cost and benefit to Indonesia. Master`s thesis  

SciTech Connect

Indonesia, the largest archipelagic country with a population the fourth biggest in the world, is now in the process of development. It needs a large quantity of energy electricity to meet the industrial and household demands. The currently available generating capacity is not sufficient to meet the electricity demand for the rapidly growing industries and the increasing population. In order to meet the future demand for electricity, new generating capacity is required to be added to the current capacity. Nuclear electricity generation is one possible alternative to supplement Indonesia`s future demand of electricity. This thesis investigates the possibility of developing nuclear electricity generation in Indonesia, considering the political, social, and economic cost and benefit to Indonesia.

Waliyo

1994-12-01T23:59:59.000Z

262

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

Science Conference Proceedings (OSTI)

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

2003-09-30T23:59:59.000Z

263

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

SciTech Connect

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

Pete Jordan

2010-09-01T23:59:59.000Z

264

Spent Nuclear Fuel project photon heat deposition calculation for hygrogen generation within MCO  

DOE Green Energy (OSTI)

Three types of water conditions are analyzed for nuclear heat deposition in a MCO: fully flooded, thick film, and thin film. These heat deposition rates within water can be used to determine gas generation during the different phases of Spent Fuel removal and processing for storage.

Lan, J.S.

1996-08-01T23:59:59.000Z

265

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

Science Conference Proceedings (OSTI)

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

2003-09-30T23:59:59.000Z

266

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

SciTech Connect

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

267

Vermont Marble Company, Proctor, Vermont: Otter Creek hydroelectric feasibility report  

DOE Green Energy (OSTI)

Vermont Marble Company (VMCO) owns and operates four hydroelectric projects in a 50-mile reach of Otter Creek in west central Vermont. This study concerns three of the installations - Center Rutland, Beldens, and Huntington Falls. The fourth site is known as Proctor and will be studied separately. All four plants operate as run-of-river stations, and the limited reservoir storage capacity places severe limitations on any other type of operation. The plants are presently operating at much lower outputs than can be obtained, because they do not use the available discharge and head. The results show that, under the assumptions made in this study, Beldens and Huntington Falls can be economically improved. The rehabilitation of the Center Rutland plant did not look economically attractive. However, the improvement of Center Rutland should not be eliminated from further consideration, because it could become economically attractive if the cost of energy starts escalating at a rate of around 10% per year. The study included a brief appraisal of the existing generating facilities and condition of existing concrete structures, a geological reconnaissance of the sites, analysis of the power potential, flood studies, technical and economic investigations and comparative evaluations of the alternatives for developing the streamflow for power generation, selection of the most suitable alternative, financial analysis, preparation of drawings, and preparation of detailed quantity and cost estimates.

None

1979-02-01T23:59:59.000Z

268

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

2007-07-27T23:59:59.000Z

269

Modeling of a horizontal steam generator for the submerged nuclear power station concept  

SciTech Connect

A submerged nuclear power station has been proposed as an alternative power station with a relatively low environmental impact for use by both industrialized and developing countries. The station would be placed 10 m above the seabed at a depth of 30--100 m and a distance of 10--30 km from shore. The submerged nuclear power station would be manufactured and refueled in a central facility, thus gaining the economies of factoryfabrication and the flexibility of short-lead-time deployment. To minimize the size of the submerged hull, horizontal steam generators are proposed for the primary-to-secondary heat transfer, instead of the more traditional vertical steam generators. The horizontal steam generators for SNPS would be similar in design to the horizontal steam generators used in the N-Reactors except the tube orientation is horizontal (the tube`s inlet and outlet connection points on the tubesheet are at the same elevation). Previous RELAP5 input decks for horizontal steam generators have been either very simplistic (Loviisa PWR) or used a vertical tube orientation (N-Reactor). This paper will present the development and testing of a RELAP5 horizontal steam generator model, complete with a simple secondary water level control system, that accounts for the dynamic flow conditions which exist inside horizontal steam generators.

Palmrose, D.E.; Herring, J.S.

1993-05-01T23:59:59.000Z

270

Modeling of a horizontal steam generator for the submerged nuclear power station concept  

Science Conference Proceedings (OSTI)

A submerged nuclear power station has been proposed as an alternative power station with a relatively low environmental impact for use by both industrialized and developing countries. The station would be placed 10 m above the seabed at a depth of 30--100 m and a distance of 10--30 km from shore. The submerged nuclear power station would be manufactured and refueled in a central facility, thus gaining the economies of factoryfabrication and the flexibility of short-lead-time deployment. To minimize the size of the submerged hull, horizontal steam generators are proposed for the primary-to-secondary heat transfer, instead of the more traditional vertical steam generators. The horizontal steam generators for SNPS would be similar in design to the horizontal steam generators used in the N-Reactors except the tube orientation is horizontal (the tube's inlet and outlet connection points on the tubesheet are at the same elevation). Previous RELAP5 input decks for horizontal steam generators have been either very simplistic (Loviisa PWR) or used a vertical tube orientation (N-Reactor). This paper will present the development and testing of a RELAP5 horizontal steam generator model, complete with a simple secondary water level control system, that accounts for the dynamic flow conditions which exist inside horizontal steam generators.

Palmrose, D.E.; Herring, J.S.

1993-01-01T23:59:59.000Z

271

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

Science Conference Proceedings (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

272

Decision-making in Electricity Generation Based on Global Warming Potential and Life-cycle Assessment for Climate Change  

E-Print Network (OSTI)

499, [OECD 2003] OECD. Decommissioning Nuclear Power Plants:maintenance, and ultimate decommissioning of electric poweremissions during the decommissioning of hydroelectric power

Horvath, Arpad

2005-01-01T23:59:59.000Z

273

Use of mediation to resolve the dispute over low-head hydroelectric development at Swan Lake  

DOE Green Energy (OSTI)

In 1978, the Maine Hydroelectric Development Corporation announced that the company planned to renovate five dams on the Goose River near Belfast, Maine to generate electricity. The most important part of the plan involved the use of the first of the dams, at the lower end of Swan Lake, to regulate the flow of water to the downstream dams. For Maine Hydro, management of the Swan Lake dam could make an otherwise marginal proposal lucrative. However, Swan Lake is vitally important to the residents of Swanville. The town was so concerned about the impact of this proposed hydroelectric project that it petitioned the Federal Energy Regulatory Commission (FERC) to deny Maine Hydro's application on the grounds that it would damage the environment, reduce property values and eliminate recreational opportunities for its citizens. This report was written by the mediator of the dispute and represents the views and behavior of the parties as the mediator understood them. It is intended to present the mediator's observations in a way which will inform and assist others who may someday face a difficult situation like the one the Town of Swanville and Maine Hydroelectric Development Corporation faced, and successfully resolved, in the spring and summer of 1979.

O'Connor, D.

1980-08-01T23:59:59.000Z

274

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

275

RESTRUCTURING RELAP5-3D FOR NEXT GENERATION NUCLEAR PLANT ANALYSIS  

Science Conference Proceedings (OSTI)

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

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

2006-06-01T23:59:59.000Z

276

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

SciTech Connect

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

277

DOE/EIS-0456 CUSHMAN HYDROELECTRIC PROJECT MASON COUNTY, WASHINGTON  

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

6 6 CUSHMAN HYDROELECTRIC PROJECT MASON COUNTY, WASHINGTON (FERC PROJECT NO. 460) FINAL ENVIRONMENTAL IMPACT STATEMENT (FERC/EIS-0095F, ADOPTED AS DOE/EIS-0456) US Department of Energy OCTOBER 2010 Lead Agency: U.S. Department of Energy (DOE) Title: Final Environmental Impact Statement (FEIS) for the Cushman Hydroelectric Project, Mason County, Washington (Adopted) Contact: For additional copies or more information on this final environmental impact statement (EIS), please

278

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

DOE Green Energy (OSTI)

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

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

2004-06-01T23:59:59.000Z

279

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

Science Conference Proceedings (OSTI)

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

2009-04-22T23:59:59.000Z

280

Report on technical feasibility of underground pumped hydroelectric storage in a marble quarry site in the Northeast United States  

DOE Green Energy (OSTI)

The technical and economic aspects of constructing a very high head underground hydroelectric pumped storage were examined at a prefeasibility level. Excavation of existing caverns in the West Rutland Vermont marble quarry would be used to construct the underground space. A plant capacity of 1200 MW and 12 h of continuous capacity were chosen as plant operating conditions. The site geology, plant design, and electrical and mechanical equipment required were considered. The study concluded that the cost of the 1200 MW underground pumped storage hydro electric project at this site even with the proposed savings from marketable material amounts to between $581 and $595 per kilowatt of installed capacity on a January 1982 pricing level. System studies performed by the planning group of the New England Power System indicate that the system could economically justify up to about $442 per kilowatt on an energy basis with no credit for capacity. To accommodate the plant with the least expensive pumping energy, a coal and nuclear generation mix of approximately 65% would have to be available before the project becomes feasible. It is not expected that this condition can be met before the year 2000 or beyond. It is therefore concluded that the West Rutland underground pumped storage facility is uneconomic at this time. Several variables however could have marked influence on future planning and should be examined on periodic basis.

Chas. T. Main, Inc.

1982-03-01T23:59:59.000Z

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

Nuclear power to the Pacific  

SciTech Connect

The nuclear power industry is increasingly being pressured to export reactors to the Third World. The experiences of the five ASEAN (Association of Southeast Asian Nations) are recounted. To date, only the Philippine Republic has formally committed itself to a nuclear generator. The Republic lacks oil and has only limited hydroelectric potential. Its geothermal energy program is being accelerated. It appears Indonesia will be the next ASEAN country ''to go nuclear'', hoping to have a nuclear plant on-line in 1985. The island of Singapore has been voicing a desire for a nuclear power plant, but the country does not have space for a plant. The possibility of a floating station has been mentioned, but the World Bank does not finance unproved projects. Singapore could obtain an island from Indonesia or share a plant with Malaysia if a plant were built on the mainland of the Malay peninsula. The Thai Energy Generating Authority (EGAT) is preparing ''to go nuclear'' with the emergence of a stable coalition rule in Bangkok; the financial restrictions are discussed. Thailand is diligently searching for its own oil and gas. The article closes by projecting the problem that could arise with IAEA having only 40 inspectors who are charged with monitoring nuclear power plants all over the world. The authors point out that the industrial countries themselves have proved wholly incapable of monitoring their own systems. (MCW)

Wasserman, H.; Wainer, A.

1976-11-01T23:59:59.000Z

282

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

SciTech Connect

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

283

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

SciTech Connect

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

284

Essays on energy and environmental policy  

E-Print Network (OSTI)

gas, nuclear, hydroelectric, and ‘other’ generators as thehydroelectric), and intermittent renewable generators (e.g.generators, however, there are no fuel costs and unlike hydroelectric

Novan, Kevin Michael

2012-01-01T23:59:59.000Z

285

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

SciTech Connect

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

286

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

SciTech Connect

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

287

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

DOE Green Energy (OSTI)

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

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

2008-03-01T23:59:59.000Z

288

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

289

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

SciTech Connect

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

290

Case study analysis of the legal and institutional obstacles and incentives to the development of the hydroelectric power of the Boardman River at Traverse City, Michigan  

SciTech Connect

An analytic description of one decision-making process concerning whether or not to develop the hydroelectric potential of the Boardman River is presented. The focus of the analysis is on the factor that the developers considered, or should consider in making a responsible commitment to small-scale hydroelectric development. Development of the Boardman River would occur at the five dam sites. Two existing dams, owned by the county, previously generated hydroelectricity, as did a third before being washed out. One dam has never been utilized. It is owned by the city which also owns the washed-out area. The study concludes that hydroelectric power is feasible at each. Grand Traverse County and Traverse City would engage in a joint venture in developing the resource. Chapter I presents a detailed description of the developers, the river resource, and the contemplated development. Chapter II is an analysis of the factors affecting the decision making process. Chapter III summarizes the impact of the more significant barriers and incentives and presents recommendations that, if implemented, will favorably affect decisions to develop small-scale hydroelectric generation capability.

1980-05-01T23:59:59.000Z

291

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

Science Conference Proceedings (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

292

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 the atomistic to the macroscopic level, great morphological changes occur within the fuel over its lifetime. The main initial damaging events produced by fuel recoils from fast neutrons and fission fragment spiking leads to the onset of grain growths and fuel restructuring. Therefore, it is desirable to have a more detailed understanding of the initial events leading to fuel morphology changes at the atomistic level. However, this is difficult to achieve with the fission fragments due to the wide variability of their species (charge, mass, and energy) and the large averaging of their relative yields in the nuclear data files. This work is our first iteration at developing a general methodology to characterize a procedure, based on Monte Carlo principles, for generating individual fission event result channels and analyzing their specific response in the fuel. We utilized the nuclear reaction simulation tool, TALYS, to generate energy-dependent fission fragment yield distributions for different fissile/fissionable isotopes. These distributions can then be used in conjunction with fuel isotopics and a neutron energy spectrum to generate a fission-reaction-rate-averaged distribution of the fission fragment yields. We then used Monte Carlo sampling to generate the result channels from individual fission events, using the Q-value of the prompt fission system to either accept or reject. The simulation tool: Transport of Ions in Matter (TRIM) was used to characterize the general response of the fission fragment species within Uranium Dioxide (UO2), including the range, energy loss, displacements, recoils, etc. These responses were then correlated which allowed for the quick calculation of the response of the individual fission fragment species generated from the Monte Carlo sampling. As an example of this strategy, we calculated the response on a PWR fuel pin where MCNP was used to generate a high-fidelity neutron energy spectrum.

Hackemack, Michael Wayne

2013-05-01T23:59:59.000Z

293

Hydrogen generation rates in Savannah River Site high-level nuclear waste  

DOE Green Energy (OSTI)

High-level nuclear waste (HLW) is stored at the Savannah River Site (SRS) as alkaline, high-nitrate slurries in underground carbon steel tanks. Hydrogen is continuously generated in the waste tanks as a result of the radiolysis of water. Hydrogen generation rates have recently been measured in several waste tanks containing different types of waste. The measured rates ranged from 1.1 to 6.7 cubic feet per million Btu of decay heat. The measured rates are consistent with laboratory data which show that the hydrogen generation rate depends on the nitrate concentration and the decay heat content of the waste. Sampling at different locations indicated that the hydrogen is uniformly distributed radially within the tank.

Hobbs, D.T.; Norris, P.W.; Pucko, S.A.; Bibler, N.E.; Walker, D.D.; d'Entremont, P.D.

1992-01-01T23:59:59.000Z

294

Ontology-based Software for Generating Scenarios for Characterizing Searches for Nuclear Materials  

Science Conference Proceedings (OSTI)

A software environment was created in which ontologies are used to significantly expand the number and variety of scenarios for special nuclear materials (SNM) detection based on a set of simple generalized initial descriptions. A framework was built that combined advanced reasoning from ontologies with geographical and other data sources to generate a much larger list of specific detailed descriptions from a simple initial set of user-input variables. This presentation shows how basing the scenario generation on a process of inferencing from multiple ontologies, including a new SNM Detection Ontology (DO) combined with data extraction from geodatabases, provided the desired significant variability of scenarios for testing search algorithms, including unique combinations of variables not previously expected. The various components of the software environment and the resulting scenarios generated will be discussed.

Ward, Richard C [ORNL; Sorokine, Alexandre [ORNL; Schlicher, Bob G [ORNL; Wright, Michael C [ORNL; Kruse, Kara L [ORNL

2011-01-01T23:59:59.000Z

295

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

DOE Green Energy (OSTI)

Corrosion of steel canisters, stored in a repository for spent fuel and high-level nuclear wastes, leads to the generation and accumulation of hydrogen gas in the backfilled emplacement tunnels, which may significantly affect long-term repository safety. Previous studies used H{sub 2} generation rates based on the volume of the waste or canister material and the stoichiometry of the corrosion reaction. However, iron corrosion and H{sub 2} generation rates vary with time, depending on factors such as amount of iron, water availability, water contact area, and aqueous and solid chemistry. To account for these factors and feedback mechanisms, we developed a chemistry model related to iron corrosion, coupled with two-phase (liquid and gas) flow phenomena that are driven by gas-pressure buildup associated with H{sub 2} generation and water consumption. Results indicate that by dynamically calculating H{sub 2} generation rates based on a simple model of corrosion chemistry, and by coupling this corrosion reaction with two-phase flow processes, the degree and extent of gas pressure buildup could be much smaller compared to a model that neglects the coupling between flow and reactive transport mechanisms. By considering the feedback of corrosion chemistry, the gas pressure increases initially at the canister, but later decreases and eventually returns to a stabilized pressure that is slightly higher than the background pressure. The current study focuses on corrosion under anaerobic conditions for which the coupled hydrogeochemical model was used to examine the role of selected physical parameters on the H{sub 2} gas generation and corresponding pressure buildup in a nuclear waste repository. The developed model can be applied to evaluate the effect of water and mineral chemistry of the buffer and host rock on the corrosion reaction for future site-specific studies.

Xu, T.; Senger, R.; Finsterle, S.

2008-10-15T23:59:59.000Z

296

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

DOE Green Energy (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

297

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

SciTech Connect

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

298

Environmental radiological studies in 1989 near the Rancho Seco Nuclear Power Generating Station  

SciTech Connect

In December 1988, the Sacramento Municipal Utilities District (SMUD) asked the Lawrence Livermore National Laboratory's (LLNL) Environmental Sciences Division (ENV) to collect sediment, water,and fish samples downstream from the Rancho Seco Nuclear Power Generating Station for analysis of radionuclides to compare with results from earlier surveys in 1984 through 1987 (1--8). ENV was, however, asked to reduce the total number of sample collections to a minimum in this study because of financial constraints. The proposal ENV submitted for the 1989 Environmental Radiological Studies downstream of the Rancho Seco Nuclear Power Generating Station reflected this reduction, but we believe, nevertheless, the 1989 efforts do allow us to make some meaningful comparisons with the previous studies. Cesium-137 is the most significant radionuclide still observed downstream from the Rancho Seco Nuclear Power Plant. Only occasionally is {sup 134}Cs or {sup 60}CO observed. In 1989, the concentration of {sup 137}Cs in the water and fish decreased with distance from the plant to the same level that is was in 1987, and was lower than it had been from 1984 through 1986. The concentration ratio (CR) for {sup 137}Cs in fish is between 1000 and 1500, which is below the NRC default value of 2000. Physical mixing in the creek environment has moved the {sup 137}Cs deeper into the sediment column, thereby reducing the concentration in the top 12 cm relative to that in previous years. 8 refs., 18 figs., 9 tabs.

Robison, W.L.; Wong, Kai M.; Jones, H.E.

1990-11-01T23:59:59.000Z

299

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

SciTech Connect

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

300

The Coming Nuclear Renaissance for Next Generation Safeguards Specialists--Maximizing Potential and Minimizing the Risks  

SciTech Connect

This document is intended to provide an overview of the workshop entitled 'The Coming Nuclear Renaissance for the Next Generation Safeguards Experts-Maximizing Benefits While Minimizing Proliferation Risks', conducted at Oak Ridge National Laboratory (ORNL) in partnership with the Y-12 National Security Complex (Y-12) and the Savannah River National Laboratory (SRNL). This document presents workshop objectives; lists the numerous participant universities and individuals, the nuclear nonproliferation lecture topics covered, and the facilities tours taken as part of the workshop; and discusses the university partnership sessions and proposed areas for collaboration between the universities and ORNL for 2009. Appendix A contains the agenda for the workshop; Appendix B lists the workshop attendees and presenters with contact information; Appendix C contains graphics of the evaluation form results and survey areas; and Appendix D summarizes the responses to the workshop evaluation form. The workshop was an opportunity for ORNL, Y-12, and SRNL staff with more than 30 years combined experience in nuclear nonproliferation to provide a comprehensive overview of their expertise for the university professors and their students. The overall goal of the workshop was to emphasize nonproliferation aspects of the nuclear fuel cycle and to identify specific areas where the universities and experts from operations and national laboratories could collaborate.

Eipeldauer, Mary D [ORNL

2009-01-01T23:59:59.000Z

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

Tazimina Hydroelectric Project, Iliamna, Alaska Final Technical and Construction Cost Report  

DOE Green Energy (OSTI)

The Iliamna-Newhalen-Nondalton Electric Cooperative (INNEC) provides electrical power to three communities of the same names. These communities are located near the north shore of Iliamna Lake in south-central Alaska approximately 175 miles southwest of Anchorage. These communities have a combined population of approximately 600 residents. There is no direct road connection from these villages to larger population centers. Electric power has been generated by INNEC since 1983 using diesel generators located in the community of Newhalen. Fuel for these generators was transported up the Kvichak River, an important salmon river, and across Iliamna Lake. In dry years the river is low and fuel is flown into Iliamna and then trucked five miles into Newhalen. The cost, difficult logistics and potential spill hazard of this fuel was a primary reason for development of hydroelectric power in this area. A hydroelectric project was constructed for these communities, starting in the spring of 1996 and ending in the spring of 1998. The project site is at Tazimina Falls about 9 miles upstream of the confluence of the Tazimina River and the Newhalen River. The project has an installed capacity of 824 kilowatts (kW) and is expandable to 1.5 megawatts (MW). The project is run-of-the-river (no storage) and uses the approximately 100 feet of natural head provided by the falls. The project features include a channel control sill, intake structure, penstock, underground powerhouse, tailrace, surface control building, buried transmission line and communication cable, and access road.

HDR Alaska, Inc.

1998-11-01T23:59:59.000Z

302

Hydroelectric feasibility study: Chubb River Sites, Village of Lake Placid, New York  

DOE Green Energy (OSTI)

This study was performed to determine if the re-installation and re-activation of hydroelectric generating facilities at the Mill Pond and Power Pond dams in the Village of Lake Placid, N.Y. would be technically, environmentally, and economically feasible. The study includes a description and evaluation of the conditions of the existing facilities, an estimate of the potential generation at the two sites, a review of regulatory requirements, an economic analysis, and an implementation schedule for installing the facilities. The results show that the installation of new generating equipment within the existing powerhouse may be economically advantageous. Installation of generating facilities at the Mill Pond site would be uneconomical due to low head, aesthetic, environmental costraints, and therefore, is not recommended. The benefits which would be realized by installing equipment at the powerhouse are long term and station operation would initially have to be subsidized for a number of years. (LCL)

Not Available

1979-01-01T23:59:59.000Z

303

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

SciTech Connect

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

304

DOE Office of Indian Energy Foundational Course: Hydroelectric  

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

Hydroelectric Hydroelectric Presented by the National Renewable Energy Laboratory Course Outline What we will cover...  About the DOE Office of Indian Energy Education Initiative  Course Introduction  Resource Map & Project Scales  Technology Overview: - Siting - Costs  Successful Project Examples  Policies Relevant to Project Development  Additional Information & Resources Introduction The U.S. Department of Energy (DOE) Office of Indian Energy Policy and Programs is responsible for assisting Tribes with energy planning and development, infrastructure, energy costs, and electrification of Indian lands and homes. As part of this commitment and on behalf of DOE, the Office of Indian Energy is leading education and capacity building efforts in

305

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

DOE Green Energy (OSTI)

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

Ball, Sydney J [ORNL

2008-03-01T23:59:59.000Z

306

FUTURE HYDROELECTRIC DEVELOPMENT SECTION 12 FISH AND WILDLIFE PROGRAM 12-1 September 13, 1995  

E-Print Network (OSTI)

during the Federal Energy Regulatory Commission (FERC) proceedings on renewal of the hydroelectric of decommissioning dams in the Klamath Hydroelectric Project, Energy Commission staff has completed a preliminaryPRELIMINARY ASSESSMENT OF ENERGY ISSUES ASSOCIATED WITH THE KLAMATH HYDROELECTRIC PROJECT Kevin

307

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

SciTech Connect

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

Mark Holbrook

2007-09-01T23:59:59.000Z

308

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

Science Conference Proceedings (OSTI)

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

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

2012-10-01T23:59:59.000Z

309

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

SciTech Connect

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

310

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

SciTech Connect

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

311

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

312

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

313

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

SciTech Connect

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

314

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

DOE Green Energy (OSTI)

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

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

2008-03-01T23:59:59.000Z

315

Advanced, Environmentally Friendly Hydroelectric Turbines for the Restoration of Fish and Water Quality  

DOE Green Energy (OSTI)

Hydroelectric power contributes about 10 percent of the electrical energy generated in the United States, and nearly 20 percent of the world?s electrical energy. The contribution of hydroelectric generation has declined in recent years, often as a consequence of environmental concerns centering around (1) restriction of upstream and downstream fish passage by the dam, and (2) alteration of water quality and river flows by the impoundment. The Advanced Hydropower Turbine System (AHTS) Program of the U.S. Department of Energy is developing turbine technology which would help to maximize global hydropower resources while minimizing adverse environmental effects. Major technical goals for the Program are (1) the reduction of mortality among turbine-passed fish to 2 percent or less, compared to current levels ranging up to 30 percent or greater; and (2) development of aerating turbines that would ensure that water discharged from reservoirs has a dissolved oxygen concentration of at least 6 mg/L. These advanced, ?environmentally friendly? turbines would be suitable both for new hydropower installations and for retrofitting at existing dams. Several new turbine designs that have been he AHTS program are described.

Brookshier, P.A.; Cada, G.F.; Flynn, J.V.; Rinehart, B.N.; Sale, M.J.; Sommers, G.L.

1999-09-06T23:59:59.000Z

316

Energy 101: Hydroelectric Power | Department of Energy  

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

of dams. America has been using hydropower to generate electricity for more than 100 years now. The words "7% Electricity From Hydropower" appear onscreen, followed by shots of...

317

Environmental impacts of increased hydroelectric development...  

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

27 iii 3 . 2 . 7 Energy Security Benefits . . . . . . . 3 . 3 IMPACTS OF GENERATION USING FOSSIL FUELS . . . 3 . 3 . 1 Water Resources . . . . . . . . . . . . 3 . 3 . 2 Air Quality...

318

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

Science Conference Proceedings (OSTI)

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

Georges Abdul-Nour; Michel Demers; Raynald Vaillancourt

2002-06-01T23:59:59.000Z

319

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

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

320

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

SciTech Connect

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

Note: This page contains sample records for the topic "nuclear generation hydroelectric" from the National Library of EnergyBeta (NLEBeta).
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321

Hydroelectric power potential, Woonsocket Falls Dam, Woonsocket, Rhode Island  

DOE Green Energy (OSTI)

The feasibility of developing a hydroelectric power plant at an existing flood control dam of the city of Woonsocket, RI was examined considering environmental, economic, technical and engineering factors. It was concluded that the City should proceed with plans to develop a hydro plant. (LCL)

Daly, J C; Dowdell, R B; Kelly, W E; Koveos, P E; Krikorian, Jr, J S; Lengyel, G; Prince, M J; Seely, S; Tromp, L; Urish, D W

1979-01-01T23:59:59.000Z

322

Assessment of Aerating Hydroelectric Turbine Developments and Related Research Needs  

Science Conference Proceedings (OSTI)

Aerating hydroelectric turbine developments and research needs were assessed in four separate but complementary areas. This report expands on previous work and describes industry experience with aerating  minimum and environmental flow units; with aerating Kaplan, propeller units, and diagonal flow units; and with environmental optimization of aerating turbines. In addition, the report discusses results from data analyses of the long-term ...

2013-12-17T23:59:59.000Z

323

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

SciTech Connect

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

324

Design Option of Heat Exchanger for the Next Generation Nuclear Plant  

DOE Green Energy (OSTI)

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

Eung Soo Kim; Chang Oh

2008-09-01T23:59:59.000Z

325

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

SciTech Connect

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

326

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

SciTech Connect

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

327

Nuclear & Uranium  

U.S. Energy Information Administration (EIA)

Nuclear & Uranium. Uranium fuel ... nuclear reactors, generation, spent fuel. Total Energy. Comprehensive data summaries, comparisons, analysis, and projections ...

328

Nuclear data uncertainty analysis for the generation IV gas-cooled fast reactor  

Science Conference Proceedings (OSTI)

For the European 2400 MW Gas-cooled Fast Reactor (GoFastR), this paper summarizes a priori uncertainties, i.e. without any integral experiment assessment, of the main neutronic parameters which were obtained on the basis of the deterministic code system ERANOS (Edition 2.2-N). JEFF-3.1 cross-sections were used in conjunction with the newest ENDF/B-VII.0 based covariance library (COMMARA-2.0) resulting from a recent cooperation of the Brookhaven and Los Alamos National Laboratories within the Advanced Fuel Cycle Initiative. The basis for the analysis is the original GoFastR concept with carbide fuel pins and silicon-carbide ceramic cladding, which was developed and proposed in the first quarter of 2009 by the 'French alternative energies and Atomic Energy Commission', CEA. The main conclusions from the current study are that nuclear data uncertainties of neutronic parameters may still be too large for this Generation IV reactor, especially concerning the multiplication factor, despite the fact that the new covariance library is quite complete; These uncertainties, in relative terms, do not show the a priori expected increase with bum-up as a result of the minor actinide and fission product build-up. Indeed, they are found almost independent of the fuel depletion, since the uncertainty associated with {sup 238}U inelastic scattering results largely dominating. This finding clearly supports the activities of Subgroup 33 of the Working Party on International Nuclear Data Evaluation Cooperation (WPEC), i.e. Methods and issues for the combined use of integral experiments and covariance data, attempting to reduce the present unbiased uncertainties on nuclear data through adjustments based on available experimental data. (authors)

Pelloni, S.; Mikityuk, K. [Paul Scherrer Inst., 5232 Villigen PSI (Switzerland)

2012-07-01T23:59:59.000Z

329

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

Science Conference Proceedings (OSTI)

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

J. K. Wright; R. N. Wright

2010-07-01T23:59:59.000Z

330

Structural integrity analysis of the degraded drywell containment at the Oyster Creek Nuclear generating station.  

SciTech Connect

This study examines the effects of the degradation experienced in the steel drywell containment at the Oyster Creek Nuclear Generating Station. Specifically, the structural integrity of the containment shell is examined in terms of the stress limits using the ASME Boiler and Pressure Vessel (B&PV) Code, Section III, Division I, Subsection NE, and examined in terms of buckling (stability) using the ASME B&PV Code Case N-284. Degradation of the steel containment shell (drywell) at Oyster Creek was first observed during an outage in the mid-1980s. Subsequent inspections discovered reductions in the shell thickness due to corrosion throughout the containment. Specifically, significant corrosion occurred in the sandbed region of the lower sphere. Since the presence of the wet sand provided an environment which supported corrosion, a series of analyses were conducted by GE Nuclear Energy in the early 1990s. These analyses examined the effects of the degradation on the structural integrity. The current study adopts many of the same assumptions and data used in the previous GE study. However, the additional computational recourses available today enable the construction of a larger and more sophisticated structural model.

Petti, Jason P.

2007-01-01T23:59:59.000Z

331

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

Science Conference Proceedings (OSTI)

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

Ian McKirdy

2011-07-01T23:59:59.000Z

332

Social issues and energy alternatives: the context of conflict over nuclear waste. Final report  

DOE Green Energy (OSTI)

The perceived risks and benefits of electric power alternatives were used to explore the context of attitudes toward nuclear power. Supporters and opponents of nuclear power responded to thirty-three items which referred to five categories of energy issue: the production potential of electric, risks of those technologies, power generation technologies, energy conservation, comparisons of risks among technologies and comparisons between risks and benefits of each technology. The results are summarized. The nuclear supporters studied here do favor nuclear power. However, they believe that there are limited prospects for contributions from solar, wind and hydroelectric technologies. They also believe that there are serious disadvantages to conservation. Nuclear opponents, on the other hand, disagree that there are such limited prospects for solar and wind, although they are neutral on the prospects for increased hydro capacity. They also do not believe that conservation necessarily poses serious adverse consequences either for themselves or others.

Lindell, M.K.; Earle, T.C.; Perry, R.W.

1980-06-01T23:59:59.000Z

333

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

Science Conference Proceedings (OSTI)

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

L.E. Demick

2010-09-01T23:59:59.000Z

334

MHK Projects/Deception Pass Tidal Energy Hydroelectric Project | Open  

Open Energy Info (EERE)

Deception Pass Tidal Energy Hydroelectric Project Deception Pass Tidal Energy Hydroelectric Project < MHK Projects Jump to: navigation, search << Return to the MHK database homepage Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":5,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"500px","height":"350px","centre":false,"title":"","label":"","icon":"File:Aquamarine-marker.png","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":48.4072,"lon":-122.643,"alt":0,"address":"","icon":"http:\/\/prod-http-80-800498448.us-east-1.elb.amazonaws.com\/w\/images\/7\/74\/Aquamarine-marker.png","group":"","inlineLabel":"","visitedicon":""}]}

335

A Study of United States Hydroelectric Plant Ownership  

Science Conference Proceedings (OSTI)

Ownership of United States hydroelectric plants is reviewed from several perspectives. Plant owners are grouped into six owner classes as defined by the Federal Energy Regulatory Commission. The numbers of plants and the corresponding total capacity associated with each owner class are enumerated. The plant owner population is also evaluated based on the number of owners in each owner class, the number of plants owned by a single owner, and the size of plants based on capacity ranges associated with each owner class. Plant numbers and corresponding total capacity associated with owner classes in each state are evaluated. Ownership by federal agencies in terms of the number of plants owned by each agency and the corresponding total capacity is enumerated. A GIS application that is publicly available on the Internet that displays hydroelectric plants on maps and provides basic information about them is described.

Douglas G Hall

2006-06-01T23:59:59.000Z

336

International Energy Outlook 2000 - Hydroelectricity and Other Renewable  

Gasoline and Diesel Fuel Update (EIA)

The renewable energy share of total world energy consumption is expected to continue at a level of about 8 percent from 1997 through 2020, despite a projected 54-percent increase in consumption of hydroelectricity and other renewable resources. The renewable energy share of total world energy consumption is expected to continue at a level of about 8 percent from 1997 through 2020, despite a projected 54-percent increase in consumption of hydroelectricity and other renewable resources. The development of renewable energy sources is constrained in the International Energy Outlook 2000 (IEO2000) reference case projections by expectations that fossil fuel prices will remain low and, as a result, renewables will have a difficult time competing. Although energy prices rebounded in 1999 from 1998 lows, it remains unlikely that renewable energy can compete economically over the projection period. Failing a strong worldwide commitment to environmental considerations, such as the limitations and reductions of carbon emissions outlined in the Kyoto

337

Shawmut hydroelectric redevelopment project. Final technical and construction cost report  

DOE Green Energy (OSTI)

This report describes the major steps undertaken by the Central Maine Power Company to redevelop an old existing lowhead (19 to 23 ft) hydroelectric station and, at the same time, demonstrate the commercial viability of such a venture. The report addresses the process of site selection, preliminary conceptual design for determining economic viability, licensing and the regulatory process, final design, and project construction with the objective of presenting to the reader a technical and economical guide useful for a similar undertaking.

None

1982-08-01T23:59:59.000Z

338

Results from Case Studies of Conventional Hydroelectric Plants  

Science Conference Proceedings (OSTI)

Detailed plant performance analyses for three conventional hydroelectric plants were conducted using unit and plant performance characteristics and 1-minute plant operational data from 2008, 2009, and 2010. This report describes results from detailed performance analyses that evaluated reductions in overall plant efficiencies under a variety of operation-related and market-related conditions for the plants. Results show that the non-market operation of the conventional plant exhibited more efficient ...

2012-09-14T23:59:59.000Z

339

Legal factors affecting the financing of small scale hydroelectric projects  

DOE Green Energy (OSTI)

An introduction to the major business organizational options open to small-scale hydroelectric (SSH) projects is given. The major federal income tax treatments of these options are compared. Significant general federal income tax factors affecting SSH projects are reintroduced and explained. Some of the special federal income tax problem areas in SSH development are isolated. Tax benefit flow through or transfer mechanisms are discussed. Tax exempt financing opportunities for private SSH projects are reviewed. (MHR)

Wilson, W.H.; Ringo, M.J.; Forgione, N.

1983-09-01T23:59:59.000Z

340

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

SciTech Connect

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

Sackschewsky, M.R.

1997-03-01T23:59:59.000Z

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

High Efficiency Generation of Hydrogen Fuels Using Nuclear Power for the period November 1, 2001- January 31, 2001  

DOE Green Energy (OSTI)

OAK B188 High Efficiency Generation of Hydrogen Fuels Using Nuclear Power for the period November 1, 2001-January 31, 2001. Future nuclear reactors will operate at higher efficiencies and, therefore, at higher temperature than current reactors. High temperatures present the potential for generating hydrogen at high efficiency using a thermochemical process. Thermochemical cycles for the generation of hydrogen from water were extensively studied in the 1970s and early 1980s both in the U.S. and abroad. Since that time, thermochemical water-splitting has not been pursued in the U.S. at any significant level. In Phase 1, we reviewed and analyzed all available data to determine the process best suited to hydrogen production from the advanced nuclear reactors expected to be available in the next 20 to 30 years. The Sulfur-Iodine Cycle was selected for detailed study in Phases 2 and 3. In Phase 2, we investigated means of adapting this cycle to the heat output characteristics of an advanced high temperature nuclear reactor. In Phase 3, we are integrating the cycle and reactor into a unified hydrogen production plant. The highlight of this period was the size of the nuclear reactor used in the matching has been assumed to be 2400 MWt.

Brown, L. C.

2002-09-01T23:59:59.000Z

342

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

Science Conference Proceedings (OSTI)

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

J. K. Wright; R. N. Wright

2008-04-01T23:59:59.000Z

343

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

DOE Green Energy (OSTI)

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

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

2007-03-21T23:59:59.000Z

344

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

E-Print Network (OSTI)

-2% to 60-70%; and third step is the employment of nuclear fusion. However, a report by Zhongguo Dianli Wang thermonuclear experimental reactors (ITER) by International Atomic Energy Agency (IAEA), says, are meant to utilize the energy generated in the fusion of hydrogen, as in the explosion of a hydrogen bomb

345

Feasibility study for a low-head hydroelectric installation at Archusa Creek Dam. Final report to the Pat Harrison Waterway District  

DOE Green Energy (OSTI)

The rising cost, uncertain future supply, and environmental problems associated with energy sources have resulted in serious investigation of energy sources that have not previously been considered economically and technically feasible. One such source involves low-head hydroelectric generation. The Department of Energy has funded several feasibility studies for the installation of hydroelectric generators at existing low-head dams. Such a feasibility study for the Archusa Creek Dam near Quitman, Mississippi, is described. The study indicates that there are no apparent technical dificulties to prevent such a project and that a suitable turbine-generator could be obtained. The study further indicates that the project should be economically feasible for the Pat Harrison Waterway District (owners of the dam and lake) to construct if arrangements could be completed for interconnecting with the local utility and selling the energy to the utility. The utility (Mississippi Power Company) has expressed interest in such an arrangement.

Carlson, K.W.; Herring, J.W. Jr.

1979-02-26T23:59:59.000Z

346

Hoopa Valley Small Scale Hydroelectric Feasibility Project  

DOE Green Energy (OSTI)

The feasibility of hydropower on the Hoopa Valley Indian Reservation has real potential for development and many alternative options for project locations, designs, operations and financing. In order to realize this opportunity further will require at least 2-3 years of intense data collection focusing on stream flow measurements at multiple locations in order to quantify real power potential. This also includes on the ground stream gradient surveys, road access planning and grid connectivity to PG&E for sale of electricity. Imperative to this effort is the need for negotiations between the Hoopa Tribal Council and PG&E to take place in order to finalize the power rate the Tribe will receive through any wholesale agreement that utilizes the alternative energy generated on the Reservation.

Curtis Miller

2009-03-22T23:59:59.000Z

347

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

Science Conference Proceedings (OSTI)

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

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

2008-09-01T23:59:59.000Z

348

International Energy Statistics - U.S. Energy Information ...  

U.S. Energy Information Administration (EIA)

Nuclear: Renewables: Total Fossil Fuels: Hydroelectric Pumped Storage: Total Net Generation: Hydroelectric: ... Pakistan 2.432 31.493 0 0.010 ...

349

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

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

350

Characteristics of colloids generated during the corrosion of nuclear waste glasses in groundwater  

SciTech Connect

Aqueous colloidal suspensions were generated by reacting nuclear waste glasses with groundwater at 90{degrees}C at different ratios of the glass surface area to solution volume (S/V). The colloids have been characterized in terms of size, charge, identity, and stability with respect to salt concentration, pH, and time, by examination using dynamic light scattering, electrophoretic mobility, and transmission electron microscopy. The colloids are predominately produced by precipitation from solution, possibly with contribution from reacted layers that have spallated from the glass. These colloids are silicon-rich minerals. The colloidal suspensions agglomerate when the salinity of the solutions increase. The following implications for modeling the colloidal transport of contaminants have been derived from this study: (1) The sources of the colloids are not only solubility-limited real colloids and the pseudo colloids formed by adsorption of radionuclides onto a groundwater colloid, but also from the spalled surface layers of reacted waste glasses. (2) In a repository, the local environment is likely to be glass-reaction dominated and the salt concentration is likely to be high, leading to rapid colloid agglomeration and settling; thus, colloid transport may be insignificant. (3) If large volumes of groundwater contact the glass reaction site, the precipitated colloids may become resuspended, and colloid transport may become important. (4) Under most conditions, the colloids are negatively charged and will deposit readily on positively charged surfaces. Negatively charged surfaces will, in general, facilitate colloid stability and transport.

Feng, X.; Buck, E.C.; Mertz, C.; Bates, J.K.; Cunnane, J.C.; Chaiko, D.

1993-10-01T23:59:59.000Z

351

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

DOE Green Energy (OSTI)

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

E. A. Harvego

2006-04-01T23:59:59.000Z

352

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

Science Conference Proceedings (OSTI)

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

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

2000-09-01T23:59:59.000Z

353

A policy analysis of the Federal Energy Regulatory Commission's hydroelectric relicensing process.  

E-Print Network (OSTI)

??In this thesis, the FERC’s hydroelectric relicensing process is examined from a historical perspective. It finds that strong federal control to ensure a comprehensive plan… (more)

Wright, Jay

2006-01-01T23:59:59.000Z

354

Attitudes to Hydroelectricity in Chile: The Roles of Trust and Social Identities .  

E-Print Network (OSTI)

??New large hydroelectricity (hydro) power plants have been characterised as an essential component for Chile’s economic development. Rivers are the only locally available natural resource… (more)

Elgueta, Herman

2013-01-01T23:59:59.000Z

355

Maximizing Gross Margin of a Pumped Storage Hydroelectric Facility Under Uncertainty in Price and Water Inflow.  

E-Print Network (OSTI)

??The operation of a pumped storage hydroelectric facility is subject to uncertainty. This is especially true in today’s energy markets. Published models to achieve optimal… (more)

Ikudo, Akina

2009-01-01T23:59:59.000Z

356

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

Science Conference Proceedings (OSTI)

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

J. K. Wright

2008-04-01T23:59:59.000Z

357

A Hybrid Model for Hydroturbine Generating Unit Trend Analysis  

Science Conference Proceedings (OSTI)

According to the nonlinear and nonstationary characteristics of hydroelectricity systems, an hybrid prediction model based on wavelet transform and support vector machines is proposed in this paper for the trend analysis of hydroturbine generating unit ...

Min Zou; Jianzhong Zhou; Zhong Liu; Liangliang Zhan

2007-08-01T23:59:59.000Z

358

High Efficiency Generation of Hydrogen Fuels Using Nuclear Power for the period February 01, 2001- April 30, 2002  

DOE Green Energy (OSTI)

OAK B188 High Efficiency Generation of Hydrogen Fuels Using Nuclear Power for the period February 01, 2001-April 30, 2002. Future nuclear reactors will operate at higher efficiencies and, therefore, at higher temperature than current reactors. High temperatures present the potential for generating hydrogen at high efficiency using a thermochemical process. Thermochemical cycles for the generation of hydrogen from water were extensively studied in the 1970s and early 1980s both in the U.S. and abroad. Since that time, thermochemical water-splitting has not been pursued in the U.S. at any significant level. In Phase 1, we reviewed and analyzed all available data to determine the process best suited to hydrogen production from the advanced nuclear reactors expected to be available in the next 20 to 30 years. The Sulfur-Iodine Cycle was selected for detailed study in Phases 2 and 3. In Phase 2, we investigated means of adapting this cycle to the heat output characteristics of an advanced high temperature nuclear reactor. In Phase 3, we are integrating the cycle and reactor into a unified hydrogen production plant. The highlight of this period was that the scheme of processing the HI/I{sub 2}/H{sub 2}O phase with phosphoric acid is being considered in addition to the reactive distillation scheme.

Brown, L. C.

2002-09-01T23:59:59.000Z

359

High Efficiency Generation of Hydrogen Fuels using Nuclear Power for the period May 1, 2002- July 31, 2002  

DOE Green Energy (OSTI)

OAK B188 High Efficiency Generation of Hydrogen Fuels using Nuclear Power for the period May 1, 2002-July 31, 2002. Future nuclear reactors will operate at higher efficiencies and, therefore, at higher temperature than current reactors. High temperatures present the potential for generating hydrogen at high efficiency using a thermochemical process. Thermochemical cycles for the generation of hydrogen from water were extensively studied in the 1970s and early 1980s both in the U.S. and abroad. Since that time, thermochemical water-splitting has not been pursued in the U.S. at any significant level. In Phase 1, we reviewed and analyzed all available data to determine the process best suited to hydrogen production from the advanced nuclear reactors expected to be available in the next 20 to 30 years. The Sulfur-Iodine Cycle was selected for detailed study in Phases 2 and 3. In Phase 2, we investigated means of adapting this cycle to the heat output characteristics of an advanced high temperature nuclear reactor. In Phase 3, we are integrating the cycle and reactor into a unified hydrogen production plant. The highlight of this period was that the sulfuric acid processing portion of the flowsheet was completed.

Brown, L.C.

2002-09-01T23:59:59.000Z

360

High Efficiency Generation of Hydrogen Fuels Using Nuclear Power for the period August 1, 2001-October 31, 2001  

DOE Green Energy (OSTI)

OAK B188 High Efficiency Generation of Hydrogen Fuels Using Nuclear Power for the period August 1, 2001-October 31, 2001. Future nuclear reactors will operate at higher efficiencies and, therefore, at higher temperature than current reactors. High temperatures present the potential for generating hydrogen at high efficiency using a thermochemical process. Thermochemical cycles for the generation of hydrogen from water were extensively studied in the 1970s and early 1980s both in the U.S. and abroad. Since that time, thermochemical water-splitting has not been pursued in the U.S. at any significant level. In Phase 1, we reviewed and analyzed all available data to determine the process best suited to hydrogen production from the advanced nuclear reactors expected to be available in the next 20 to 30 years. The Sulfur-Iodine Cycle was selected for detailed study in Phases 2 and 3. In Phase 2, we investigated means of adapting this cycle to the heat output characteristics of an advanced high temperature nuclear reactor. In Phase 3, we are integrating the cycle and reactor into a unified hydrogen production plant. The highlight of this period is that a project coordination meeting was held with Sandia on October 9, 2001.

Brown, L. C.

2002-09-01T23:59:59.000Z

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

Generation IV Nuclear Energy Systems Construction Cost Reductions through the use of Virtual Environments: Task 1 Completion Report  

SciTech Connect

OAK B204 The objective of this 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. Specifically, this project will test the suitability of Immersive Projection Display (IPD) 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.

Whisker, V.E.; Baratta, A.J.; Shaw, T.S.; Winters, J.W.; Trikouros, N.; Hess, C.

2002-11-26T23:59:59.000Z

362

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

SciTech Connect

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

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

2007-04-05T23:59:59.000Z

363

Health and safety impacts of nuclear, geothermal, and fossil-fuel electric generation in California. Volume 1. Health and safety impacts of nuclear, geothermal, and fossil-fuel electric generation in California  

DOE Green Energy (OSTI)

This report presents an overview of a project on the health and safety impacts of nuclear, geothermal, and fossil-fuel electric generation in California. In addition to presenting an executive summary of the project, it sets forth the main results of the four tasks of the project: to review the health impacts (and related standards) of these forms of power generation, to review the status of standards related to plant safety (with an emphasis on nuclear power), to consider the role of the California Energy Resources Conservation and Development Commission in selection of standards, and to set forth methodologies whereby that Commission may review the health and safety aspects of proposed sites and facilities.

Nero, A.V. Jr.

1977-01-01T23:59:59.000Z

364

STARLIB: A Next-Generation Reaction-Rate Library for Nuclear Astrophysics  

E-Print Network (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: (i) theoretical TALYS rates for reactions for which no experimental input is available, and (ii) laboratory and theoretical weak rates. STARLIB includes all types of reactions of astrophysical interest to Z = 83, such as (p,g), (p,a), (a,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.

A. L. Sallaska; C. Iliadis; A. E. Champagne; S. Goriely; S. Starrfield; F. X. Timmes

2013-04-29T23:59:59.000Z

365

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

SciTech Connect

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

366

[en] THERMOHIDRAULIC MODEL FOR A TYPICAL STEAM GENERATOR OF PWR NUCLEAR POWER PLANTS.  

E-Print Network (OSTI)

??[pt] Muitas centrais nucleares do tipo PWR utilizam vapor produzido em geradores de vapor do tipo tubos em U invertido, com recirculação interna natural, nos… (more)

CARLOS VALOIS MACIEL BRAGA

2011-01-01T23:59:59.000Z

367

Global generation capacity for nuclear power has grown to over 346 ...  

U.S. Energy Information Administration (EIA)

... nuclear capacity in North America and Europe are relatively small in comparison to those in such countries as China, Korea, and India.

368

Assessment of the feasibility of recommissioning the French Landing Hydroelectric Facility in Van Buren Township, Michigan. Final report  

DOE Green Energy (OSTI)

The results of a study of the feasibility of recommissioning a small, low-head hydroelectric facility in southeastern Michigan are presented. The study concludes that there are several cost-effective designs for recommissioning the site, based on the use of vertical turbines and the sale of power to nearby industrial markets. In terms of the bulk sale of power to the local electric utility, no cost-effective alternatives were found to exist. A major burden on project cost-effectiveness was found to be the relatively large costs for structural repairs to the dam and powerhouse needed to insure safe operation and on adequate service life. From an engineering standpoint it was found that the items of equipment needed to recommission the site are readily available from both US and foreign manufacturers. A variety of hydraulic turbine designs could be successfully adapted to the existing powerhouse, without extensive new construction. It was determined that the production capacity of the facility had an important influence on the cost-effectiveness of the project. A detailed benefit/cost analysis was conducted to identify the optimum facility size in terms of incremental costs and revenues. A detailed environmental assessment using an impact matrix methodology concluded that the development of the facility for hydroelectric generation would have important positive environmental consequences related to improved impoundment and flow management techniques as well as enhanced public safety due to structural repairs to the dam. The institutional and regulatory implications of developing the site for hydroelectric generation were found to be significant but manageable.

Not Available

1979-02-01T23:59:59.000Z

369

GRADUATE RESEARCH OPPORTUNITIES IN APPLIED SCIENCE Effects of Hydroelectric Operations in Canadian Aquatic Ecosystems  

E-Print Network (OSTI)

. C. CAUDILL Fish Ecology Research Laboratory, Department of Fish and Wildlife Resources, College ascension and fallback over a series of large hydroelectric dams within the migration corridor, were hydroelectric dams, a behaviour termed `fallback'. On average, 15­22% of the fishes from studied runs of chinook

Cooke, Steven J.

370

Pricing Hydroelectric Power Plants with/without Operational Restrictions: a Stochastic Control Approach  

E-Print Network (OSTI)

, uranium, hydroelectric, and geothermal. It also comes indirectly from wind, tidal and geo-solar sources/clean: hydroelectric, wind, tidal/wave, geothermal, and hydrogen Conventional fuels: coal, oil, oil-sand natural gas Research on Minerals, Metals and Materials (CERM3) Department of Mining and Mineral Process Engineering

Forsyth, Peter A.

371

RETURN TO THE RIVER : Prepublication Copy 10 September 1996 Chapter 7 Hydroelectric Project Development264  

E-Print Network (OSTI)

, uranium, hydroelectric, and geothermal. It also comes indirectly from wind, tidal and geo-solar sources/clean: hydroelectric, wind, tidal/wave, geothermal, and hydrogen Conventional fuels: coal, oil, oil-sand natural gas Research on Minerals, Metals and Materials (CERM3) Department of Mining and Mineral Process Engineering

372

CLIMATE CHANGE IMPACTS ON HYDROELECTRIC POWER G.P. Harrison(1),  

E-Print Network (OSTI)

Report of the Independent Scientific Advisory Board Regarding a Research Proposal for Inclusion Estimates of the effects of the hydroelectric system on the health of salmon populations are essential the hydroelectric system. Yet while it has been technically feasible to gather highly detailed information to guide

Harrison, Gareth

373

Status Review of Wildlife Mitigation at Columbia Basin Hydroelectric Projects, Oregon Facilities, Final Report.  

DOE Green Energy (OSTI)

The report presents a review and documentation of existing information on wildlife resources at Columbia River Basin hydroelectric facilities within Oregon. Effects of hydroelectric development and operation; existing agreements; and past, current and proposed wildlife mitigation, enhancement, and protection activities were considered. (ACR)

Bedrossian, Karen L.

1984-08-01T23:59:59.000Z

374

SMI 2012: Full Paper: Medial design of blades for hydroelectric turbines and ship propellers  

Science Conference Proceedings (OSTI)

We present a method for constructing blades of hydroelectric turbines and ship propellers based on design parameters that possess a clear hydraulic meaning. The design process corresponds to the classical construction of a blade using the medial surface ... Keywords: B-spline representation, CAD-model, Hydroelectric turbine blade, Medial axis-based design, Propeller blade

M. Rossgatterer; B. Jüttler; M. Kapl; G. Della Vecchia

2012-08-01T23:59:59.000Z

375

High Efficiency Generation of Hydrogen Fuels Using Nuclear Power - for the period August 1, 1999 through October 31, 1999  

DOE Green Energy (OSTI)

OAK B188 High Efficiency Generation of Hydrogen Fuels Using Nuclear Power - for the period August 1, 1999 through October 31, 1999. The highlights for this period are: (1) The methodologies for searching the literature for potentially attractive thermochemical water-splitting cycles, storing cycle and reference data, and screening the cycles have been established; and (2) The water-splitting cycle screening criteria were established on schedule.

L. C. Brown

2000-01-01T23:59:59.000Z

376

Benefits of fish passage and protection measures at hydroelectric projects  

DOE Green Energy (OSTI)

The US Department of Energy`s Hydropower Program is engaged in a multi-year study of the costs and benefits of environmental mitigation measures at nonfederal hydroelectric power plants. An initial report (Volume 1) reviewed and surveyed the status of mitigation methods for fish passage, instream flows, and water quality; this paper focuses on the fish passage/protection aspects of the study. Fish ladders were found to be the most common means of passing fish upstream; elevators/lifts were less common, but their use appears to be increasing. A variety of mitigative measures is employed to prevent fish from being drawn into turbine intakes, including spill flows, narrow-mesh intake screens, angled bar racks, and lightor sound-based guidance measures. Performance monitoring and detailed, quantifiable performance criteria were frequently lacking at non-federal hydroelectric projects. Volume 2 considers the benefits and costs of fish passage and protection measures, as illustrated by case studies for which performance monitoring has been conducted. The report estimates the effectiveness of particular measures, the consequent impacts on the fish populations that are being maintained or restored, and the resulting use and non-use values of the maintained or restored fish populations.

Cada, G.F.; Jones, D.W.

1993-06-01T23:59:59.000Z

377

"1. John Day","Hydroelectric","USCE-North Pacific Division",2160  

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

Oregon" Oregon" "1. John Day","Hydroelectric","USCE-North Pacific Division",2160 "2. The Dalles","Hydroelectric","USCE-North Pacific Division",1823 "3. Bonneville","Hydroelectric","USCE-North Pacific Division",1093 "4. McNary","Hydroelectric","USCE-North Pacific Division",991 "5. Hermiston Power Partnership","Gas","Hermiston Power Partnership",615 "6. Boardman","Coal","Portland General Electric Co",585 "7. Beaver","Gas","Portland General Electric Co",487 "8. Klamath Cogeneration Plant","Gas","Pacific Klamath Energy Inc",470

378

DOE Office of Indian Energy Foundational Course on Hydroelectric Renewable Energy Text Version  

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

Hydroelectric Webinar Hydroelectric Webinar (text version) Below is the text version of the Webinar titled "DOE Office of Indian Energy Foundational Courses Renewable Energy Technologies: Hydroelectric." Amy Hollander: Hello. I'm Amy Hollander with the National Renewable Energy Laboratory. Welcome to today's webinar on hydroelectricity as a renewable energy, sponsored by the U.S. Department of Energy Office of Indian Energy Policy and Programs. This webinar is being recorded from DOE's National Renewable Energy Laboratory's brand new, state of the art, net zero energy research support facility in Golden, Colorado. Our hydroelectricity presentation today is one of nine foundational webinars in the series from the DOE Office of Indian Energy Education Initiative, designed to assist tribes with

379

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

E-Print Network (OSTI)

Dose Commitments from Nuclear Tests carried out beforeDose Commitments from Nuclear Tests carried out before 1968,of the dose from nuclear weapons test fallout. As indicated

Nero, A.V.

2010-01-01T23:59:59.000Z

380

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

Science Conference Proceedings (OSTI)

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

2011-12-08T23:59:59.000Z

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

Feasibility of determination of low-head hydroelectric power development at existing sites: North Hartland Dam Project. Feasibility report  

DOE Green Energy (OSTI)

The feasibility of constructing a low-head hydroelectric power plant at the North Hartland Dam in Vermont was investigated. Evaluation of technical, economic, environmental, safety, and regulatory aspects led to the conclusion that the North Hartland Dam Hydroelectric Project is a technically feasible concept. The proposed project will have a recommended 6000 kW nominally rated capacity at a 52 ft turbine design head and 1680 cfs demand flow. The gross generation expected from the project is 11,980,000 kWh per year. It is estimated that the project will cost $8,997,000 at 1978 price levels, with no allowance for funds during construction. The project will provide peaking power at a levelized cost of about 41 mills per kWh at 1979 price levels, based on 7% cost of money, a 1985 commissioning date, and allowing for funds during construction and cost escalation over a 30 y period. The benefit-cost ratio compared with an equivalent oil-based generation source over a similar period is estimated as 1.06. (LCL)

None

1979-03-01T23:59:59.000Z

382

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

E-Print Network (OSTI)

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

Nero, A.V.

2010-01-01T23:59:59.000Z

383

Nuclear plant design and modification guidelines for PWR steam generator reliability  

Science Conference Proceedings (OSTI)

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

Not Available

1991-09-01T23:59:59.000Z

384

Analysis of environmental issues related to small scale hydroelectric development. II. Design considerations for passing fish upstream around dams. Environmental Sciences Division Publication No. 1567  

DOE Green Energy (OSTI)

The possible requirement of facilities to move migrating fish upstream around dams may be a factor in determining the feasibility of retrofitting small dams for hydroelectric generation. Basic design considerations are reported that should be evaluated on a site-specific basis if upstream fish passage facilities are being considered for a small scale hydroelectric project (defined as an existing dam that can be retrofitted to generate 25 MW or less). Information on general life history and geographic distribution of fish species that may require passage is presented. Biological factors important in the design of upstream passage facilities are discussed: gas bubble disease, fish swimming speed, oxygen consumption by fish, and diel and photo behavior. Three general types of facilities (fishways, fish locks, and fish lifts) appropriate for upstream fish passage at small scale hydroelectric projects are described, and size dimensions are presented. General design criteria for these facilities (including fish swimming ability and behavior) and general location of facilities at a site are discussed. Basic cost considerations for each type of passage facility, including unit cost, operation and maintenance costs, and costs for supplying attraction water, are indicated.

Hildebrand, S.G. (ed.)

1980-08-01T23:59:59.000Z

385

Replacement energy costs for nuclear electricity-generating units in the United States: 1997--2001. Volume 4  

Science Conference Proceedings (OSTI)

This report updates previous estimates of replacement energy costs for potential short-term shutdowns of 109 US nuclear electricity-generating units. This information was developed to assist the US Nuclear Regulatory Commission (NRC) in its regulatory impact analyses, specifically those that examine the impacts of proposed regulations requiring retrofitting of or safety modifications to nuclear reactors. Such actions might necessitate shutdowns of nuclear power plants while these changes are being implemented. The change in energy cost represents one factor that the NRC must consider when deciding to require a particular modification. Cost estimates were derived from probabilistic production cost simulations of pooled utility system operations. Factors affecting replacement energy costs, such as random unit failures, maintenance and refueling requirements, and load variations, are treated in the analysis. This report describes an abbreviated analytical approach as it was adopted to update the cost estimates published in NUREG/CR-4012, Vol. 3. The updates were made to extend the time frame of cost estimates and to account for recent changes in utility system conditions, such as change in fuel prices, construction and retirement schedules, and system demand projects.

VanKuiken, J.C.; Guziel, K.A.; Tompkins, M.M.; Buehring, W.A. [Argonne National Lab., IL (United States)

1997-09-01T23:59:59.000Z

386

International Energy Outlook 1999 - Hydroelectricity and Other Renewable  

Gasoline and Diesel Fuel Update (EIA)

hydroelectricty.gif (7905 bytes) hydroelectricty.gif (7905 bytes) Renewable energy use is projected to increase by 62 percent between 1996 and 2020. Almost half the increase is expected in the developing world, where large-scale hydroelectric projects still are being undertaken. Low prices for oil and natural gas in world energy markets continued to diminish the potential for rapid development of renewable energy sources worldwide. Oil prices hit 20-year lows in 1998, in part because the Asian economic crisis resulted in lower worldwide demand. Even production cut agreements by some major oil producers, such as Saudi Arabia, Mexico, and Venezuela, failed to provide measurable price recovery during 1998. On the positive side, the Kyoto Climate Change Protocol proposals to cut greenhouse gas emissions levels may provide an opportunity for growth in

387

Woodruff Narrows low head hydroelectric power plant feasibility determination  

DOE Green Energy (OSTI)

Woodruff Narrows Reservoir, owned by the State of Utah, was built in 1961 as an irrigation reservoir. The reservoir outlet works and spillway are in need of repair, and plans have been made to enlarge the reservoir from its present capacity of 28,000 acre-feet to 53,200 acre-feet when these repairs are made. The purpose of this study was to determine if it is feasible to add hydropower facilities when the reservoir is repaired and enlarged. A computer simulation model based on mean monthly values, utilizing 26 years of recorded streamflow into the reservoir, was used to determine the mean annual energy potential for the following configurations: (1) present dam, (2) the proposed enlarged dam, (3) a new dam at the lower site with a maximum head of 65 feet, and (4) a new dam at the lower site which would store water to the same elevation as the proposed enlarged dam. Results of the simulation study show that maximum power capacities are respectively 2.1, 3.0, 3.9, and 4.5 megawatts. The marketing potential for this electric power, cost estimates and financial analysis, and environmental, social, and regulatory aspects of the proposed hydropower facilities were evaluated. The results showed the addition of hydroelectric power development at the Woodruff Narrows site would have minimal social and environmental effects on the area, would result in little or no changes in the present patterns of water and land use, income, population, and employment and would not result in any significant changes of the social structure or characteristics of the area. However, hydroelectric power development at the Woodruff Narrows site is not economically feasible at the present time. (LCL)

Not Available

1979-03-01T23:59:59.000Z

388

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

389

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

390

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

391

Initial Screening of Thermochemical Water-Splitting Cycles for High Efficiency Generation of Hydrogen Fuels Using Nuclear Power  

DOE Green Energy (OSTI)

OAK B188 Initial Screening of Thermochemical Water-Splitting Cycles for High Efficiency Generation of Hydrogen Fuels Using Nuclear Power There is currently no large scale, cost-effective, environmentally attractive hydrogen production process, nor is such a process available for commercialization. Hydrogen is a promising energy carrier, which potentially could replace the fossil fuels used in the transportation sector of our economy. Fossil fuels are polluting and carbon dioxide emissions from their 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. Almost 800 literature references were located which pertain to thermochemical production of hydrogen from water and over 100 thermochemical watersplitting cycles were examined. Using defined criteria and quantifiable metrics, 25 cycles have been selected for more detailed study.

Brown, L.C.; Funk, J.F.; Showalter, S.K.

1999-12-15T23:59:59.000Z

392

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

Science Conference Proceedings (OSTI)

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

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

1981-09-15T23:59:59.000Z

393

Nuclear Instruments and Methods in Physics Research A 566 (2006) 598608 The number distribution of neutrons and gamma photons generated in a  

E-Print Network (OSTI)

that are based on nuclear physics constants (fission neutron and gamma photon multi- plicities), weighted by nonNuclear Instruments and Methods in Physics Research A 566 (2006) 598­608 The number distribution of neutrons and gamma photons generated in a multiplying sample Andreas Enqvista,�, Imre Pa´ zsita , Sara

Pázsit, Imre

394

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

SciTech Connect

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

395

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

E-Print Network (OSTI)

. But as US demand increases for gas in heating,cookingandtransportation,itspricewillrise.Natural--arelativelylow-carbon-emissionfossilfuel--hasbeen thepreferredfuelfornewelectricalcapacityoverthepasttwodecades. Resourcediscoveriesandadvancesinextractiontechnologieshavemade natural gas seem inexpensive-fuellednuclear)2 .Smartpolicywould be to reduce the use of natural gas in electricity generation. Although

396

Nuclear Plant Design and Modification Guidelines for PWR Steam Generator Reliability  

Science Conference Proceedings (OSTI)

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

1991-09-25T23:59:59.000Z

397

Materials Reliability Program: San Onofre Nuclear Generating Station Reactor Vessel Internals Management Engineering Program (MRP-303)  

Science Conference Proceedings (OSTI)

All operating pressurized water reactors must have a reactor vessel internals aging management document in place by December 2011 according to the mandatory requirement under Nuclear Energy Institute (NEI) 03-08. This program should be developed to meet the guidance provided by Materials Reliability Program (MRP) -227, Rev. 0, Pressurized Water Reactor Internals Inspection and Evaluation Guidelines. For non-license renewal plants, the requirements are valid within the current license period, and the Elec...

2011-02-28T23:59:59.000Z

398

Desired Characteristics for Next Generation Integrated Nuclear Safety Analysis Methods and Software  

Science Conference Proceedings (OSTI)

As a result of economic, environmental, and policy imperatives, it is envisioned that operation of the current fleet of commercial nuclear power plants NPPs will extend significantly beyond their original licensing periods. This objective can be achieved only if these plants continue to operate in a safe and cost-effective manner. The capability to perform detailed technical safety analyses of operational events either actual or postulated and desired operational enhancements such as power uprates will c...

2010-12-23T23:59:59.000Z

399

Assessment of DC Backup Power Technology Options for Nuclear Power Generation Stations  

Science Conference Proceedings (OSTI)

The March 2011 Fukushima nuclear power plant accident in Japan created a renewed industry interest in examining potential improvements for backup power options to support plant accident scenarios in both near-term and long-term implementation time periods. This report assesses technology options that can be considered in improving DC backup power. Options with near-term applicability were considered and reviewed. Certain energy storage systems and hydrogen power fuel cells were identified that could ...

2013-10-15T23:59:59.000Z

400

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

SciTech Connect

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

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

''Rancho Hydro'': a low-head, high volume residential hydroelectric power system, Anahola, Kauai, Hawaii  

DOE Green Energy (OSTI)

The site is a 1.75 acre residential site with two households. The Anahola stream intersects the property line. Design of the proposed hydroelectric system is described, along with the permit process. Construction is in progress. (DLC)

Harder, J.D.

1982-07-01T23:59:59.000Z

402

Small-Hydroelectricity and Landscape Change in the Bitterroot Mountains: Public Perceptions and Attitudes.  

E-Print Network (OSTI)

??Newman, Chad, M.A. December 2007 Geography Small-Hydroelectricity and Landscape Change in the Bitterroot Mountains: Public Perceptions and Attitudes Chairperson: Dr. David D. Shively The development… (more)

Newman, Chad E

2008-01-01T23:59:59.000Z

403

Hydroelectricity and landscape protection in the Highlands of Scotland, 1919 - 1980.  

E-Print Network (OSTI)

??This thesis employs twentieth-century hydroelectric development ventures in the Highlands of Scotland as a means of exploring conflicting demands of socio-economic development and landscape protection… (more)

Payne, Jill

2008-01-01T23:59:59.000Z

404

Automation of a hydroelectric power station using variable-structure control systems  

Science Conference Proceedings (OSTI)

This article presents the basis and conception of, and some experimental results obtained from, the automation of a hydroelectric power station. The principle of this automation, the purpose of which was to maximize the active power supplied by the station, ...

J. Erschler; F. Roubellat; J. P. Vernhes

1974-01-01T23:59:59.000Z

405

PUBLISHED ONLINE: 31 JULY 2011 | DOI: 10.1038/NGEO1211 Carbon emission from hydroelectric reservoirs  

E-Print Network (OSTI)

of hydroelectric and fuel cell facilities, respectively.) The Energy Commission recognizes the importance Edition OCTOBER 2011 CEC3002011008SD CALIFORNIA ENERGY COMMISSION Edmund G. Brown, Jr., Governor #12;CALIFORNIA ENERGY COMMISSION CARLA PETERMAN Lead Commissioner Kate Zocchetti Project Manager Tony

406

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

E-Print Network (OSTI)

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

Nero, A.V.

2010-01-01T23:59:59.000Z

407

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)

applies, not only to the nuclear reactor, but also to otherdetailed de- sign of nuclear reactor power s tations is vgreat importance in nuclear reactor accidents. 3.2 Increase

Nero, A.V.

2010-01-01T23:59:59.000Z

408

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

E-Print Network (OSTI)

refabrication. through which nuclear fuel passes. Fusion.with the experience at the Nuclear Fuel Services Plant (seecommitment from the nuclear fuel cycle; see Section 3.2.3. )

Nero, A.V.

2010-01-01T23:59:59.000Z

409

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

SciTech Connect

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

S. Blaine Grover

2009-05-01T23:59:59.000Z

410

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

SciTech Connect

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

411

Challenges to Integration of Safety and Reliability with Proliferation Resistance and Physical Protection for Generation IV Nuclear Energy Systems  

Science Conference Proceedings (OSTI)

The optimization of a nuclear energy system's performance requires an integrated consideration of multiple design goals - sustainability, safety and reliability (S&R), proliferation resistance and physical protection (PR&PP), and economics - as well as careful evaluation of trade-offs for different system design and operating parameters. Design approaches motivated by each of the goal areas (in isolation from the other goal areas) may be mutually compatible or in conflict. However, no systematic methodology approach has yet been developed to identify and maximize synergies and optimally balance conflicts across the possible design configurations and operating modes of a nuclear energy system. Because most Generation IV systems are at an early stage of development, design, and assessment, designers and analysts are only beginning to identify synergies and conflicts between PR&PP, S&R, and economics goals. The close coupling between PR&PP and S&R goals has motivated early attention within the Generation IV International Forum to their integrated consideration to facilitate the optimization of their effects and the minimization of potential conflicts. This paper discusses the status of this work.

H. Khalil; P. F. Peterson; R. Bari; G. -L. Fiorini; T. Leahy; R. Versluis

2012-07-01T23:59:59.000Z

412

New technology for purging the steam generators of nuclear power plants  

Science Conference Proceedings (OSTI)

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

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

2011-07-15T23:59:59.000Z

413

Evaluation Metrics for Intermediate Heat Exchangers for Next Generation Nuclear Reactors  

SciTech Connect

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

414

Environmental mitigation at hydroelectric projects. Volume 2, Benefits and costs of fish passage and protection  

DOE Green Energy (OSTI)

This study examines envirorunental mitigation practices that provide upstream and downstream fish passage and protection at hydroelectric projects. The study includes a survey of fish passage and protection mitigation practices at 1,825 hydroelectric plants regulated by the Federal Energy Regulatory Commission (FERC) to determine frequencies of occurrence, temporal trends, and regional practices based on FERC regions. The study also describes, in general terms, the fish passage/protection mitigation costs at 50 non-Federal hydroelectric projects. Sixteen case studies are used to examine in detail the benefits and costs of fish passage and protection. The 16 case studies include 15 FERC licensed or exempted hydroelectric projects and one Federally-owned and-operated hydroelectric project. The 16 hydroelectric projects are located in 12 states and range in capacity from 400 kilowatts to 840 megawatts. The fish passage and protection mitigation methods at the case studies include fish ladders and lifts, an Eicher screen, spill flows, airburst-cleaned inclined and cylindrical wedgewire screens, vertical barrier screens, and submerged traveling screens. The costs, benefits, monitoring methods, and operating characteristics of these and other mitigation methods used at the 16 case studies are examined.

Francfort, J.E.; Rinehart, B.N.; Sommers, G.L. [EG and G Idaho, Inc., Idaho Falls, ID (United States); Cada, G.F.; Jones, D.W. [Oak Ridge National Lab., TN (United States); Dauble, D.D. [Pacific Northwest Lab., Richland, WA (United States); Hunt, R.T. [Hunt (Richard) Associates, Inc., Concord, NH (United States); Costello, R.J. [Northwest Water Resources Advisory Services (United States)

1994-01-01T23:59:59.000Z

415

THE ECONOMICS OF ELECTRICITY GENERATION IN QUEENSLAND AND THE POTENTIAL EMPLOYMENT OF NUCLEAR REACTORS  

SciTech Connect

An endeavor was made to fix a tentative date at which atomic energy is likely to compete with conventional forms of power generation and to indicate the sizes of plant required and cost figures that will be prevailing at that time. (M.H.R.)

Waldie, R.D.

1957-01-01T23:59:59.000Z

416

Inexpensive cross-flow hydropower turbine at Arbuckle Mountain Hydroelectric Project  

SciTech Connect

This report documents the first three and half years of operation and maintenance on the Arbuckle Mountain Hydroelectric Project. Located on a flashy mountain stream in northern California, the project was designed, built and tested through a Cooperative Agreement between the US DOE and OTT Engineering, Inc. (OTT). The purpose of the Agreement is to build and intensively test an inexpensive American-made cross-flow turbine and to provide information to the DOE on the cost, efficiency, operation, and maintenance of the unit. It requires that OTT document for DOE a summary of the complete operating statistics, operation and maintenance cost, and revenues from power sales for a two-year operating period. Several unique events occurred between the initial start-up (December 1986) and the beginning of the 1989 generation season (October 1988) that delayed the first year's full operation and provided unique information for a demonstration project of this type. Accordingly, this report will discuss certain major problems experienced with the design, operation and maintenance, and energy production, as well as the operation and maintenance costs and value of the power produced for the first three and half years of operation. 9 figs., 2 tabs.

1991-07-01T23:59:59.000Z

417

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

Science Conference Proceedings (OSTI)

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

1991-07-01T23:59:59.000Z

418

"1. Brownlee","Hydroelectric","Idaho Power Co",744 "2. Dworshak","Hydroelectric","USCE-North Pacific Division",400  

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

Idaho" Idaho" "1. Brownlee","Hydroelectric","Idaho Power Co",744 "2. Dworshak","Hydroelectric","USCE-North Pacific Division",400 "3. Cabinet Gorge","Hydroelectric","Avista Corp",255 "4. Rathdrum Power LLC","Gas","Rathdrum Operating Services Co., Inc.",248 "5. Evander Andrews Power Complex","Gas","Idaho Power Co",247 "6. Palisades","Hydroelectric","U S Bureau of Reclamation",176 "7. Bennett Mountain","Gas","Idaho Power Co",164 "8. Rathdrum","Gas","Avista Corp",132 "9. Goshen Phase II","Other Renewables","AE Power Services LLC",125

419

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

SciTech Connect

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

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

2009-01-15T23:59:59.000Z

420

Seismic structural fragility investigation for the San Onofre Nuclear Generating Station, Unit 1 (Project I); SONGS-1 AFWS Project  

Science Conference Proceedings (OSTI)

An evaluation of the seismic capacities of several of the San Onofre Nuclear Generating Station, Unit 1 (SONGS-1) structures was conducted to determine input to the overall probabilistic methodology developed by Lawrence Livermore National Laboratory. Seismic structural fragilities to be used as input consist of median seismic capacities and their variabilities due to randomness and uncertainty. Potential failure modes were identified for each of the SONGS-1 structures included in this study by establishing the seismic load-paths and comparing expected load distributions to available capacities for the elements of each load-path. Particular attention was given to possible weak links and details. The more likely failure modes were screened for more detailed investigation.

Wesley, D.A.; Hashimoto, P.S.

1982-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear generation hydroelectric" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
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We encourage you to perform a real-time search of NLEBeta
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421

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

SciTech Connect

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

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

1980-07-01T23:59:59.000Z

422

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

E-Print Network (OSTI)

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

Barner, Robert Buckner

2006-12-01T23:59:59.000Z

423

2002 EIA Models Directory - Energy Information Administration  

U.S. Energy Information Administration (EIA)

Levelized Nuclear Fuel Cycle Cost Model (LNFCC-PC) Propane Market Model (PPMM) Short-Term Hydroelectric Generation Model (STHGM)

424

Climate Change, Nuclear Power and Nuclear  

E-Print Network (OSTI)

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

425

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

SciTech Connect

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

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

2002-07-01T23:59:59.000Z

426

Potential hydroelectric power. Vertical turbine: spillway combine Broadwater Dam. Final report  

DOE Green Energy (OSTI)

A feasibility study was made of the hydroelectric power potential at Broadwater Dam in western Montana. Two alternative configurations for the potential project were evaluated and the economics of four possible sources of project funding were assessed. The configurations analyzed were an apron-mounted configuration, in which the turbine-generator units are located on the downstream apron of the existing dam, and a conventional configuration, in which the units are located in a new powerhouse adjacent to the existing dam. The funding sources considered were the Department of Energy loan program, the United States Bureau of Reclamation PL-984 loan program and conventional revenue bonds, both taxable and tax-exempt. The optimal project alternative was determined to be the apron-mounted configuration. The final choice of funding would be dependent on the power purchaser. It was shown that, regardless of the configuraton or funding source selected, the project would be feasible. The cost of the apron-mounted configuration, which would consist of four turbine-generator units for a total installed capacity of 9.76 MW, was estimated as $13,250,000 with financing provided by either a PL-984 loan or tax-exempt bonds. The cost per installed kilowatt was therefore $1,350, and the cost per kilowatt-hour was 19.6 mills. The average annual energy was estimated to be 56.44 million kWh, the equivalent of approximately 87,000 barrels of oil per y. It is therefore recommended that the Montana Department of Natural Resources and Conservation proceed with the project and that discussions be initiated with potential power purchasers as soon as possible.

Willer, D.C.

1979-04-23T23:59:59.000Z

427

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

428

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

429

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

DOE Green Energy (OSTI)

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

Michael W. Patterson

2008-05-01T23:59:59.000Z

430

Noble metal catalyzed hydrogen generation from formic acid in nitrite-containing simulated nuclear waste media  

SciTech Connect

Simulants for the Hanford Waste Vitrification Plant (HWVP) feed containing the major non-radioactive components Al, Cd, Fe, Mn, Nd, Ni, Si, Zr, Na, CO{sub 3}{sup 2{minus}}, NO{sub 3}-, and NO{sub 2}- were used as media to evaluate the stability of formic acid towards hydrogen evolution by the reaction HCO{sub 2}H {yields} H{sub 2} + CO{sub 2} catalyzed by the noble metals Ru, Rh, and/or Pd found in significant quantities in uranium fission products. Small scale experiments using 40-50 mL of feed simulant in closed glass reactors (250-550 mL total volume) at 80-100{degree}C were used to study the effect of nitrite and nitrate ion on the catalytic activities of the noble metals for formic acid decomposition. Reactions were monitored using gas chromatography to analyze the CO{sub 2}, H{sub 2}, NO, and N{sub 2}O in the gas phase as a function of time. Rhodium, which was introduced as soluble RhCl{sub 3}{center_dot}3H{sub 2}O, was found to be the most active catalyst for hydrogen generation from formic acid above {approx}80{degree}C in the presence of nitrite ion in accord with earlier observations. The inherent homogeneous nature of the nitrite-promoted Rh-catalyzed formic acid decomposition is suggested by the approximate pseudo first-order dependence of the hydrogen production rate on Rh concentration. Titration of the typical feed simulants containing carbonate and nitrite with formic acid in the presence of rhodium at the reaction temperature ({approx}90{degree}C) indicates that the nitrite-promoted Rh-catalyzed decomposition of formic acid occurs only after formic acid has reacted with all of the carbonate and nitrite present to form CO{sub 2} and NO/N{sub 2}O, respectively. The catalytic activities of Ru and Pd towards hydrogen generation from formic acid are quite different than those of Rh in that they are inhibited rather than promoted by the presence of nitrite ion.

King, R.B.; Bhattacharyya, N.K. [Univ. of Georgia, Athens, GA (United States). Department of Chemistry; Wiemers, K.D.

1994-08-01T23:59:59.000Z

431

Recovery Act: Hydroelectric Facility Improvement Project - Replacement of Current Mechanical Seal System with Rope Packing System  

SciTech Connect

On January 27, 2010 the City of North Little Rock, Arkansas received notification of the awarding of a Department of Energy (DOE) grant totaling $450,000 in funding from the American Recovery and Reinvestment Act (ARRA) under the Project Title: Recovery Act: Hydroelectric Facility Improvement Project – Automated Intake Clearing Equipment and Materials Management. The purpose of the grant was for improvements to be made at the City’s hydroelectric generating facility located on the Arkansas River. Improvements were to be made through the installation of an intake maintenance device (IMD) and the purchase of a large capacity wood grinder. The wood grinder was purchased in order to receive the tree limbs, tree trunks, and other organic debris that collects at the intake of the plant during high flow. The wood grinder eliminates the periodic burning of the waste material that is cleared from the intake and reduces any additional air pollution to the area. The resulting organic mulch has been made available to the public at no charge. Design discussion and planning began immediately and the wood grinder was purchased in July of 2010 and immediately put to work mulching debris that was gathered regularly from the intake of the facility. The mulch is currently available to the public for free. A large majority of the design process was spent in discussion with the Corps of Engineers to obtain approval for drawings, documents, and permits that were required in order to make changes to the structure of the powerhouse. In April of 2011, the City’s Project Engineer, who had overseen the application, resigned and left the City’s employ. A new Systems Mechanical Engineer was hired and tasked with overseeing the project. The transfer of responsibility led to a re-examination of the original assumptions and research upon which the grant proposal was based. At that point, the project went under review and a trip was booked for July 2011 to visit facilities that currently had an IMD installed. This further study of facilities revealed that the implementation of the project as originally described, while proving the benefits described in the original grant application, would likely intensify sand intake. Increased sand intake would lead to an increase in required shutdowns for maintenance and more rapid depreciation of key equipment which would result in a loss of generation capacity. A better solution to the problem, one that continued to meet the criteria for the original grant and ARRA standards, was developed. A supporting day trip was planned to visit other facilities located on the Arkansas River to determine how they were coping with the same strong amounts of sand, silt, and debris. Upon returning from the trip to other Arkansas River facilities it was extremely clear what direction to go in order to most efficiently address the issue of generator capacity and efficiency. Of the plants visited on the Arkansas River, every one of them was running what is called a rope packing shaft sealing system as opposed to mechanical shaft seals, which the facility was running. Rope packing is a time proven sealing method that has been around for centuries. It has proved to perform very well in dirty water situations just like that of the Arkansas River. In April of 2012 a scope change proposal was submitted to the DOE for approval. In August of 2012 the City received word that the change of scope had been approved. Plans were immediately set in motion to begin the conversion from mechanical seals to a packing box at the facility. Contractors arrived on October 1st, 2012 and the project team began unwatering the unit for disassembly. The seal conversion was completed on February 29th, 2013 with start-up of the unit. Further testing and adjusting was done throughout the first two weeks of March.

Stephens, Jessica D.

2013-05-29T23:59:59.000Z

432

Long-Term Planning for Nuclear Power's Development in Japan for a Zero-Carbon Electricity Generation System by 2100  

Science Conference Proceedings (OSTI)

Education, Economics, and Sustainability / Proceedings of the Fifteenth International Conference on Emerging Nuclear Energy Systems

Qi Zhang; Keiichi N. Ishihara; Benjamin McLellan; Tetsuo Tezuka

433

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

SciTech Connect

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

Belle R. Upadhyaya; J. Wesley Hines

2004-09-27T23:59:59.000Z

434

An Investigation of the Application of the Gas Generator-Free Turbine Cycle to a Nuclear Powered Aircraft  

SciTech Connect

This study has investigated the feasibility of installing a gas generator-free turbine type power plant in the R3Y aircraft, using a circulating fuel reactor as a power source. Two variations of the cycle were considered. The split flow cycle bleeds high temperature, high pressure air from the gas generator directly to the free turbine in the wing. The through flow cycle partially expands the high temperature, high pressure air through the compressor turbine of the gas generator then directs the compressor-turbine exhaust air to the free turbine in the wing. Design parameters of pressure ratio, radiator depth, radiation flow density, and hot gas duct size were optimized to give minimum weight per shaft horsepower of the complete power plant. The weight of a split flow power plant capable of supplying 22,000 shaft horsepower was found to be 116,600 pounds. The weight of a similar through flow power plant was found to be 119,900 pounds. The reactor power required in both cases was 70 megawatts. The nominal gross weight of the R3Y airplane is 175,000 pounds. With pay loads of approximately 20,000 pounds, either nuclear conversion will have a gross weight of 200,000 pounds. It was found that either cycle could be installed in the R3Y aircraft; however, the installation of either would require major structural redesign. The split flow cycle with its smaller hot air ducts required the least amount of redesign. A comparison of existing aircraft engines with a preliminary design of the split flow turbo-components indicated that the compressor and possibly the free turbine could be adapted from current engine components.

Alvis, J. H.; Chessman, S. R.

1957-08-01T23:59:59.000Z

435

Water-Power Development, Conservation of Hydroelectric Power Dams and Works  

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

Water-Power Development, Conservation of Hydroelectric Power Dams Water-Power Development, Conservation of Hydroelectric Power Dams and Works (Virginia) Water-Power Development, Conservation of Hydroelectric Power Dams and Works (Virginia) < Back Eligibility Commercial Construction Developer Industrial Investor-Owned Utility Municipal/Public Utility Rural Electric Cooperative Systems Integrator Utility Savings Category Water Buying & Making Electricity Home Weatherization Program Info State Virginia Program Type Siting and Permitting Provider Virginia State Corporation Commission It is the policy of the Commonwealth of Virginia to encourage the utilization of its water resources to the greatest practicable extent, to control the waters of the Commonwealth, and also to construct or reconstruct dams in any rivers or streams within the Commonwealth for the

436

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

E-Print Network (OSTI)

MISCELLAN £OUS LlOUID STEAM GENERATOR ORAIH OE .. ,N[PALIZEAon the steam system and turbine generator units, as d~fined

Nero, A.V.

2010-01-01T23:59:59.000Z

437

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

SciTech Connect

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

S. Blaine Grover

2009-09-01T23:59:59.000Z

438

Geothermal energy in the western United States and Hawaii: Resources and projected electricity generation supplies. [Contains glossary and address list of geothermal project developers and owners  

DOE Green Energy (OSTI)

Geothermal energy comes from the internal heat of the Earth, and has been continuously exploited for the production of electricity in the United States since 1960. Currently, geothermal power is one of the ready-to-use baseload electricity generating technologies that is competing in the western United States with fossil fuel, nuclear and hydroelectric generation technologies to provide utilities and their customers with a reliable and economic source of electric power. Furthermore, the development of domestic geothermal resources, as an alternative to fossil fuel combustion technologies, has a number of associated environmental benefits. This report serves two functions. First, it provides a description of geothermal technology and a progress report on the commercial status of geothermal electric power generation. Second, it addresses the question of how much electricity might be competitively produced from the geothermal resource base. 19 figs., 15 tabs.

Not Available

1991-09-01T23:59:59.000Z

439

"1. Grand Coulee","Hydroelectric","U S Bureau of Reclamation...  

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

of Reclamation",7079 "2. Palo Verde","Nuclear","Arizona Public Service Co",3937 "3. Martin","Gas","Florida Power & Light Co",3695 "4. W A Parish","Coal","NRG Texas Power...

440

EIA - Electricity Generating Capacity  

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

imports and exports. Renewable & Alternative Fuels Includes hydropower, solar, wind, geothermal, biomass and ethanol. Nuclear & Uranium Uranium fuel, nuclear reactors, generation,...

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

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

Science Conference Proceedings (OSTI)

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

Not Available

2010-12-01T23:59:59.000Z

442

Status Review of Wildlife Mitigation, Columbia Basin Hydroelectric Projects, Columbia River Mainstem Facilities, 1984 Final Report.  

DOE Green Energy (OSTI)

This report reviews the status of past, present, and proposed future wildlife planning and mitigation programs at existing hydroelectric projects in the Columbia River Basin. The project evaluations will form the basis for determining any needed remedial measures or additional project analysis. Each hydropower facility report is abstracted separately for inclusion in the Energy Data Base.

Howerton, Jack; Hwang, Diana

1984-11-01T23:59:59.000Z