National Library of Energy BETA

Sample records for nuclear generation hydroelectric

  1. Hydro-electric generator

    SciTech Connect (OSTI)

    Vauthier, P.

    1980-06-03

    The efficiency of a hydro-electric generator is improved by providing open-ended hollow tubes having influx ends proximate the axis and efflux ends proximate the periphery of a fan-bladed turbine. The jets of water developed by rotation of the fanbladed turbine are directed against turbine vanes at the periphery of the fan blades. The device is particularly suitable for mounting in a water current such as in an ocean current or river.

  2. Microsoft PowerPoint - AECC Hydroelectric Generation 2010.pptx

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

    AECC H d l i AECC Hydroelectric Generation Facilities Generation Facilities Arkansas ... E i ti H d l t i Existing Hydroelectric Generating Resources g * Ellis Hydroelectric ...

  3. Water management for hydroelectric power generation at Matera and Kidatu in Tanzania

    SciTech Connect (OSTI)

    Matondo, J.I.; Rutashobya, D.G.

    1995-12-31

    The major sources of power in Tanzania are hydropower and thermo power. Most of the hydroelectric power is generated in the Great Ruaha river system (280 MW) and in the Pangani river system (46 MW). However, the generated power (hydro and thermo) does not meet the power demand and as a result, an accute power shortage occurred in August 1992. This paper explores the hydropower generation mechanism at Mtera and Kidatu hydroelectric power plants. It also looks into what measures could have been taken in order to avoid the massive power shedding which officially lasted for about six months, although unofficially, power shedding was continued well beyond that period. Strategies for future water management in the Great Ruaha river system for efficient generation of power are also presented.

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

    SciTech Connect (OSTI)

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

    1981-05-01

    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.

  5. List of Hydroelectric Incentives | Open Energy Information

    Open Energy Info (EERE)

    Coal with CCS Concentrating Solar Power Energy Storage Fuel Cells Geothermal Electric Natural Gas Nuclear Tidal Energy Wave Energy Wind energy BiomassBiogas Hydroelectric...

  6. Underground pumped hydroelectric storage

    SciTech Connect (OSTI)

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

    1984-07-01

    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.

  7. NUCLEAR FLASH TYPE STEAM GENERATOR

    DOE Patents [OSTI]

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

    1962-09-01

    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)

  8. 2013 Electrical Production: EPAct 2005 Section 242 Hydroelectric Incentive

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

    Program | Department of Energy 3 Electrical Production: EPAct 2005 Section 242 Hydroelectric Incentive Program 2013 Electrical Production: EPAct 2005 Section 242 Hydroelectric Incentive Program In 2014, Congress appropriated funds for Hydroelectric Production Incentives under Section 242 of the Energy Policy Act of 2005. Qualified hydroelectric facilities-existing powered or non-powered dams and conduits that added a new turbine or other hydroelectric generating device-may receive up to 1.8

  9. 2015 Electrical Production: EPACT 2005 Section 242 Hydroelectric Incentive

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

    Program | Department of Energy 5 Electrical Production: EPACT 2005 Section 242 Hydroelectric Incentive Program 2015 Electrical Production: EPACT 2005 Section 242 Hydroelectric Incentive Program In 2016, Congress appropriated funds for Hydroelectric Production Incentives under Section 242 of the Energy Policy Act of 2005. Qualified hydroelectric facilities-existing powered or non-powered dams and conduits that added a new turbine or other hydroelectric generating device-may receive up to 1.8

  10. 2015 Electrical Production: EPACT 2005 Section 242 Hydroelectric Incentive

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

    Program | Department of Energy 2015 Electrical Production: EPACT 2005 Section 242 Hydroelectric Incentive Program 2015 Electrical Production: EPACT 2005 Section 242 Hydroelectric Incentive Program In 2016, Congress appropriated funds for Hydroelectric Production Incentives under Section 242 of the Energy Policy Act of 2005. Qualified hydroelectric facilities-existing powered or non-powered dams and conduits that added a new turbine or other hydroelectric generating device-may receive up to

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

    SciTech Connect (OSTI)

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

    1988-01-01

    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.

  12. Utilities' Use of Nuclear Generation

    SciTech Connect (OSTI)

    Ray, Harold B.

    2002-09-30

    This PowerPoint presentation was given at the Nuclear Energy Research Advisory Committee meeting, held 30 September 2002 in Arlington, VA.

  13. U.S. Nuclear Generation of Electricity

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

    U.S. Nuclear Generation and Generating Capacity Data Released: August 25, 2016 Data for: June 2016 Next Release: September 2016 Year Capacity and Generation by State and Reactor 2016 P XLS 2015 P XLS 2014 P XLS 2013 XLS 2012 XLS 2011 XLS 2010 XLS 2009 XLS 2008 XLS 2007 XLS 2006 XLS 2005 XLS 2004 XLS 2003 XLS P = Preliminary 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

  14. Energy 101: Hydroelectric Power

    Broader source: Energy.gov [DOE]

    Learn how hydroelectric power, or hydropower, captures the kinetic energy of flowing water and turns it into electricity for our homes and businesses.

  15. Energy Department Seeks Feedback on Draft Guidance for the Hydroelectr...

    Energy Savers [EERE]

    Any qualified owner or operator of a hydroelectric facility who added hydropower to non-powered dams or conduits ... applications for generation produced in calendar year ...

  16. Accepting Applications: $3.96 Million Hydroelectric Production...

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

    The incentive is available to developers who added hydroelectric power generating capabilities to existing non-powered dams throughout the United States. Equipping local, ...

  17. Hydroelectric energy | Open Energy Information

    Open Energy Info (EERE)

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

  18. Small Hydroelectric | Open Energy Information

    Open Energy Info (EERE)

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

  19. STEAM GENERATOR FOR NUCLEAR REACTOR

    DOE Patents [OSTI]

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

    1963-07-16

    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)

  20. The Birth of Nuclear-Generated Electricity

    DOE R&D Accomplishments [OSTI]

    1999-09-01

    The Experimental Breeder Reactor-I (EBR-I), built in Idaho in 1949, generated the first usable electricity from nuclear power on December 20, 1951. More importantly, the reactor was used to prove that it was possible to create more nuclear fuel in the reactor than it consumed during operation -- fuel breeding. The EBR-I facility is now a National Historic Landmark open to the public.

  1. 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 expiration date" 2,"1,070","6,989",74.6,"PWR","application/vnd.ms-excel","application/vnd.ms-excel"

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

    SciTech Connect (OSTI)

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

    2011-10-01

    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.

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

    SciTech Connect (OSTI)

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

    2011-07-01

    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.

  4. Nuclear power generation and fuel cycle report 1996

    SciTech Connect (OSTI)

    1996-10-01

    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.

  5. Potential nuclear safeguards applications for neutron generators

    SciTech Connect (OSTI)

    Lindquist, L.O.

    1980-01-01

    Many nuclear safeguards inspection instruments use neutron sources to interrogate the fissile material (commonly /sup 235/U and /sup 239/Pu) to be measured. The neutron sources currently used in these instruments are isotopics such as Californium-252, Americium-Lithium, etc. It is becoming increasingly more difficult to transport isotopic sources from one measurement location to another. This represents a significant problem for the International Atomic Energy Agency (IAEA) safeguards inspectors because they must take their safeguards instruments with them to each nuclear installation to make an independent measurement. Purpose of this paper is to review the possibility of replacing isotopic neutron sources now used in IAEA safeguards instruments with electric neutron sources such as deuterium-tritium (D-T, 14-MeV neutrons) or deuterium-deuterium (D-D, 2-MeV neutrons). The potential for neutron generators to interrogate spent-light water reactor fuel assemblies in storage pools is also reviewed.

  6. Nuclear power generation and fuel cycle report 1997

    SciTech Connect (OSTI)

    1997-09-01

    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.

  7. Fostering the Next Generation of Nuclear Energy Technology | Department of

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

    Energy Fostering the Next Generation of Nuclear Energy Technology Fostering the Next Generation of Nuclear Energy Technology September 29, 2014 - 11:06am Addthis Fostering the Next Generation of Nuclear Energy Technology Peter W. Davidson Peter W. Davidson Former Executive Director of the Loan Programs Office (LPO) What are the key facts? If finalized, this solicitation would make available $12.6 billion in loan guarantees for advanced nuclear energy technologies. Learn more about the draft

  8. NNSA Completes Fourth International Meeting on Next Generation Nuclear

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

    Safeguards | National Nuclear Security Administration | (NNSA) NNSA Completes Fourth International Meeting on Next Generation Nuclear Safeguards July 12, 2012 HANOI, VIETNAM - The U.S. Department of Energy's National Nuclear Security Administration (NNSA), together with the Vietnam Agency for Radiation and Nuclear Safety, announced today the successful completion of the Fourth International Meeting on Next Generation Safeguards. Organized by NNSA's Next Generation Safeguards Initiative

  9. Energy Department Accepting Applications for a $3.6 Million Hydroelectric Production Incentive Program

    Office of Energy Efficiency and Renewable Energy (EERE)

    The Energy Department today announced an incentive program for developers adding hydroelectric power generating capabilities to existing non-powered dams throughout the United States.

  10. Next-generation nuclear fuel withstands high-temperature accident...

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

    Next-generation nuclear fuel withstands high-temperature accident conditions IDAHO FALLS - A safer and more efficient nuclear fuel is on the horizon. A team of researchers at the ...

  11. Industry Participation Sought for Design of Next Generation Nuclear Plant |

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

    Department of Energy 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

  12. Bush Administration Moves Forward to Develop Next Generation Nuclear Energy

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

    Systems | Department of Energy 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

  13. Lushui County Quande Hydroelectrical Power Development Ltd |...

    Open Energy Info (EERE)

    County Quande Hydroelectrical Power Development Ltd Jump to: navigation, search Name: Lushui County Quande Hydroelectrical Power Development Ltd. Place: Yunnan Province, China...

  14. Potential Hydroelectric Development at Existing Federal Facilities...

    Open Energy Info (EERE)

    Potential Hydroelectric Development at Existing Federal Facilities Jump to: navigation, search OpenEI Reference LibraryAdd to library Report: Potential Hydroelectric Development at...

  15. Lessons Learned: Pangue Hydroelectric | Open Energy Information

    Open Energy Info (EERE)

    Learned: Pangue Hydroelectric Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Lessons Learned: Pangue Hydroelectric AgencyCompany Organization: International Finance...

  16. Mix and mingle: Networking for the next nuclear generation |...

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

    Mix and mingle: Networking ... Mix and mingle: Networking for the next nuclear generation Posted: February 25, 2016 ... for science, technology, engineering and math employees. ...

  17. Next Generation Nuclear Plant GAP Analysis Report

    SciTech Connect (OSTI)

    Ball, Sydney J; Burchell, Timothy D; Corwin, William R; Fisher, Stephen Eugene; Forsberg, Charles W.; Morris, Robert Noel; Moses, David Lewis

    2008-12-01

    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.

  18. 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 ...

  19. Training the Next Generation of Nuclear Energy Leaders | Department of

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

    Energy 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

  20. NNSA Next Generation Safeguards Initiative | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration | (NNSA) NNSA Next Generation Safeguards Initiative January 02, 2009 International safeguards are a central pillar of the nuclear nonproliferation regime. Administered by the International Atomic Energy Agency (IAEA), international safeguards serve to monitor nuclear activities under the Non-Proliferation Treaty (NPT) and are the primary vehicle for verifying compliance with peaceful use and nuclear nonproliferation undertakings. The Department of Energy's National Nuclear

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

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

    LLC",1628 8,"Powerton","Coal","Midwest Generations EME LLC",1538 9,"Elwood Energy LLC","Natural gas","Elwood Energy LLC",1350 10,"Newton","Coal","Illinois Power Generating Co",119

  2. 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" ...0","9,556",94.0,"PWR","applicationvnd.ms-excel","applicationvnd.ms-excel" ...

  3. The National Nuclear Security Administration's Neutron Generator Activities

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

    National Nuclear Security Administration's Neutron Generator Activities OAS-L-14-11 August 2014 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 August 20, 2014 MEMORANDUM FOR THE MANAGER, SANDIA FIELD OFFICE FROM: David Sedillo Director, Western Audits Division Office of Inspector General SUBJECT: INFORMATION: Audit Report on "The National Nuclear Security Administration's Neutron Generator Activities"

  4. Impact of High Wind Power Penetration on Hydroelectric Unit Operations

    SciTech Connect (OSTI)

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

    2011-01-01

    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.

  5. 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 expiration date" 1,"1,178","9,197",89.1,"PWR","application/vnd.ms-excel","application/vnd.ms-excel"

  6. 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" 1,"1,164","10,337",101.4,"PWR","application/vnd.ms-excel","application/vnd.ms-excel"

  7. AEA Hydroelectric Program

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

    * Technical assistance, regional planning and project management * Provide synergy between ... hydrograph from stream gauging data collection EIA Generation data from ...

  8. Small-Scale Hydroelectric Power Demonstration Project

    SciTech Connect (OSTI)

    Gleeson, L.

    1991-12-01

    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.

  9. 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 (percent)","Type","Commercial operation date","License expiration date" 1,"1,160","9,556",94.0,"PWR","application/vnd.ms-excel","application/vnd.ms-excel"

  10. 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 date" 2,867,"7,727",101.7,"BWR","application/vnd.ms-excel","application/vnd.ms-excel" 3,867,"6,866",90.4,"BWR","application/vnd.ms-excel","application/vnd.ms-excel"

  11. Method and apparatus for generating low energy nuclear particles

    DOE Patents [OSTI]

    Powell, James R.; Reich, Morris; Ludewig, Hans; Todosow, Michael

    1999-02-09

    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.

  12. Method and apparatus for generating low energy nuclear particles

    DOE Patents [OSTI]

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

    1999-02-09

    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.

  13. POWER GENERATION FROM LIQUID METAL NUCLEAR FUEL

    DOE Patents [OSTI]

    Dwyer, O.E.

    1958-12-23

    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.

  14. An Integrated Safety Assessment Methodology for Generation IV Nuclear Systems

    SciTech Connect (OSTI)

    Timothy J. Leahy

    2010-06-01

    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.

  15. EIS-0456: Cushman Hydroelectric Project, Tacoma, Washington

    Broader source: Energy.gov [DOE]

    This EIS is for the design and construction of certain components of the Cushman Hydroelectric Project in Mason County, Washington.

  16. Energy 101: Hydroelectric Power | Department of Energy

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

    Hydroelectric Power Energy 101: Hydroelectric Power Addthis Description Learn how hydropower captures the kinetic energy of flowing water and turns it into electricity for our homes and businesses. Topic Water Text Version Below is the text version for the Energy 101: Hydroelectric Power video: The video opens with the words "Energy 101: Hydroelectric Power." This is followed by a montage of rivers and streams, then a shot of an older water wheel. People have been capturing the energy

  17. ADVANCED CERAMIC MATERIALS FOR NEXT-GENERATION NUCLEAR APPLICATIONS

    SciTech Connect (OSTI)

    Marra, J.

    2010-09-29

    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

  18. NNSA Program Develops the Next Generation of Nuclear Security Experts

    SciTech Connect (OSTI)

    Brim, Cornelia P.; Disney, Maren V.

    2015-09-02

    NNSA is fostering the next generation of nuclear security experts is through its successful NNSA Graduate Fellowship Program (NGFP). NGFP offers its Fellows an exceptional career development opportunity through hands-on experience supporting NNSA mission areas across policy and technology disciplines. The one-year assignments give tomorrow’s leaders in global nuclear security and nonproliferation unparalleled exposure through assignments to Program Offices across NNSA.

  19. Thayer Creek Hydroelectric Update - 2015

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

    Thayer Creek Hydroelectric Update - 2015 2015 Program Review Meeting DOE Tribal Energy Program Denver, Colorado May 5, 2015 Sharon Love General Manger/President Kootznoowoo, Inc. Harold Frank, Jr., M.S. Land and Environmental Planner Kootznoowoo, Inc. Angoon, Alaska Vicinity Map Angoon, Alaska * City of Angoon - 457 people (2013) * Angoon Community Association (IRA tribe) * Kootznoowoo, Inc. - 1,000(+) shareholders (629 original) - ANCSA village corporation * Angoon area inhabited at least

  20. Next Generation Nuclear Plant Materials Selection and Qualification Program Plan

    SciTech Connect (OSTI)

    R. Doug Hamelin; G. O. Hayner

    2004-11-01

    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.

  1. Next Generation Nuclear Plant Materials Research and Development Program Plan

    SciTech Connect (OSTI)

    G. O. Hayner; E.L. Shaber

    2004-09-01

    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.

  2. China Hydroelectric Corp | Open Energy Information

    Open Energy Info (EERE)

    Corp Jump to: navigation, search Name: China Hydroelectric Corp Place: Beijing, Beijing Municipality, China Zip: 100010 Sector: Hydro Product: Engaged in the acquisition of small...

  3. Hebei Hydroelectric Company Limited | Open Energy Information

    Open Energy Info (EERE)

    Place: Shijiazhuang, Hebei Province, China Zip: 50011 Sector: Hydro Product: China-based small hydro project developer. References: Hebei Hydroelectric Company Limited1 This...

  4. Marine Hydroelectric Company | Open Energy Information

    Open Energy Info (EERE)

    to: navigation, search Name: Marine Hydroelectric Company Address: 24040 Camino Del Avion A 107 Place: Monarch Beach Sector: Marine and Hydrokinetic Year Founded: 1983 Phone...

  5. Vermont Water Quality Certification Application for Hydroelectric...

    Open Energy Info (EERE)

    Water Quality Certification Application for Hydroelectric Facilities Jump to: navigation, search OpenEI Reference LibraryAdd to library Form: Vermont Water Quality Certification...

  6. Huaiji Hydroelectric Power Project | Open Energy Information

    Open Energy Info (EERE)

    Power Project Jump to: navigation, search Name: Huaiji Hydroelectric Power Project Place: Guangzhou, Guangdong Province, China Zip: 510620 Product: The Huaiji project involves nine...

  7. Hydroelectric Webinar Presentation Slides and Text Version

    Broader source: Energy.gov [DOE]

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

  8. Reducing Risk for the Next Generation Nuclear Plant

    SciTech Connect (OSTI)

    John M. Beck II; Harold J. Heydt; Emmanuel O. Opare; Kyle B. Oswald

    2010-07-01

    The Next Generation Nuclear Plant (NGNP) Project, managed by the Idaho National Laboratory (INL), is directed by the Energy Policy Act of 2005, to research, develop, design, construct, and operate a prototype forth generation nuclear reactor to meet the needs of the 21st Century. As with all large projects developing and deploying new technologies, the NGNP has numerous risks that need to be identified, tracked, mitigated, and reduced in order for successful project completion. A Risk Management Plan (RMP) was created to outline the process the INL is using to manage the risks and reduction strategies for the NGNP Project. Integral to the RMP is the development and use of a Risk Management System (RMS). The RMS is a tool that supports management and monitoring of the project risks. The RMS does not only contain a risk register, but other functionality that allows decision makers, engineering staff, and technology researchers to review and monitor the risks as the project matures.

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

    SciTech Connect (OSTI)

    Radulescu, Laura; Pavelescu, Margarit

    2010-01-21

    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.

  10. Salt disposal of heat-generating nuclear waste.

    SciTech Connect (OSTI)

    Leigh, Christi D.; Hansen, Francis D.

    2011-01-01

    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

  11. Longyang Zone Hongqiang Hydroelectric Power Development Co Ltd...

    Open Energy Info (EERE)

    Longyang Zone Hongqiang Hydroelectric Power Development Co Ltd Jump to: navigation, search Name: Longyang Zone Hongqiang Hydroelectric Power Development Co., Ltd. Place: Baoshan...

  12. Yingjiang County Binglang River Hydroelectric Power Co Ltd |...

    Open Energy Info (EERE)

    Yingjiang County Binglang River Hydroelectric Power Co Ltd Jump to: navigation, search Name: Yingjiang County Binglang River Hydroelectric Power Co., Ltd. Place: Dehong Dai-Jingpo...

  13. Bihar State Hydroelectric Power Corp BSHPC | Open Energy Information

    Open Energy Info (EERE)

    Hydroelectric Power Corp BSHPC Jump to: navigation, search Name: Bihar State Hydroelectric Power Corp (BSHPC) Place: Patna, Bihar, India Sector: Hydro Product: Patna-based nodal...

  14. List of Small Hydroelectric Incentives | Open Energy Information

    Open Energy Info (EERE)

    using Renewable Fuels Geothermal Electric Photovoltaics Renewable Fuels Solar Water Heat Natural Gas Hydroelectric energy Small Hydroelectric Yes Alternative Energy Development...

  15. Ningguo Liucunba Hydroelectric Co Ltd | Open Energy Information

    Open Energy Info (EERE)

    Ningguo Liucunba Hydroelectric Co Ltd Jump to: navigation, search Name: Ningguo Liucunba Hydroelectric Co., Ltd. Place: Ningguo, Anhui Province, China Zip: Ningguo Sector: Hydro...

  16. Hunan Mayang Hengyuan Hydroelectric Development Co Ltd | Open...

    Open Energy Info (EERE)

    Hengyuan Hydroelectric Development Co Ltd Jump to: navigation, search Name: Hunan Mayang Hengyuan Hydroelectric Development Co. Ltd. Place: Huaihua, Hunan Province, China Zip:...

  17. Wuxi Longshui Hydroelectric Power Development Co Ltd | Open Energy...

    Open Energy Info (EERE)

    Longshui Hydroelectric Power Development Co Ltd Jump to: navigation, search Name: Wuxi Longshui Hydroelectric Power Development Co. Ltd Place: Chongqing, Chongqing Municipality,...

  18. Xinhuang Xincun Hydroelectric Co Ltd | Open Energy Information

    Open Energy Info (EERE)

    Xinhuang Xincun Hydroelectric Co Ltd Jump to: navigation, search Name: Xinhuang Xincun Hydroelectric Co. Ltd. Place: Huaihua, Hunan Province, China Zip: 419200 Sector: Hydro...

  19. Shangri La County Minhe Hydroelectric Development Co Ltd | Open...

    Open Energy Info (EERE)

    Minhe Hydroelectric Development Co Ltd Jump to: navigation, search Name: Shangri-La County Minhe Hydroelectric Development Co., Ltd. Place: Yunnan Province, China Zip: 650051...

  20. Zixing Liyujiang Hydroelectric Co Ltd | Open Energy Information

    Open Energy Info (EERE)

    Zixing Liyujiang Hydroelectric Co Ltd Jump to: navigation, search Name: Zixing Liyujiang Hydroelectric Co., Ltd Place: Hunan Province, China Zip: 423402 Sector: Hydro Product:...

  1. Sangzhi Zhongyuan Hydroelectric Power Station | Open Energy Informatio...

    Open Energy Info (EERE)

    Zhongyuan Hydroelectric Power Station Jump to: navigation, search Name: Sangzhi Zhongyuan Hydroelectric Power Station Place: Zhangjiajie, Hunan Province, China Zip: 427100 Sector:...

  2. Jinping Guoneng Hydroelectric Development Co Ltd | Open Energy...

    Open Energy Info (EERE)

    Hydroelectric Development Co Ltd Jump to: navigation, search Name: Jinping Guoneng Hydroelectric Development Co., Ltd Place: Jinping, Yunnan Province, China Zip: 661507 Sector:...

  3. Hunan Zhexi hydroelectric Co Ltd | Open Energy Information

    Open Energy Info (EERE)

    Zhexi hydroelectric Co Ltd Jump to: navigation, search Name: Hunan Zhexi hydroelectric Co., Ltd. Place: Shaoyang, Hunan Province, China Zip: 422200 Sector: Hydro Product:...

  4. Sichuan Bahe Hydroelectric Development Co Ltd | Open Energy Informatio...

    Open Energy Info (EERE)

    Bahe Hydroelectric Development Co Ltd Jump to: navigation, search Name: Sichuan Bahe Hydroelectric Development Co. Ltd. Place: Bazhong, Sichuan Province, China Zip: 635400 Sector:...

  5. Cangxi Jianghe Hydroelectric Power Development Co Ltd | Open...

    Open Energy Info (EERE)

    Cangxi Jianghe Hydroelectric Power Development Co Ltd Jump to: navigation, search Name: Cangxi Jianghe Hydroelectric Power Development Co., Ltd. Place: Guanyuan, Sichuan Province,...

  6. Guangxi Shenghui Haihe Hydroelectric Development Co Ltd | Open...

    Open Energy Info (EERE)

    Shenghui Haihe Hydroelectric Development Co Ltd Jump to: navigation, search Name: Guangxi Shenghui Haihe Hydroelectric Development Co., Ltd Place: Hechi, Guangxi Autonomous Region,...

  7. Shimen Boyuan Hydroelectric Co Ltd | Open Energy Information

    Open Energy Info (EERE)

    Shimen Boyuan Hydroelectric Co Ltd Jump to: navigation, search Name: Shimen Boyuan Hydroelectric Co. Ltd. Place: Changsha, Hunan Province, China Zip: 410004 Sector: Hydro Product:...

  8. Lintan Luertai Hydroelectric Power Company Ltd | Open Energy...

    Open Energy Info (EERE)

    Luertai Hydroelectric Power Company Ltd Jump to: navigation, search Name: Lintan Luertai Hydroelectric Power Company, Ltd Place: Lintan County, Gansu Province, China Sector: Hydro...

  9. Qiyang Yangguang Hydroelectric Co Ltd | Open Energy Information

    Open Energy Info (EERE)

    Hydroelectric Co Ltd Jump to: navigation, search Name: Qiyang Yangguang Hydroelectric Co., Ltd Place: Yongzhou, Hunan Province, China Zip: 426100 Sector: Hydro Product: Hunan-based...

  10. Guangxi Baise City Chenyu Hydroelectric Development Co Ltd |...

    Open Energy Info (EERE)

    Baise City Chenyu Hydroelectric Development Co Ltd Jump to: navigation, search Name: Guangxi Baise City Chenyu Hydroelectric Development Co., Ltd. Place: Baise, Guangxi Autonomous...

  11. Hunan Caishi Hydroelectric Co Ltd | Open Energy Information

    Open Energy Info (EERE)

    Caishi Hydroelectric Co Ltd Jump to: navigation, search Name: Hunan Caishi Hydroelectric Co., Ltd Place: Hunan Province, China Zip: 427221 Sector: Hydro Product: Hunan-based small...

  12. Qiyang Haojie Hydroelectric Co Ltd | Open Energy Information

    Open Energy Info (EERE)

    Haojie Hydroelectric Co Ltd Jump to: navigation, search Name: Qiyang Haojie Hydroelectric Co., Ltd Place: Yongzhou City, Hunan Province, China Zip: 426100 Sector: Hydro Product:...

  13. Shaowu Jinwei Hydroelectric Power Development Co Ltd | Open Energy...

    Open Energy Info (EERE)

    Shaowu Jinwei Hydroelectric Power Development Co Ltd Jump to: navigation, search Name: Shaowu Jinwei Hydroelectric Power Development Co., Ltd. Place: Shaowu City, Fujian Province,...

  14. Golmud Kunlun Hydroelectric Co Ltd | Open Energy Information

    Open Energy Info (EERE)

    Golmud Kunlun Hydroelectric Co Ltd Jump to: navigation, search Name: Golmud Kunlun Hydroelectric Co., Ltd. Place: Qinghai Province, China Sector: Hydro Product: China-based small...

  15. Zhijiang Peace Hydroelectric Co Ltd | Open Energy Information

    Open Energy Info (EERE)

    Zhijiang Peace Hydroelectric Co Ltd Jump to: navigation, search Name: Zhijiang Peace Hydroelectric Co. Ltd Place: Huaihua City, Hunan Province, China Sector: Hydro Product:...

  16. Dongkou Zhexiang hydroelectric Co Ltd | Open Energy Information

    Open Energy Info (EERE)

    Zhexiang hydroelectric Co Ltd Jump to: navigation, search Name: Dongkou Zhexiang hydroelectric Co. Ltd. Place: Shaoyang, Hunan Province, China Zip: 422300 Sector: Hydro Product:...

  17. Xuan en Tongziying Hydroelectric Power Development Co Ltd | Open...

    Open Energy Info (EERE)

    Tongziying Hydroelectric Power Development Co Ltd Jump to: navigation, search Name: Xuan(tm)en Tongziying Hydroelectric Power Development Co., Ltd. Place: Enshi Prefecture,...

  18. Winter Hydroelectric Dam Feasibility Assessment: The Lac Courte...

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

    WINTER HYDROELECTRIC DAM FEASIBILITY ASSESSMENT THE LAC COURTE OREILLES BAND OF LAKE ... IN 1920 AND COMPLETED BY 1923 THE HYDROELECTRIC FACILITY WAS BUILT IN 1988. ISSUES ...

  19. 2015 Electrical Production: EPACT 2005 Section 242 Hydroelectric...

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

    In 2016, Congress appropriated funds for Hydroelectric Production Incentives under Section 242 of the Energy Policy Act of 2005. Qualified hydroelectric facilities-existing powered ...

  20. Hunan Jishou Sanlian Hydroelectric Investment Co Ltd | Open Energy...

    Open Energy Info (EERE)

    Jishou Sanlian Hydroelectric Investment Co Ltd Jump to: navigation, search Name: Hunan Jishou Sanlian Hydroelectric Investment Co., Ltd Place: Jishou, Hunan Province, China Zip:...

  1. S ENERGY POLICY ACT OF 2005 SECTION 242 HYDROELECTRIC INCENTIVE...

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

    Project Albany Engineering Corporation (AEC) Stuyvesant Falls Hydroelectric Project ... Hydro Green Mountain Power Corp. Essex Hydroelectric Station Unit 9 Hydrodynamics Inc. ...

  2. Wind and Hydroelectric Feasibility Study - Bristol Bay Native...

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

    Wind and Wind and Hydroelectric Hydroelectric Feasibility Feasibility Study Study Tiel Smith Tiel Smith - - BBNC BBNC Doug Vaught, PE Doug Vaught, PE - - Consultant Consultant A ...

  3. The Belleville Hydroelectric Project - An overview

    SciTech Connect (OSTI)

    Gemperline, E.J.; Konstantellos, C.; Meier, P.E.

    1995-12-31

    The Belleville Hydroelectric Project, a 42 MW project on the Ohio River at the U.S. Army Corps of Engineers (USACE) Belleville Locks and Dam was licensed to the City of Jackson, Ohio in 1989. In 1993 a joint venture of 42 Ohio municipal electric suppliers was formed to develop the project - known as Ohio Municipal Electric Generation Agency Joint Venture 5. Design of the project, including procurement of the turbines and generators, began the same year. At the time this paper is being published project construction is beginning with development of the cofferdams. Completion of the project is scheduled for late 1997. The project will be located on the east bank of the Ohio River. Energy will be generated by two identical 24.6 ft (7.5 m) runner diameter 21 MW bulb turbines, among the world`s largest. Each unit will operate over a head range of from 5 ft to 22 ft (1.5 m to 6.7 m), and discharges from 3000 ft{sup 3}/sec (cfs) to 20,000 cfs (85 m{sup 3}/s to 566 m{sup 3}/s). This paper includes discussions of project history, operation, siting, layout, design and other considerations.

  4. Yacyreta hydroelectric project contract signed

    SciTech Connect (OSTI)

    Not Available

    1987-09-01

    On June 26, 1987 the $270 million contract for the supply of 20 large hydraulic turbines for the Yacyreta Hydroelectric Project was signed by the Entidad Binacional Yacyreta, (a binational agency created by the governments of Argentina and Paraguay for the development of Yacyreta), and by Voith Hydro, Inc., of York, Pennsylvania, and Canadian General Electric of Montreal, Canada. Under the terms of the contract, 9 turbine units will be supplied by Voith Hydro, Inc. from its York, Pennsylvania plant, 4 units by Canadian General Electric of Montreal, and 7 units by Metanac, a consortium of Argentine manufacturers, who will utilize technology and technical assistance from Voith and CGE. The Yacyreta Project is being built on the Parana River on the border between Argentina and Paraguay. Construction at the site commenced in late 1983. Voith's portion of this contrast represents approximately $130 million dollars worth of business for its York, Pennsylvania facility.

  5. Table 9.1 Nuclear Generating Units, 1955-2011

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

    1 Nuclear Generating Units, 1955-2011 Year Original Licensing Regulations (10 CFR Part 50) 1 Current Licensing Regulations (10 CFR Part 52) 1 Permanent Shutdowns Operable Units 7 Construction Permits Issued 2,3 Low-Power Operating Licenses Issued 3,4 Full-Power Operating Licenses Issued 3,5 Early Site Permits Issued 3 Combined License Applications Received 6 Combined Licenses Issued 3 1955 1 0 0 – – – – – – 0 0 1956 3 0 0 – – – – – – 0 0 1957 1 1 1 – – – – – – 0 1 1958 0 0 0 –

  6. HIGH EFFICIENCY GENERATION OF HYDROGEN FUELS USING NUCLEAR POWER

    SciTech Connect (OSTI)

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

    2003-06-01

    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

  7. Generating unstructured nuclear reactor core meshes in parallel

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Jain, Rajeev; Tautges, Timothy J.

    2014-10-24

    Recent advances in supercomputers and parallel solver techniques have enabled users to run large simulations problems using millions of processors. Techniques for multiphysics nuclear reactor core simulations are under active development in several countries. Most of these techniques require large unstructured meshes that can be hard to generate in a standalone desktop computers because of high memory requirements, limited processing power, and other complexities. We have previously reported on a hierarchical lattice-based approach for generating reactor core meshes. Here, we describe efforts to exploit coarse-grained parallelism during reactor assembly and reactor core mesh generation processes. We highlight several reactor coremore » examples including a very high temperature reactor, a full-core model of the Korean MONJU reactor, a ¼ pressurized water reactor core, the fast reactor Experimental Breeder Reactor-II core with a XX09 assembly, and an advanced breeder test reactor core. The times required to generate large mesh models, along with speedups obtained from running these problems in parallel, are reported. A graphical user interface to the tools described here has also been developed.« less

  8. Generating unstructured nuclear reactor core meshes in parallel

    SciTech Connect (OSTI)

    Jain, Rajeev; Tautges, Timothy J.

    2014-10-24

    Recent advances in supercomputers and parallel solver techniques have enabled users to run large simulations problems using millions of processors. Techniques for multiphysics nuclear reactor core simulations are under active development in several countries. Most of these techniques require large unstructured meshes that can be hard to generate in a standalone desktop computers because of high memory requirements, limited processing power, and other complexities. We have previously reported on a hierarchical lattice-based approach for generating reactor core meshes. Here, we describe efforts to exploit coarse-grained parallelism during reactor assembly and reactor core mesh generation processes. We highlight several reactor core examples including a very high temperature reactor, a full-core model of the Korean MONJU reactor, a ¼ pressurized water reactor core, the fast reactor Experimental Breeder Reactor-II core with a XX09 assembly, and an advanced breeder test reactor core. The times required to generate large mesh models, along with speedups obtained from running these problems in parallel, are reported. A graphical user interface to the tools described here has also been developed.

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

    Reports and Publications (EIA)

    2011-01-01

    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.

  10. Following Nature's Current HYDROELECTRIC POWER IN THE NORTHWEST

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

    9 Environmental Protection, Mitigation and Enhancement at Hydroelectric Projects ----10 Fish Passage Tour ---...

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

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

    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

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

    SciTech Connect (OSTI)

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

    2009-03-01

    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.

  13. Indian River Hydroelectric Project Grant

    SciTech Connect (OSTI)

    Rebecca Garrett

    2005-04-29

    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.

  14. NEXT GENERATION NUCLEAR PLANT LICENSING BASIS EVENT SELECTION WHITE PAPER

    SciTech Connect (OSTI)

    Mark Holbrook

    2010-09-01

    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.

  15. Next Generation Nuclear Plant Resilient Control System Functional Analysis

    SciTech Connect (OSTI)

    Lynne M. Stevens

    2010-07-01

    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.

  16. Hoopa Valley Small Scale Hydroelectric Feasibility Project

    SciTech Connect (OSTI)

    Curtis Miller

    2009-03-22

    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.

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

    ScienceCinema (OSTI)

    Thomas D'Agostino

    2010-09-01

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

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

    ScienceCinema (OSTI)

    Thomas D'Agostino

    2010-09-01

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

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

    SciTech Connect (OSTI)

    Thomas D'Agostino

    2009-07-14

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

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

    SciTech Connect (OSTI)

    Thomas D'Agostino

    2009-07-14

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

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

    SciTech Connect (OSTI)

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

    2011-01-01

    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.

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

    SciTech Connect (OSTI)

    Dr. Mark Schanfein; Philip Casey Durst

    2012-07-01

    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.

  3. Nuclear Power Generation and Fuel Cycle Report 1996

    Reports and Publications (EIA)

    1996-01-01

    This report provides information and forecasts important to the domestic and world nuclear and uranium industries.

  4. Hydroelectric power in Hawaii. A report on the statewide survey of potential hydroelectric sites

    SciTech Connect (OSTI)

    Beck, C. A.

    1981-02-01

    An assessment was made of the hydropower potential in Hawaii. The major conclusion of this study is that hydropower resources in the State of Hawaii are substantial, and they offer the potential for major increases in hydropower generating capacity. Hydropower resources on all islands total about 50 MW of potential generating capacity. Combined with the 18 MW of existing hydropower capacity, hydropower resources potentially could generate about 307 million kWh of electric energy annually. This represents about 28% of the present combined electricity needs of the Neighbor Islands, Kauai, Molokai, Maui, and the Big Island. Hydropower resources on Kauai equal 72% of that island's electricity needs; on Molokai, 40%, on the Big Island, 20%; and on Maui, 18%. The island of Oahu, however, has only small hydropower resources, and could only generate a negligible portion of its electricity needs from this energy source. A summary of existing and future (potential) hydropower capacities and estimated annual outputs for each island is presented. How much of the potential capacity is being actively considered for development and how much is only tentatively proposed at the time is indicated. The economics of hydropower at specific sites were analyzed. The major conclusion of this analysis is that hydropower development costs vary widely among the different sites, but that generally the cost of hydroelectric power is either less than or comparable to the cost of oil-fired power.

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

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

    Department of Energy 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

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

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

    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

  7. Next Generation Nuclear Plant Materials Research and Development Program Plan

    SciTech Connect (OSTI)

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

    2005-09-01

    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

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

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

    Energy 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

  9. Next Generation Nuclear Plant Research and Development Program Plan

    SciTech Connect (OSTI)

    2005-01-01

    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

  10. Small Modular Reactors- Key to Future Nuclear Power Generation in the U.S.

    Office of Energy Efficiency and Renewable Energy (EERE)

    Small Modular Reactors - Key to Future Nuclear Power Generation in the U.S. University of Chicago, Energy Policy Institute at Chicago

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

    SciTech Connect (OSTI)

    Simma, Fred Y.; Chetwynd, Russell J.; Rowe, Stuart A.

    2006-07-01

    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

  12. Meeting the Next Generation of Nuclear Nonproliferation Specialists...

    National Nuclear Security Administration (NNSA)

    ... DNN R&D directs an integrated research and development portfolio in support of its mission to detect signs of nuclear proliferation and nuclear detonations. The DNN R&D-funded ...

  13. Next Generation Nuclear Plant Methods Technical Program Plan

    SciTech Connect (OSTI)

    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

    2007-01-01

    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.

  14. Next Generation Nuclear Plant Methods Technical Program Plan

    SciTech Connect (OSTI)

    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

    2010-12-01

    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.

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

    SciTech Connect (OSTI)

    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

    2010-09-01

    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.

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

    SciTech Connect (OSTI)

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

    1987-06-01

    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.

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

    SciTech Connect (OSTI)

    L.E. Demick

    2011-10-01

    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.

  18. Radionuclide gas transport through nuclear explosion-generated fracture networks

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Jordan, Amy B.; Stauffer, Philip H.; Knight, Earl E.; Rougier, Esteban; Anderson, Dale N.

    2015-12-17

    Underground nuclear weapon testing produces radionuclide gases which may seep to the surface. Barometric pumping of gas through explosion-fractured rock is investigated using a new sequentially-coupled hydrodynamic rock damage/gas transport model. Fracture networks are produced for two rock types (granite and tuff) and three depths of burial. The fracture networks are integrated into a flow and transport numerical model driven by surface pressure signals of differing amplitude and variability. There are major differences between predictions using a realistic fracture network and prior results that used a simplified geometry. Matrix porosity and maximum fracture aperture have the greatest impact on gasmore » breakthrough time and window of opportunity for detection, with different effects between granite and tuff simulations highlighting the importance of accurately simulating the fracture network. In particular, maximum fracture aperture has an opposite effect on tuff and granite, due to different damage patterns and their effect on the barometric pumping process. From stochastic simulations using randomly generated hydrogeologic parameters, normalized detection curves are presented to show differences in optimal sampling time for granite and tuff simulations. In conclusion, seasonal and location-based effects on breakthrough, which occur due to differences in barometric forcing, are stronger where the barometric signal is highly variable.« less

  19. Radionuclide gas transport through nuclear explosion-generated fracture networks

    SciTech Connect (OSTI)

    Jordan, Amy B.; Stauffer, Philip H.; Knight, Earl E.; Rougier, Esteban; Anderson, Dale N.

    2015-12-17

    Underground nuclear weapon testing produces radionuclide gases which may seep to the surface. Barometric pumping of gas through explosion-fractured rock is investigated using a new sequentially-coupled hydrodynamic rock damage/gas transport model. Fracture networks are produced for two rock types (granite and tuff) and three depths of burial. The fracture networks are integrated into a flow and transport numerical model driven by surface pressure signals of differing amplitude and variability. There are major differences between predictions using a realistic fracture network and prior results that used a simplified geometry. Matrix porosity and maximum fracture aperture have the greatest impact on gas breakthrough time and window of opportunity for detection, with different effects between granite and tuff simulations highlighting the importance of accurately simulating the fracture network. In particular, maximum fracture aperture has an opposite effect on tuff and granite, due to different damage patterns and their effect on the barometric pumping process. From stochastic simulations using randomly generated hydrogeologic parameters, normalized detection curves are presented to show differences in optimal sampling time for granite and tuff simulations. In conclusion, seasonal and location-based effects on breakthrough, which occur due to differences in barometric forcing, are stronger where the barometric signal is highly variable.

  20. Managing water temperatures below hydroelectric facilities

    SciTech Connect (OSTI)

    Johnson, P.L.; Vermeyen, T.B.; O`Haver, G.G.

    1995-05-01

    Due to drought-related water temperature problems in the Bureau of Reclamation`s California Central Valley Project in the early 1990`s, engineers were forced to bypass water from the plants during critical periods. This was done at considerable cost in the form of lost revenue. As a result, an alternative method of lowering water temperature was developed and it has successfully lowered water temperatures downstream from hydroelectric facilities by using flexible rubber curtains. This innovative technology is aiding the survival of endangered fish populations. This article outlines the efforts and discusses the implementation of this method at several hydroelectric facilities in the area.

  1. Next Generation Nuclear Plant Research and Development Program Plan

    SciTech Connect (OSTI)

    P. E. MacDonald

    2005-01-01

    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

  2. Title 16 USC 823a Conduit Hydroelectric Facilities | Open Energy...

    Open Energy Info (EERE)

    a Conduit Hydroelectric Facilities Jump to: navigation, search OpenEI Reference LibraryAdd to library Legal Document- StatuteStatute: Title 16 USC 823a Conduit Hydroelectric...

  3. 2015 Electrical Production: EPACT 2005 Section 242 Hydroelectric...

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

    Section 242 of the Energy Policy Act of 2005. Qualified hydroelectric facilities-existing powered or non-powered dams and conduits that added a new turbine or other hydroelectric ...

  4. 2013 Electrical Production: EPAct 2005 Section 242 Hydroelectric...

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

    Section 242 of the Energy Policy Act of 2005. Qualified hydroelectric facilities-existing powered or non-powered dams and conduits that added a new turbine or other hydroelectric ...

  5. Final Guidance for EPAct 2005 Section 242 Hydroelectric Incentive...

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

    Section 242 of the Energy Policy Act of 2005. Qualified hydroelectric facilities-existing powered or non-powered dams and conduits that added a new turbine or other hydroelectric ...

  6. A High Intensity Multi-Purpose D-D Neutron Generator for Nuclear Engineering Laboratories

    SciTech Connect (OSTI)

    Ka-Ngo Leung; Jasmina L. Vujic; Edward C. Morse; Per F. Peterson

    2005-11-29

    This NEER project involves the design, construction and testing of a low-cost high intensity D-D neutron generator for teaching nuclear engineering students in a laboratory environment without radioisotopes or a nuclear reactor. The neutron generator was designed, fabricated and tested at Lawrence Berkeley National Laboratory (LBNL).

  7. Nuclear Power Generation and Fuel Cycle Report 1997

    Reports and Publications (EIA)

    1997-01-01

    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.

  8. Investing in the next generation: The Office of Nuclear Energy...

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

    educational and research opportunities to prepare NS&E students for nuclear energy professions, in support of NE's mission. NE is seeking applicants for undergraduate...

  9. Tribal Renewable Energy Foundational Course: Hydroelectric | Department of

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

    Energy Hydroelectric Tribal Renewable Energy Foundational Course: Hydroelectric Watch the U.S. Department of Energy Office of Indian Energy foundational course webinar on hydroelectric renewable energy by clicking on the .swf link below. You can also download the PowerPoint slides and a text version of the audio. See the full list of DOE Office of Indian Energy educational webinars and provide your feedback on the National Training & Education Resource (NTER) website. hydroelectric.swf

  10. Investing in the next generation: The Office of Nuclear Energy...

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

    The IUP mission is to maintain the discipline of nuclear science and engineering (NS&E). The NE component of IUP supports this mission by providing educational and research ...

  11. Method and apparatus for generating low energy nuclear particles...

    Office of Scientific and Technical Information (OSTI)

    A thin target (14) is rotated in the path of the input beam for undergoing nuclear ... The target (14) produces low energy secondary particles and is effectively cooled by ...

  12. DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear...

    Energy Savers [EERE]

    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 ...

  13. Next Generation Nuclear Plant Steam Generator and Intermediate Heat Exchanger Materials Research and Development Plan

    SciTech Connect (OSTI)

    J. K. Wright

    2010-09-01

    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

  14. Hydroelectric redevelopment maintains heritage values

    SciTech Connect (OSTI)

    Bulkovshteyn, L.; Chidiac, M.; Hall, W.

    1995-12-31

    The Seymour GS is an 80 year old generating station on the historic Trent-Severn Waterway in Ontario, Canada. The rehabilitation at Seymour was approved by Provincial and Federal authorities on condition that the original appearance of the building be maintained. The capacity of the Generating Station (GS) is being uprated from 3.15 MW to 5.7 MW, by replacing five vertical double runner Francis units with five horizontal Kaplan turbines. The replacement of vertical Francis units with horizontal Kaplan units, necessitated an extensive and innovative demolition approach for the substructure modification. The new turbines required a powerhouse base slab 3.5 m below the grade of the original slab. This required removal of the existing slabs and foundation rock along with most of the interior powerhouse walls. The type of modification and demolition were carefully chosen to accommodate a very tight schedule dictated by the requirement of the Federal Department of Fisheries and Oceans (DFO), where in-water work is restricted to certain months of the year.

  15. 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

    SciTech Connect (OSTI)

    Jager, Yetta; Smith, Brennan T

    2008-02-01

    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.

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

    SciTech Connect (OSTI)

    John Collins

    2009-01-01

    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.

  17. Design Features and Technology Uncertainties for the Next Generation Nuclear Plant

    SciTech Connect (OSTI)

    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

    2004-06-01

    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.

  18. Next Generation Nuclear Plant Project 2009 Status Report

    SciTech Connect (OSTI)

    Larry Demick; Jim Kinsey; Keith Perry; Dave Petti

    2010-05-01

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

  19. 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 expiration date" 1,"1,174","8,777",85.3,"PWR","application/vnd.ms-excel","application/vnd.ms-excel"

  20. 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 date" 1,"1,118","9,207",94.0,"BWR","application/vnd.ms-excel","application/vnd.ms-excel"

  1. Installation of a Low Flow Unit at the Abiquiu Hydroelectric Facility

    SciTech Connect (OSTI)

    Jack Q. Richardson

    2012-06-28

    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.

  2. Seismic risk assessment as applied to the Zion Nuclear Generating Station

    SciTech Connect (OSTI)

    Wells, J.

    1984-08-01

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

  3. 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 expiration date" 1,"1,161","9,439",92.8,"BWR","application/vnd.ms-excel","application/vnd.ms-excel" ,"1,161","9,439",92.8

  4. Yonggwang nuclear power plant units 3 and 4; Bridging the gap to the next generation

    SciTech Connect (OSTI)

    Heider, R.C.; Daley, T.J.; Green, K.J. )

    1991-01-01

    This paper reports on the use of nuclear energy since the oil embargo of 1973 has displaced the use of 4.3 billion barrels of imported oil, which helped conserve 1 billion tons of coal and 6.5 trillion cubic feet of natural gas for future generations, and helped protect the environment by reducing utility emissions of carbon dioxide by 20% a year. The current 112 operating nuclear energy plants generate more electricity than those of France, Japan, and the Soviet Union-nations that have made a national commitment to nuclear energy-combined. Yet it has been over 10 years since the last construction permit was issued for a nuclear power plant in the United States. Considering a projected shortfall in baseload electric generation capacity in the mid-1990s, new requirements for costly air pollution controls on coal plants, the concern over increased dependence on oil imports from the unstable Middle East region, and the increased concern over the possible long-term effects of greenhouse gas emissions, the Nuclear Power Oversight Committee (NPOC), the governing organization for the commercial nuclear energy industry, has developed a strategic plan with the goal of being able to order new nuclear power plants by the mid-1990s. The strategic plan, which contains 14 enabling conditions or building blocks, outlines an integrated effort to address the range of institutional and technical issues on which significant progress must be achieved to make nuclear power attractive in the United States for the 1990s.

  5. Environmental Impacts of Increased Hydroelectric Development at Existing

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

    Dams | Department of Energy Impacts of Increased Hydroelectric Development at Existing Dams Environmental Impacts of Increased Hydroelectric Development at Existing Dams This report describes the environmental impacts of a proposed U.S. Department of Energy (DOE) initiative to promote the development of hydropower resources at existing dams. enviro_impacts_hydroelectric_dev_existing_dams.pdf (2.77 MB) More Documents & Publications EA-2017: Final Environmental Assessment Hydropower Vision

  6. Final Technical Report - Modernization of the Boulder Canyon Hydroelectric Project

    SciTech Connect (OSTI)

    Joe Taddeucci, P E

    2013-03-29

    The Boulder Canyon Hydroelectric Project (BCH) was purchased by the City of Boulder, CO (the city) in 2001. Project facilities were originally constructed in 1910 and upgraded in the 1930s and 1940s. By 2009, the two 10 MW turbine/generators had reached or were nearing the end of their useful lives. One generator had grounded out and was beyond repair, reducing plant capacity to 10 MW. The remaining 10 MW unit was expected to fail at any time. When the BCH power plant was originally constructed, a sizeable water supply was available for the sole purpose of hydroelectric power generation. Between 1950 and 2001, that water supply had gradually been converted to municipal water supply by the city. By 2001, the water available for hydroelectric power generation at BCH could not support even one 10 MW unit. Boulder lacked the financial resources to modernize the facilities, and Boulder anticipated that when the single, operational historical unit failed, the project would cease operation. In 2009, the City of Boulder applied for and received a U.S. Department of Energy (DOE) grant for $1.18 million toward a total estimated project cost of $5.155 million to modernize BCH. The federal funding allowed Boulder to move forward with plant modifications that would ensure BCH would continue operation. Federal funding was made available through the American Recovery and Reinvestment Act (ARRA) of 2009. Boulder determined that a single 5 MW turbine/generator would be the most appropriate capacity, given the reduced water supply to the plant. Average annual BCH generation with the old 10 MW unit had been about 8,500 MW-hr, whereas annual generation with a new, efficient turbine could average 11,000 to 12,000 MW-hr. The incremental change in annual generation represents a 30% increase in generation over pre-project conditions. The old turbine/generator was a single nozzle Pelton turbine with a 5-to-1 flow turndown and a maximum turbine/generator efficiency of 82%. The new unit is a

  7. FERC Handbook for Hydroelectric Project Licensing and 5 MW Exemptions...

    Open Energy Info (EERE)

    Handbook for Hydroelectric Project Licensing and 5 MW Exemptions from Licensing Jump to: navigation, search OpenEI Reference LibraryAdd to library PermittingRegulatory Guidance -...

  8. Forest Service Handbook 2709.15 - Hydroelectric Handbook | Open...

    Open Energy Info (EERE)

    search OpenEI Reference LibraryAdd to library PermittingRegulatory Guidance - GuideHandbook: Forest Service Handbook 2709.15 - Hydroelectric HandbookPermitting...

  9. Asia Power Leibo Hydroelectricity Co Ltd | Open Energy Information

    Open Energy Info (EERE)

    Province, China Sector: Hydro Product: China-based developer and operator of small hydro plants. References: Asia Power (Leibo) Hydroelectricity Co Ltd1 This article is a...

  10. FERC Handbook for Hydroelectric Filings other than Licenses and...

    Open Energy Info (EERE)

    search OpenEI Reference LibraryAdd to library PermittingRegulatory Guidance - GuideHandbook: FERC Handbook for Hydroelectric Filings other than Licenses and...

  11. FERC Hydroelectric Project Handbook for Filings other than Licenses...

    Open Energy Info (EERE)

    Hydroelectric Project Handbook for Filings other than Licenses and Exemptions Jump to: navigation, search OpenEI Reference LibraryAdd to library PermittingRegulatory Guidance -...

  12. The development of advanced hydroelectric turbines to improve...

    Office of Scientific and Technical Information (OSTI)

    turbines to improve fish passage survival Citation Details In-Document Search Title: The development of advanced hydroelectric turbines to improve fish passage survival You ...

  13. The development of advanced hydroelectric turbines to improve...

    Office of Scientific and Technical Information (OSTI)

    turbines to improve fish passage survival Citation Details In-Document Search Title: The development of advanced hydroelectric turbines to improve fish passage survival Recent ...

  14. The Development of Small Hydroelectric Projects in Vermont |...

    Open Energy Info (EERE)

    potential, the state and federal regulatory processes, the impacts of dams on rivers, the principles behind hydroelectric facility design, the importance of streamflow protection,...

  15. MHK Projects/Deception Pass Tidal Energy Hydroelectric Project...

    Open Energy Info (EERE)

    Deception Pass Tidal Energy Hydroelectric Project < MHK Projects Jump to: navigation, search << Return to the MHK database homepage Loading map... "minzoom":false,"mappingservice"...

  16. Final Guidance for EPAct 2005 Section 242 Hydroelectric Incentive Program

    Broader source: Energy.gov [DOE]

    This document contains the Final Guidance for the EPAct 2005 Section 242 Hydroelectric Incentive Program. Applications are due February 20, 2015.

  17. Accepting Applications: $3.96 Million Hydroelectric Production Incentive Program

    Broader source: Energy.gov [DOE]

    A second round of funding for the Section 242 Hydroelectric Incentive Program is now available from the Energy Department's Water Power Program.

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

    SciTech Connect (OSTI)

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

    1987-08-01

    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.

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

    Office of Energy Efficiency and Renewable Energy (EERE)

    Building on President Obama’s Climate Action Plan to continue America’s leadership in clean energy innovation, the Energy Department announced more than $60 million in nuclear energy research awards and improvements to university research reactors and infrastructure.

  20. Impact of the proposed energy tax on nuclear electric generating technologies

    SciTech Connect (OSTI)

    Edmunds, T.A.; Lamont, A.D.; Pasternak, A.D.; Rousseau, W.F.; Walter, C.E.

    1993-05-01

    The President`s new economic initiatives include an energy tax that will affect the costs of power from most electric generating technologies. The tax on nuclear power could be applied in a number of different ways at several different points in the fuel cycle. These different approaches could have different effects on the generation costs and benefits of advanced reactors. The Office of Nuclear Energy has developed models for assessing the costs and benefits of advanced reactor cycles which must be updated to take into account the impacts of the proposed tax. This report has been prepared to assess the spectrum of impacts of the energy tax on nuclear power and can be used in updating the Office`s economic models. This study was conducted in the following steps. First, the most authoritative statement of the proposed tax available at this time was obtained. Then the impacts of the proposed tax on the costs of nuclear and fossil fueled generation were compared. Finally several other possible approaches to taxing nuclear energy were evaluated. The cost impact on several advanced nuclear technologies and a current light water technology were computed. Finally, the rationale for the energy tax as applied to various electric generating methods was examined.

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

    Office of Energy Efficiency and Renewable Energy (EERE) 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 ...

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

    DOE Patents [OSTI]

    Bowman, Charles D.

    1992-01-01

    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.

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

    DOE Patents [OSTI]

    Bowman, C.D.

    1992-11-03

    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.

  4. SAS Output

    Gasoline and Diesel Fuel Update (EIA)

    Generation by Energy Source: Independent Power Producers, 2004 - 2014 (Thousand ... Gas Nuclear Hydroelectric Conventional Solar Renewable Sources Excluding Hydroelectric ...

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

    SciTech Connect (OSTI)

    2005-03-01

    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.

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

    SciTech Connect (OSTI)

    Pete Jordan

    2010-09-01

    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.

  7. Grid-Connected Renewable Energy Generation Toolkit-Hydroelectric...

    Open Energy Info (EERE)

    United States Agency for International Development Sector: Energy Resource Type: Training materials Website: www.energytoolbox.orggcremod4index.shtml Grid-Connected...

  8. EERE Success Story-Hydropower Generators Will Deliver New Energy...

    Energy Savers [EERE]

    of the Cushman Hydroelectric Project for the first time since the dams were constructed in the late 1920s. ... for clean, domestic power generation from resources such as ...

  9. RESTRUCTURING RELAP5-3D FOR NEXT GENERATION NUCLEAR PLANT ANALYSIS

    SciTech Connect (OSTI)

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

    2006-06-01

    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.

  10. The SGR Multipurpose - Generation IV - Transportable Cogeneration Nuclear Reactor with Innovative Shielding

    SciTech Connect (OSTI)

    Pahladsingh, R.R.

    2002-07-01

    Deregulation and liberalization are changing the global energy-markets. At the same time innovative technologies are introduced in the electricity industry; often as a requirement from the upcoming Digital Society. Energy solutions for the future are more seen as a mix of energy-sources for generation-, transmission- and distribution energy-services. The Internet Energy-web based 'Virtual' enterprises are coming up and will gradually change our society. It the fast changing world we have to realize that there will be less time to look for the adequate solutions to anticipate on global developments and the way they will influence our own societies. Global population may reach 9 billion people by 2030; this will put tremendous pressure on energy-, water- and food supply in the global economy. It is time to think about some major issues as described below and come up with the right answers. These are needed on very short term to secure a humane global economic growth and the sustainable global environment. The DOE (Department of Energy - USA) has started the Generation IV initiative for the new generation of nuclear reactors that must lead to much better safety, economics and public acceptance the new reactors. The SGR (Simplified Gas-cooled Reactor) is being proposed as a Generation IV modular nuclear reactor, using graphite pebbles as fuel, whereby an attempt has been made to meet all the DOE requirements, to be used for future nuclear reactors. The focus in this paper is on the changing and emerging global energy-markets and shows some relevant criteria to the nuclear industry and how we can anticipate with improved and new designs towards the coming Digital Society. (author)

  11. Korea`s choice of a new generation of nuclear plants

    SciTech Connect (OSTI)

    Redding, J.R.

    1994-12-31

    The ABWR and SBWR design, both under development at GE, provide the best platform for developing the next generation advanced plants. The ABWR, which is rapidly setting the standard for new nuclear reactor plants, is clearly the best choice to meet the present energy needs of Korea. And through a GE/Korea partnership to develop the plant of the next century, Korea will establish itself as a leader in innovative reactor technology.

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

    SciTech Connect (OSTI)

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

    2011-09-01

    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.

  13. 1,"PSEG Salem Generating Station","Nuclear","PSEG Nuclear LLC",2366.6

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

    Jersey" ,"Plant","Primary energy source","Operating company","Net summer capacity (MW)" 1,"PSEG Salem Generating Station","Nuclear","PSEG Nuclear LLC",2366.6 2,"PSEG Linden Generating Station","Natural gas","PSEG Fossil LLC",1639.2 3,"Bergen Generating Station","Natural gas","PSEG Fossil LLC",1219 4,"PSEG Hope Creek Generating

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

    SciTech Connect (OSTI)

    Forsberg, Charles W; Gorensek, M. B.; Herring, S.; Pickard, P.

    2008-03-01

    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

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

    SciTech Connect (OSTI)

    Chas. T. Main, Inc.

    1982-03-01

    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.

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

    DOE Patents [OSTI]

    Ekeroth, Douglas E.; Corletti, Michael M.

    1993-01-01

    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.

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

    DOE Patents [OSTI]

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

    1993-11-16

    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.

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

    SciTech Connect (OSTI)

    Simos, N.

    2011-05-01

    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

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

    SciTech Connect (OSTI)

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

    2011-01-01

    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.

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

    SciTech Connect (OSTI)

    Brown, L.C.

    2002-11-01

    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

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

    SciTech Connect (OSTI)

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

    2004-10-03

    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.

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

    SciTech Connect (OSTI)

    Eipeldauer, Mary D

    2009-01-01

    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.

  3. Reynolds Creek Hydroelectric Project, Project Status

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

    Excellent School System November 17, 2009 ... South Fork (2.3 MW) Remainder of Generation is Diesel-fired November 17, 2009 6 Project ... Order TurbineGenerator - January 2010 ...

  4. Melting of the metallic wastes generated by dismantling retired nuclear research facilities

    SciTech Connect (OSTI)

    Chong-Hun Jung; Pyung-Seob Song; Byung-Youn Min; Wang-Kyu Choi

    2008-01-15

    The decommissioning of nuclear installations results in considerably large amounts of radioactive metallic wastes such as stainless steel, carbon steel, aluminum, copper etc. It is known that the reference 1,000 MWe PWR and 881 MWe PHWR will generate metal wastes of 24,800 ton and 26,500 ton, respectively. In Korea, the D and D of KRR-2 and a UCP at KAERI have been performed. The amount of metallic wastes from the KRR-1 and UCP was about 160 ton and 45 ton, respectively, up to now. These radioactive metallic wastes will induce problems of handling and storing these materials from environmental and economical aspects. For this reason, prompt countermeasures should be taken to deal with the metal wastes generated by dismantling retired nuclear facilities. The most interesting materials among the radioactive metal wastes are stainless steel (SUS), carbon steel (CS) and aluminum wastes because they are the largest portions of the metallic wastes generated by dismantling retired nuclear research facilities. As most of these steels are slightly contaminated, if they are properly treated they are able to be recycled and reused in the nuclear field. In general, the technology of a metal melting is regarded as one of the most effective methods to treat metallic wastes from nuclear facilities. In conclusion: The melting of metal wastes (Al, SUS, carbon steel) from a decommissioning of research reactor facilities was carried out with the use of a radioisotope such as cobalt and cesium in an electric arc furnace. In the aluminum melting tests, the cobalt was captured at up to 75% into the slag phase. Most of the cesium was completely eliminated from the aluminum ingot phase and moved into the slag and dust phases. In the melting of the stainless steel wastes, the {sup 60}Co could almost be retained uniformly in the ingot phase. However, we found that significant amounts of {sup 60}Co remained in the slag at up to 15%. However the removal of the cobalt from the ingot phase was

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

    SciTech Connect (OSTI)

    Soutworth, Finis; Gauthier, Jean-Claude; Lecomte, Michel; Carre, Franck

    2007-07-01

    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

  6. Idaho Nuclear Technology and Engineering Center Newly Generated Liquid Waste Demonstration Project Feasibility Study

    SciTech Connect (OSTI)

    Herbst, A.K.

    2000-02-01

    A research, development, and demonstration project for the grouting of newly generated liquid waste (NGLW) at the Idaho Nuclear Technology and Engineering Center is considered feasible. NGLW is expected from process equipment waste, decontamination waste, analytical laboratory waste, fuel storage basin waste water, and high-level liquid waste evaporator condensate. The potential grouted waste would be classed as mixed low-level waste, stabilized and immobilized to meet RCRA LDR disposal in a grouting process in the CPP-604 facility, and then transported to the state.

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

    SciTech Connect (OSTI)

    Ball, Sydney J

    2008-03-01

    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.

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

    SciTech Connect (OSTI)

    HDR Alaska, Inc.

    1998-11-01

    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.

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

    SciTech Connect (OSTI)

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

    2012-10-01

    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).

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

    SciTech Connect (OSTI)

    Mark Holbrook

    2007-09-01

    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.

  11. The Next Generation Nuclear Plant Graphite Creep Experiment Irradiation in the Advanced Test Reactor

    SciTech Connect (OSTI)

    Blaine Grover

    2010-10-01

    The United States Department of Energys 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 United States Department of Energys lead laboratory for nuclear energy development. The ATR is one of the worlds 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, including irradiation creep, at different temperatures and loading conditions to support design of the Next Generation Nuclear Plant (NGNP) Very High Temperature Gas Reactor, as well as other future gas reactors. The experiments will each consist of a single capsule that will contain six stacks of graphite specimens, with half of the graphite specimens in each stack 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 have differing compressive loads applied to the top half of each pair of specimen stacks, while a seventh stack will not have a compressive load. 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

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

    SciTech Connect (OSTI)

    Burchell, Timothy D; Bratton, Rob; Marsden, Barry; Srinivasan, Makuteswara; Penfield, Scott; Mitchell, Mark; Windes, Will

    2008-03-01

    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

  13. Next Generation Nuclear Plant Materials Research and Development Program Plan, Revision 4

    SciTech Connect (OSTI)

    G.O. Hayner; R.L. Bratton; R.E. Mizia; W.E. Windes; W.R. Corwin; T.D. Burchell; C.E. Duty; Y. Katoh; J.W. Klett; T.E. McGreevy; R.K. Nanstad; W. Ren; P.L. Rittenhouse; L.L. Snead; R.W. Swindeman; D.F. Wlson

    2007-09-01

    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 950°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, 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. Some of the general and administrative aspects of the R&D Plan include: • Expand American Society of Mechanical Engineers (ASME) Codes and American Society for Testing and Materials (ASTM) Standards in support of the NGNP Materials R&D Program. • Define and develop inspection needs and the procedures for those inspections. • Support selected university materials related R&D activities that would be of direct benefit to the NGNP Project. • Support international materials related collaboration activities through the DOE sponsored Generation IV International Forum (GIF) Materials and Components (M&C) Project Management Board (PMB). • Support document review activities through the Materials Review Committee (MRC) or other suitable forum.

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

    DOE Patents [OSTI]

    Tsiklauri, Georgi V.; Durst, Bruce M.

    1995-01-01

    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.

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

    DOE Patents [OSTI]

    Tsiklauri, Georgi V.; Durst, Bruce M.

    1996-01-01

    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.

  16. Xianggelila Xian Ge Ji Liu Yu Xia Zhi En Hydroelectric Development...

    Open Energy Info (EERE)

    Ge Ji Liu Yu Xia Zhi En Hydroelectric Development Ltd Jump to: navigation, search Name: Xianggelila Xian Ge Ji Liu Yu Xia Zhi En Hydroelectric Development Ltd Place: Xianggelila...

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

    SciTech Connect (OSTI)

    Hebdon, F.J.

    1993-03-01

    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.

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

    SciTech Connect (OSTI)

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

    2012-04-01

    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.

  19. Federal Register Notice EPAct 2005 Section 242 Hydroelectric Incentive Program: January 2015

    Broader source: Energy.gov [DOE]

    Federal Register Notice for the EPAct 2005 Section 242 Hydroelectric Incentive Program application period announcement: January, 2015.

  20. Threatened and Endangered Species Evaluation for Operating Commercial Nuclear Power Generating Plants

    SciTech Connect (OSTI)

    Sackschewsky, Michael R.

    2004-01-15

    The Endangered Species Act (ESA) of 1973 requires 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 (T&E) 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 Office of Nuclear Reactor Regulation (NRR) staff have performed appropriate assessments of potential impacts to threatened or endangered species, and consulted with appropriate agencies with regard to protection of such species in authorizing the construction, operation, and relicensing of nuclear power generating facilities. However, the assessments and consultations concerning many facilities were performed during the 1970's or early 1980's, and have not been re-evaluated in detail or updated since those initial evaluations. A review of potential Endangered Species Act issues at licensed nuclear power facilities was completed in 1997. In that review 484 different ESA-listed species were identified as potentially occurring near one or more of the 75 facility sites that were examined. An update of the previous T&E species evaluation at this time is desired because, during the intervening 6 years: nearly 200 species have been added to the ESA list, critical habitats have been designated for many of the listed species, and significantly more information is available online, allowing for more efficient high-level evaluations of potential species presence near sites and the potential operation impacts. The updated evaluation included searching the NRC's ADAMS database to find any documents related to T

  1. S ENERGY POLICY ACT OF 2005 SECTION 242 HYDROELECTRIC INCENTIVE PROGRAM

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

    S ENERGY POLICY ACT OF 2005 SECTION 242 HYDROELECTRIC INCENTIVE PROGRAM CALENDAR YEAR 2013 INCENTIVE PAYMENTS Payee (Applicant) Hydro Facility Albany Engineering Corporation (AEC) Mechanicville Hydroelectric Project Albany Engineering Corporation (AEC) Stuyvesant Falls Hydroelectric Project Barton (VT) Village, Inc., Electric Department Barton Hydro Bell Mountain Hydro LLC Bell Mountain Hydro Facility Bowersock Mills & Power Company Expanded Kansas River Hydropower Project-North Powerhouse

  2. EIS-0184: South Fork Tolt River Hydroelectric Project

    Broader source: Energy.gov [DOE]

    This EIS analyzes the Seattle City Light, a Department of the City of Seattle proposal to construct a hydroelectric project with an installed capacity of 15 MW on the South Fork Tolt River near the town of Carnation located in King County in the State of Washington.

  3. Design Option of Heat Exchanger for the Next Generation Nuclear Plant

    SciTech Connect (OSTI)

    Eung Soo Kim; Chang Oh

    2008-09-01

    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.

  4. Buildings Energy Data Book: 6.2 Electricity Generation, Transmission, and Distribution

    Buildings Energy Data Book [EERE]

    2010 Existing Capacity, by Energy Source (GW) Number of Generator Nameplate Net Summer Net Winter Plant Fuel Type Generators Capacity Capacity Capacity Coal Petroleum Natural Gas Other Gases Nuclear Hydroelectric Conventional Wind Solar Thermal and Photovoltaic Wood and Wood Derived Fuels Geothermal Other Biomass Pumped Storage Other Total Source(s): EIA, Electric Power Annual 2010, Feb. 2012, Table 1.2. 51 1.0 0.9 0.9 18,150 1,138.6 1,039.1 1,078.7 1,574 5.0 4.4 4.4 151 20.5 22.2 22.1 346 7.9

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

    SciTech Connect (OSTI)

    J. K. Wright; R. N. Wright

    2010-07-01

    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.

  6. MeV Summer School prepares next-generation nuclear scientists...

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

    Summer School is an annual 10-day program that provides early-career nuclear engineers with advanced studies in modeling, experimentation and validation of nuclear reactor design. ...

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

    SciTech Connect (OSTI)

    Ian McKirdy

    2011-07-01

    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.

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

    SciTech Connect (OSTI)

    Petti, Jason P.

    2007-01-01

    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.

  9. Hydroelectric power in Hawaii: a reconnaissance survey

    SciTech Connect (OSTI)

    1981-02-01

    The major conclusion of this study is that hydropower resources in the State of Hawaii are substantial, and they offer the potential for major increases in hydropower generating capacity. Hydropower resources on all islands total about 50 megawatts of potential generating capacity. Combined with the 18 megawatts of existing hydropower capacity, hydropower resources potentially could generate about 307 million kilowatt-hours of electric energy annually. This represents about 28% of the present combined electricity needs of the Neighbor Islands - Kauai, Molokai, Maui, and the Big Island. Hydropower resources on Kauai equal 72% of that island's electricity needs; on Molokai, 40%; on the Big Island, 20%; and on Maui, 18%. The island of Oahu, however, has only small hydropower resources, and could only generate a negligible portion of its electricity needs from this energy source. Existing and future (potential) hydropower capacities are summarized, and annual outputs for each island are estimated. Future hydropower facilities are subdivided into two categories, which show how much of the potential capacity is being actively considered for development, and how much is only tentatively proposed at the time.

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

    SciTech Connect (OSTI)

    L.E. Demick

    2010-09-01

    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.

  11. A Study of United States Hydroelectric Plant Ownership

    SciTech Connect (OSTI)

    Hall, Douglas G.; Reeves, Kelly S.

    2006-06-01

    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.

  12. DOE Office of Indian Energy Foundational Course: Hydroelectric

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

    Foundational Courses Renewable Energy Technologies 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

  13. Kootznoowoos Thayer Lake Hydroelectric Update

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

    November 16, 2011 Tribal Energy Program The Project - Run of River Project - 200 ft of head - 6 miles North - 1000 kilowatt - 8 miles of road - Underwater crossing Angoon - Angoon and its people - from Time immemorial - Only year round community in Wilderness and National Monument - USDA is the land manager - 400 residents with potential to grow - Current spot demand of 600 kW - Commercial Rate unsubsidized $.60 plus kWh - Centrally located in Panhandle & Tongass - Considerable hydroelectric

  14. High Energy Utilization, Co-Generation Nuclear power Plants With Static Energy Conversion

    SciTech Connect (OSTI)

    El-Genk, Mohamed S.; Tournier, Jean-Michel P.

    2002-07-01

    In addition to being cost effective, very small nuclear power plants with static energy conversion could meet the needs and the energy mix in underdeveloped countries and remote communities, which may include electricity, residential and industrial space heating, seawater desalination, and/or high temperature process heat or steam for industrial uses. These plants are also an attractive option in naval, marine, and undersea applications, when the absence of a sound signature is highly desirable. An Analysis is performed of Gas Cooled Reactor (CGR) and Liquid Metal Cooled Reactor (LMR), very small nuclear power plants with static energy conversion, using a combination of options. These include Alkali Metal Thermal-to-Electric Converters (AMTECs) and both single segment and segmented thermoelectric converters. The total energy utilization of these plants exceeds 88%. It includes the fraction of the reactor's thermal power converted into electricity and delivered to the Grid at 6.6 kVA and those used for residential and industrial space heating at {approx}370 K, seawater desalination at 400 K, and/or high temperature process heat or steam at {approx}850 K. In addition to its inherently high reliability, modularity, low maintenance and redundancy, static energy conversion used in the present study could deliver electricity to the Grid at a net efficiency of 29.5%. A LMR plant delivers 2-3 times the fraction of the reactor thermal power converted into electricity in a GCR plant, but could not provide for both seawater desalination and high temperature process heat/steam concurrently, which is possible in GCR plants. The fraction of the reactor's thermal power used for non-electrical power generation in a GCR plant is {approx} 10 - 15% higher than in a LMR plant. (authors)

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

    SciTech Connect (OSTI)

    Sackschewsky, M.R.

    1997-03-01

    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.

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

    SciTech Connect (OSTI)

    J. K. Wright; R. N. Wright

    2008-04-01

    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

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

    SciTech Connect (OSTI)

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

    2007-03-21

    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

  18. US Central Station Nuclear Electric Generating Units: significant milestones. (Status as of April 1, 1980)

    SciTech Connect (OSTI)

    Not Available

    1980-06-01

    Construction and operational milestones are tabulated for US nuclear power plants. Data are presented on nuclear steam supply system orders. A schedule of commercial operation through 1990 is given.

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

    Office of Energy Efficiency and Renewable Energy (EERE)

    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...

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

    SciTech Connect (OSTI)

    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

    2008-09-01

    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.

  1. The effect of availability improvement of a nuclear power plant on the cost of generating electricity

    SciTech Connect (OSTI)

    Nejat, S.M.R.

    1980-01-01

    The objective of this investigation is to study the economic benefits in operating a nuclear power plant as a result of improving the availabilitty of the secondary (steam) loop of the plant. A new method has been developed to obtain availability, frequency of failure, probability and frequency of operation, cycle time, and uptime for different capacity states of a parallel-series system having components with failure and repair rates distributed exponentially. The method has been applied to different subsystems, systems, and the seconary loop as a whole. The effect of having spare parts for several components, as measured by savings in the generation of electricity, is also studied. The Kettelle algorithm was applied to determine optimal spare part allocation in order to achieve maximum availability or minimum cost of electricity, subject to a fixed spare parts budget. It has been shown that the optimum spare parts allocation and the budget level which gives optimum availability, do not necessarily give minimum electricity cost. The savings per year for optimal spare parts allocation and different spare parts budgets were obtained. The results show that the utilty will save its customers a large amount of money if spare parts are purchased, especially at the beginning of the plant operation, and are allocated judiciously.

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

    SciTech Connect (OSTI)

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

    1993-10-01

    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.

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

    SciTech Connect (OSTI)

    J. K. Wright

    2008-04-01

    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

  4. 1,"Robert Moses Niagara","Hydroelectric","New York Power Authority",2438.8

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

    York" ,"Plant","Primary energy source","Operating company","Net summer capacity (MW)" 1,"Robert Moses Niagara","Hydroelectric","New York Power Authority",2438.8 2,"Ravenswood","Natural gas","TC Ravenswood LLC",2216.5 3,"Nine Mile Point Nuclear Station","Nuclear","Nine Mile Point Nuclear Sta LLC",1937 4,"Oswego Harbor

  5. Generation | Department of Energy

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

    Generation Generation Southeastern’s Power Operations employees perform the tasks of declaring, scheduling, dispatching, and accounting for capacity and energy generated at the 22 hydroelectric projects in the agency’s 11-state marketing area. Southeastern has Certified System Operators, meeting the criteria set forth by the North American Electric Reliability Corporation. Southeastern's Power Operations employees perform the tasks of declaring, scheduling, dispatching, and accounting

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

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

    Foundational Courses Renewable Energy Technologies: 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

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

    SciTech Connect (OSTI)

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

    2007-04-05

    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

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

    SciTech Connect (OSTI)

    Todd R. Allen

    2009-06-30

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

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

    SciTech Connect (OSTI)

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

    2013-07-15

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

  10. The Next Generation Nuclear Plant - Insights Gained from the INEEL Point Design Studies

    SciTech Connect (OSTI)

    Philip E. MacDonald; A. M. Baxter; P. D. Bayless; J. M. Bolin; H. D. Gougar; R. L. Moore; A. M. Ougouag; M. B. Richards; R. L. Sant; J. W. Sterbentz; W. K. Terry

    2004-08-01

    This paper provides the results of an assessment of two possible versions of the Next Generation Nuclear Plant (NGNP), a prismatic fuel type helium gas-cooled reactor and a pebble-bed fuel helium gas reactor. Insights gained regarding the strengths and weaknesses of the two designs are also discussed. Both designs will meet the three basic requirements that have been set for the NGNP: a coolant outlet temperature of 1000 C, passive safety, and a total power output consistent with that expected for commercial high-temperature gas-cooled reactors. Two major modifications of the current Gas Turbine- Modular Helium Reactor (GT-MHR) design were needed to obtain a prismatic block design with a 1000 C outlet temperature: reducing the bypass flow and better controlling the inlet coolant flow distribution to the core. The total power that could be obtained for different core heights without exceeding a peak transient fuel temperature of 1600 C during a high or low-pressure conduction cooldown event was calculated. With a coolant inlet temperature of 490 C and 10% nominal core bypass flow, it is estimated that the peak power for a 10-block high core is 686 MWt, for a 12-block high core is 786 MWt, and for a 14-block core is about 889 MWt. The core neutronics calculations showed that the NGNP will exhibit strongly negative Doppler and isothermal temperature coefficients of reactivity over the burnup cycle. In the event of rapid loss of the helium gas, there is negligible core reactivity change. However, water or steam ingress into the core coolant channels can produce a relatively large reactivity effect. Two versions of an annular pebble-bed NGNP have also been developed, a 300 and a 600 MWt module. From this work we learned how to design passively safe pebble bed reactors that produce more than 600 MWt. We also found a way to improve both the fuel utilization and safety by modifying the pebble design (by adjusting the fuel zone radius in the pebble to optimize the fuel