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Sample records for nuclear capacity generated

  1. EIA - Electricity Generating Capacity

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

    Electricity Generating Capacity Release Date: January 3, 2013 | Next Release: August 2013 Year Existing Units by Energy Source Unit Additions Unit Retirements 2011 XLS XLS XLS 2010 XLS XLS XLS 2009 XLS XLS XLS 2008 XLS XLS XLS 2007 XLS XLS XLS 2006 XLS XLS XLS 2005 XLS XLS XLS 2004 XLS XLS XLS 2003 XLS XLS XLS Source: Form EIA-860, "Annual Electric Generator Report." Related links Electric Power Monthly Electric Power Annual Form EIA-860 Source Data

  2. 1,"Braidwood Generation Station","Nuclear","Exelon Nuclear",2330

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

    Illinois" ,"Plant","Primary energy source","Operating company","Net summer capacity (MW)" 1,"Braidwood Generation Station","Nuclear","Exelon Nuclear",2330 2,"Byron Generating ...

  3. U.S. Nuclear Generation of Electricity

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

    U.S. Nuclear Generation and Generating Capacity Data Released: May 26, 2016 Data for: ... 2004 XLS 2003 XLS P Preliminary U.S. Nuclear Generation: 1957 to latest available EIA ...

  4. World nuclear capacity and fuel cycle requirements, November 1993

    SciTech Connect (OSTI)

    Not Available

    1993-11-30

    This analysis report presents the current status and projections of nuclear capacity, generation, and fuel cycle requirements for all countries in the world using nuclear power to generate electricity for commercial use. Long-term projections of US nuclear capacity, generation, fuel cycle requirements, and spent fuel discharges for three different scenarios through 2030 are provided in support of the Department of Energy`s activities pertaining to the Nuclear Waste Policy Act of 1982 (as amended in 1987). The projections of uranium requirements also support the Energy Information Administration`s annual report, Domestic Uranium Mining and Milling Industry: Viability Assessment.

  5. Economic Dispatch of Electric Generation Capacity | Department...

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

    Economic Dispatch of Electric Generation Capacity A report to congress and the states pursuant to sections 1234 and 1832 of the Energy Polict Act of 2005. PDF icon Economic ...

  6. INVESTING IN NEW BASE LOAD GENERATING CAPACITY

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

    INVESTING IN NEW BASE LOAD GENERATING CAPACITY Paul L. Joskow April 8, 2008 The views expressed here are my own. They do not reflect the views of the Alfred P. Sloan Foundation, MIT or any other organization with which I am affiliated. THE 25-YEAR VIEW * Significant investment in base-load generating capacity is required over the next 25 years to balance supply and demand efficiently - ~ 200 to 250 Gw (Gross) - Depends on retirements of older steam and peaking units - Depends on demand growth *

  7. Doubling Geothermal Generation Capacity by 2020: A Strategic...

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

    Doubling Geothermal Generation Capacity by 2020: A Strategic Analysis Doubling Geothermal Generation Capacity by 2020: A Strategic Analysis PDF icon NREL Doubling Geothermal ...

  8. 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.

  9. California Nuclear Profile - San Onofre Nuclear Generating Station

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

    San Onofre Nuclear Generating Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration date" 2,"1,070","6,989",74.6,"PWR","application/vnd.ms-excel","application/vnd.ms-excel"

  10. Table 2. Ten largest plants by generation capacity, 2014

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

    Tennessee" ,"Plant","Primary energy source","Operating company","Net summer capacity (MW)" 1,"Cumberland (TN)","Coal","Tennessee Valley Authority",2470 2,"Sequoyah","Nuclear","Tenn...

  11. *NEW!* Doubling Geothermal Generation Capacity by 2020: A Strategic

    Energy Savers [EERE]

    Analysis | Department of Energy *NEW!* Doubling Geothermal Generation Capacity by 2020: A Strategic Analysis *NEW!* Doubling Geothermal Generation Capacity by 2020: A Strategic Analysis PDF icon NREL Doubling Geothermal Capacity.pdf More Documents & Publications Geothermal Exploration Policy Mechanisms Offshore Wind Jobs and Economic Development Impacts in the United States: Four Regional Scenarios track 1: systems analysis | geothermal 2015 peer review

  12. Doubling Geothermal Generation Capacity by 2020: A Strategic Analysis |

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

    Department of Energy Doubling Geothermal Generation Capacity by 2020: A Strategic Analysis Doubling Geothermal Generation Capacity by 2020: A Strategic Analysis PDF icon NREL Doubling Geothermal Capacity.pdf More Documents & Publications Geothermal Exploration Policy Mechanisms Offshore Wind Jobs and Economic Development Impacts in the United States: Four Regional Scenarios track 1: systems analysis | geothermal 2015 peer review

  13. 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.

  14. Biomass Power Generation Market Capacity is Estimated to Reach...

    Open Energy Info (EERE)

    Biomass Power Generation Market Capacity is Estimated to Reach 122,331.6 MW by 2022 Home > Groups > Renewable Energy RFPs Wayne31jan's picture Submitted by Wayne31jan(150)...

  15. Table 2. Ten largest plants by generation capacity, 2014

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

    Delaware" ,"Plant","Primary energy source","Operating company","Net summer capacity (MW)" 1,"Hay Road","Natural gas","Calpine Mid-Atlantic Generation LLC",1136 2,"Edge ...

  16. Table 2. Ten largest plants by generation capacity, 2014

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

    Alaska" ,"Plant","Primary energy source","Operating company","Net summer capacity (MW)" 1,"Beluga","Natural gas","Chugach Electric Assn Inc",344.4 2,"George M Sullivan Generation ...

  17. PUCT Substantive Rule 25.91 Generating Capacity Reports | Open...

    Open Energy Info (EERE)

    PUCT Substantive Rule 25.91 Generating Capacity Reports Jump to: navigation, search OpenEI Reference LibraryAdd to library Legal Document- RegulationRegulation: PUCT Substantive...

  18. 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)

  19. Methodologies for estimating one-time hazardous waste generation for capacity generation for capacity assurance planning

    SciTech Connect (OSTI)

    Tonn, B.; Hwang, Ho-Ling; Elliot, S.; Peretz, J.; Bohm, R.; Hendrucko, B.

    1994-04-01

    This report contains descriptions of methodologies to be used to estimate the one-time generation of hazardous waste associated with five different types of remediation programs: Superfund sites, RCRA Corrective Actions, Federal Facilities, Underground Storage Tanks, and State and Private Programs. Estimates of the amount of hazardous wastes generated from these sources to be shipped off-site to commercial hazardous waste treatment and disposal facilities will be made on a state by state basis for the years 1993, 1999, and 2013. In most cases, estimates will be made for the intervening years, also.

  20. 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"

  1. 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"

  2. 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.

  3. Monthly/Annual Energy Review - nuclear section

    Reports and Publications (EIA)

    2015-01-01

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

  4. THE BIRTH OF NUCLEAR-GENERATED ELECTRICITY

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

    BIRTH OF NUCLEAR-GENERATED ELECTRICITY The first time that electricity was generated from nuclear energy occurred in an experimental breeder reactor in Idaho in 1951. The idea for a breeder reactor (a reactor that could produce more fuel than it uses) first occurred to scientists working on the nation's wartime atomic energy program in the early 1940's. Experimental evidence indicated that the breeding of nuclear fuel was possible in a properly designed reactor, but time and resources were not

  5. Table 2. Ten largest plants by generation capacity, 2014

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

    Washington" ,"Plant","Primary energy source","Operating company","Net summer capacity (MW)" 1,"Grand Coulee","Hydroelectric","U S Bureau of Reclamation",7079 2,"Chief ...

  6. Table 2. Ten largest plants by generation capacity, 2014

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

    Colorado" ,"Plant","Primary energy source","Operating company","Net summer capacity (MW)" 1,"Comanche (CO)","Coal","Public Service Co of Colorado",1410 2,"Craig ...

  7. Table 2. Ten largest plants by generation capacity, 2014

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

    Utah" ,"Plant","Primary energy source","Operating company","Net summer capacity (MW)" 1,"Intermountain Power Project","Coal","Los Angeles Department of Water & Power",1800 ...

  8. Table 2. Ten largest plants by generation capacity, 2014

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

    Virginia" ,"Plant","Primary energy source","Operating company","Net summer capacity (MW)" 1,"Bath County","Pumped storage","Virginia Electric & Power Co",3003 2,"North ...

  9. Table 2. Ten largest plants by generation capacity, 2014

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

    Oklahoma" ,"Plant","Primary energy source","Operating company","Net summer capacity (MW)" 1,"Northeastern","Coal","Public Service Co of Oklahoma",1830 2,"Redbud Power ...

  10. Table 2. Ten largest plants by generation capacity, 2014

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

    United States" ,"Plant","Primary energy source","Operating company","Net summer capacity (MW)" 1,"Grand Coulee","Hydroelectric","U S Bureau of Reclamation",7079 2,"Palo ...

  11. Table 2. Ten largest plants by generation capacity, 2014

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

    Idaho" ,"Plant","Primary energy source","Operating company","Net summer capacity (MW)" 1,"Brownlee","Hydroelectric","Idaho Power Co",744 2,"Dworshak","Hydroelectric","USACE ...

  12. Tennessee Nuclear Profile - Power Plants

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

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

  13. Texas Nuclear Profile - Power Plants

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

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

  14. 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"

  15. 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"

  16. 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 date" 2,"1,097","9,241",96.2,"BWR","application/vnd.ms-excel","application/vnd.ms-excel" ,"1,097","9,241",96.2

  17. Table 2. Ten largest plants by generation capacity, 2014

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

    Louisiana" ,"Plant","Primary energy source","Operating company","Net summer capacity (MW)" 1,"Nine Mile Point","Natural gas","Entergy Louisiana LLC",2083.3 2,"Willow Glen","Natural ...

  18. Table 2. Ten largest plants by generation capacity, 2014

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

    District of Columbia" ,"Plant","Primary energy source","Operating company","Net summer capacity (MW)" 1,"US GSA Heating and Transmission","Natural gas","US GSA Heating and ...

  19. Table 2. Ten largest plants by generation capacity, 2014

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

    California" ,"Plant","Primary energy source","Operating company","Net summer capacity (MW)" 1,"Dynegy Moss Landing Power Plant","Natural gas","Dynegy -Moss Landing LLC",2529 ...

  20. Nuclear Energy Readiness Indicator Index (NERI): A benchmarking tool for assessing nuclear capacity in developing countries

    SciTech Connect (OSTI)

    Saum-Manning,L.

    2008-07-13

    Declining natural resources, rising oil prices, looming climate change and the introduction of nuclear energy partnerships, such as GNEP, have reinvigorated global interest in nuclear energy. The convergence of such issues has prompted countries to move ahead quickly to deal with the challenges that lie ahead. However, developing countries, in particular, often lack the domestic infrastructure and public support needed to implement a nuclear energy program in a safe, secure, and nonproliferation-conscious environment. How might countries become ready for nuclear energy? What is needed is a framework for assessing a country's readiness for nuclear energy. This paper suggests that a Nuclear Energy Readiness Indicator (NERI) Index might serve as a meaningful basis for assessing a country's status in terms of progress toward nuclear energy utilization under appropriate conditions. The NERI Index is a benchmarking tool that measures a country's level of 'readiness' for nonproliferation-conscious nuclear energy development. NERI first identifies 8 key indicators that have been recognized by the International Atomic Energy Agency as key nonproliferation and security milestones to achieve prior to establishing a nuclear energy program. It then measures a country's progress in each of these areas on a 1-5 point scale. In doing so NERI illuminates gaps or underdeveloped areas in a country's nuclear infrastructure with a view to enable stakeholders to prioritize the allocation of resources toward programs and policies supporting international nonproliferation goals through responsible nuclear energy development. On a preliminary basis, the indicators selected include: (1) demonstrated need; (2) expressed political support; (3) participation in nonproliferation and nuclear security treaties, international terrorism conventions, and export and border control arrangements; (4) national nuclear-related legal and regulatory mechanisms; (5) nuclear infrastructure; (6) the utilization of IAEA technical assistance; (7) participation in regional arrangements; and (8) public support for nuclear power. In this paper, the Index aggregates the indicators and evaluates and compares the level of readiness in seven countries that have recently expressed various degrees of interest in establishing a nuclear energy program. The NERI Index could be a valuable tool to be utilized by: (1) country officials who are considering nuclear power; (2) the international community, desiring reassurance of a country's capacity for the peaceful, safe, and secure use of nuclear energy; (3) foreign governments/NGO's, seeking to prioritize and direct resources toward developing countries; and (4) private stakeholders interested in nuclear infrastructure investment opportunities.

  1. Industry Participation Sought for Design of Next Generation Nuclear...

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

    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 ...

  2. Table 2. Ten largest plants by generation capacity, 2014

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

    Sandy","Coal","Kentucky Power Co",1060 9,"Riverside Generating LLC","Natural gas","Riverside Generating Co LLC",825 10,"J K Smith","Natural gas","East Kentucky Power Coop, Inc",784

  3. Capacity Value of PV and Wind Generation in the NV Energy System

    SciTech Connect (OSTI)

    Lu, Shuai; Diao, Ruisheng; Samaan, Nader A.; Etingov, Pavel V.

    2014-03-21

    Calculation of photovoltaic (PV) and wind power capacity values is important for estimating additional load that can be served by new PV or wind installations in the electrical power system. It also is the basis for assigning capacity credit payments in systems with markets. Because of variability in solar and wind resources, PV and wind generation contribute to power system resource adequacy differently from conventional generation. Many different approaches to calculating PV and wind generation capacity values have been used by utilities and transmission operators. Using the NV Energy system as a study case, this report applies peak-period capacity factor (PPCF) and effective load carrying capability (ELCC) methods to calculate capacity values for renewable energy sources. We show the connection between the PPCF and ELCC methods in the process of deriving a simplified approach that approximates the ELCC method. This simplified approach does not require generation fleet data and provides the theoretical basis for a quick check on capacity value results of PV and wind generation. The diminishing return of capacity benefit as renewable generation increases is conveniently explained using the simplified capacity value approach.

  4. Y-12 builds capacity to meet nuclear testing schedule - Or: ...

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

    demands of the nuclear testing program of the 1950's through September 23, 1992, required Y-12 management to purchase and install a huge amount of specialized machinery. It was...

  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. Tennessee Nuclear Profile - Watts Bar Nuclear Plant

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

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

  7. 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

  8. 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.

  9. 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"

  10. 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"

  11. NNSA Next Generation Safeguards Initiative | National Nuclear...

    National Nuclear Security Administration (NNSA)

    Administered by the International Atomic Energy Agency (IAEA), international safeguards serve to monitor nuclear activities under the Non-Proliferation Treaty (NPT) and are the ...

  12. 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

  13. 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.

  14. Method and apparatus for generating low energy nuclear particles (Patent) |

    Office of Scientific and Technical Information (OSTI)

    SciTech Connect Patent: Method and apparatus for generating low energy nuclear particles Citation Details In-Document Search Title: Method and apparatus for generating low energy nuclear particles × You are accessing a document from the Department of Energy's (DOE) SciTech Connect. This site is a product of DOE's Office of Scientific and Technical Information (OSTI) and is provided as a public service. Visit OSTI to utilize additional information resources in energy science and technology.

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

    Energy Savers [EERE]

    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"

  16. 1,"PSEG Salem Generating Station","Nuclear","PSEG Nuclear LLC...

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

    Cogen Plant","Natural gas","EFS Cogen Holdings I LLC",912.2 6,"Red Oak Power LLC","Natural gas","Red Oak Operating Services LLC",765.9 7,"PSEG Mercer Generating ...

  17. 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

  18. Nuclear reactor characteristics and operational history

    Gasoline and Diesel Fuel Update (EIA)

    Table 1. Nuclear Reactor, State, Type, Net Capacity, Generation, and Capacity Factor PDF ... MWh2 Capacity Factor Percent3 Arkansas Nuclear One 1 AR PWR 842 6,607,090 90 Arkansas ...

  19. 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.

  20. Method and apparatus for generating low energy nuclear particles

    DOE Patents [OSTI]

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

    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.

  1. 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.

  2. 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.

  3. 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 proliferation), the worldwide community is working to develop and deploy new nuclear energy systems and advanced fuel cycles. These new nuclear systems address the key challenges and include: (1) extracting the full energy value of the nuclear fuel; (2) creating waste solutions with improved long term safety; (3) minimizing the potential for the misuse of the technology and materials for weapons; (4) continually improving the safety of nuclear energy systems; and (5) keeping the cost of energy affordable.

  4. 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.

  5. How and why Tampa Electric Company selected IGCC for its next generating capacity addition

    SciTech Connect (OSTI)

    Pless, D.E. )

    1992-01-01

    As the title indicates, the purpose of this paper is to relate how and why Tampa Electric Company decided to select the Integrated Gasification Combined Cycle (IGCC) for their next capacity addition at Polk Power Station, Polk Unit No. 1. For a complete understanding of this process, it is necessary to review the history related to the initial formulation of the IGCC concept as it was proposed to the Department of Energy (DOE) Clean Coal Initiative Round Three. Further, it is important to understand the relationship between Tampa Electric Company and TECO Pay Services Corporation (TPS). TECO Energy, Inc. is an energy related holding company with headquarters in Tampa, Florida. Tampa Electric Company is the principal, wholly-owned subsidiary of TECO Energy, Inc. Tampa Electric Company is an investor-owned electric utility with about 3200 MW of generation capacity of which 97% is coal fired. Tampa Electric Company serves about 2,000 square miles and approximately 470,000 customers, in west central Florida, primarily in and around Hillsborough County and Tampa, Florida. Tampa Electric Company generating units consist of coal fired units ranging in size from a 110 MW coal fired cyclone unit installed in 1957 to a 450 MW pulverized coal unit with wet limestone flue gas desulfurization installed in 1985. In addition, Tampa Electric Company has six (6) No. 6 oil fired steam units totaling approximately 220 MW. Five (5) of these units, located at the Hookers Point Station, were installed in the late 1940's and early 1950's. Tampa Electric also has about 150 MW of No. 2 oil fired start-up and peaking combustion turbines. The company also owns a 1966 vintage 12 MW natural gas fired steam plant (Dinner Lake) and two nO. 6 oil fired diesel units with heat recovery equipment built in 1983 (Phillips Plant).

  6. 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.

  7. 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.

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

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

    conditions U.S. DEPARTMENT OF ENERGY IDAHO FALLS, IDAHO, 83403 For Immediate Release: Sept. 25, 2013 Media Contacts: Teri Ehresman, 208-526-7785 teri.ehresman@inl.gov Bill Cabage (ORNL), 865-574-4399, cabagewh@ornl.gov 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 U.S. Department of Energy's Idaho National Laboratory (INL) and Oak Ridge National Laboratory

  9. 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.

  10. EIA - State Nuclear Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Minnesota Nuclear Profile 2010 Minnesota profile Minnesota total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer ...

  11. 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 States repository development, such as seal system design, coupled process simulation, and application of performance assessment methodology, helps define a clear strategy for a heat-generating nuclear waste repository in salt.

  12. Proposed changes to generating capacity 1980-1989 for the contiguous United States: as projected by the Regional Electric Reliability Councils in their April 1, 1980 long-range coordinated planning reports to the Department of Energy

    SciTech Connect (OSTI)

    1980-12-01

    The changes in generating capacity projected for 1980 to 1989 are summarized. Tabulated data provide summaries to the information on projected generating unit construction, retirements, and changes, in several different categories and groupings. The new generating units to be completed by the end of 1989 total 699, representing 259,490 megawatts. This total includes 10 wind power and one fuel cell installations totaling 48.5 MW to be completed by the end of 1989. There are 321 units totaling 13,222 MW to be retired. There are capacity changes due to upratings and deratings. Summary data are presented for: total requirement for electric energy generation for 1985; hydroelectric energy production for 1985; nuclear energy production for 1985; geothermal and other energy production for 1985; approximate non-fossil generation for 1985; range of fossil energy requirements for 1985; actual fossil energy sources 1974 to 1979; estimated range of fossil fuel requirements for 1985; coal capacity available in 1985; and computation of fuel use in 1985. Power plant capacity factors are presented. Extensive data on proposed generating capacity changes by individual units in the 9 Regional Electric Reliability Councils are presented.

  13. Advanced Nuclear Energy Projects | Department of Energy

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

    Projects Advanced Nuclear Energy Projects Advanced Nuclear Energy Projects Advanced Nuclear Energy Projects Advanced Nuclear Energy Projects Advanced Nuclear Energy Projects ADVANCED NUCLEAR ENERGY 1 PROJECT in 1 LOCATION 2,200 MW GENERATION CAPACITY 17,200,000 MWh PROJECTED ANNUAL GENERATION * 10,000,000 METRIC TONS OF CO2 EMISSIONS PREVENTED ANNUALLY ALL FIGURES AS OF MARCH 2015 * Calculated using the project's and NREL Technology specific capacity factors. For cases in which NREL's capacity

  14. 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 –

  15. A system dynamic modeling approach for evaluating municipal solid waste generation, landfill capacity and related cost management issues

    SciTech Connect (OSTI)

    Kollikkathara, Naushad; Feng Huan; Yu Danlin

    2010-11-15

    As planning for sustainable municipal solid waste management has to address several inter-connected issues such as landfill capacity, environmental impacts and financial expenditure, it becomes increasingly necessary to understand the dynamic nature of their interactions. A system dynamics approach designed here attempts to address some of these issues by fitting a model framework for Newark urban region in the US, and running a forecast simulation. The dynamic system developed in this study incorporates the complexity of the waste generation and management process to some extent which is achieved through a combination of simpler sub-processes that are linked together to form a whole. The impact of decision options on the generation of waste in the city, on the remaining landfill capacity of the state, and on the economic cost or benefit actualized by different waste processing options are explored through this approach, providing valuable insights into the urban waste-management process.

  16. 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 fuels has trace contaminants (primarily carbon monoxide) that are detrimental to precious metal catalyzed fuel cells, as is now recognized by many of the world's largest automobile companies. Thermochemical hydrogen will not contain carbon monoxide as an impurity at any level. Electrolysis, the alternative process for producing hydrogen using nuclear energy, suffers from thermodynamic inefficiencies in both the production of electricity and in electrolytic parts of the process. The efficiency of electrolysis (electricity to hydrogen) is currently about 80%. Electric power generation efficiency would have to exceed 65% (thermal to electrical) for the combined efficiency to exceed the 52% (thermal to hydrogen) calculated for one thermochemical cycle. Thermochemical water-splitting cycles have been studied, at various levels of effort, for the past 35 years. They were extensively studied in the late 70s and early 80s but have received little attention in the past 10 years, particularly in the U.S. While there is no question about the technical feasibility and the potential for high efficiency, cycles with proven low cost and high efficiency have yet to be developed commercially. Over 100 cycles have been proposed, but substantial research has been executed on only a few. This report describes work accomplished during a three-year project whose objective is to ''define an economically feasible concept for production of hydrogen, by nuclear means, using an advanced high temperature nuclear reactor as the energy source.'' The emphasis of the first phase was to evaluate thermochemical processes which offer the potential for efficient, cost-effective, large-scale production of hydrogen from water in which the primary energy input is high temperature heat from an advanced nuclear reactor and to select one (or, at most three) for further detailed consideration. During Phase 1, an exhaustive literature search was performed to locate all cycles previously proposed. The cycles located were screened using objective criteria to determine which could benefit, in terms of efficiency and cost, from the high-temperature capabilities of advanced nuclear reactors. The more promising cycles were then analyzed in depth as to their adaptability to advanced high-temperature nuclear reactors. As a result, the Sulfur-Iodine (S-I) cycle was selected for integration into the advanced nuclear reactor system. In Phases 2 and 3, alternative flowsheets were developed and compared. This effort entailed a considerable effort into developing the solution thermodynamics pertinent to the S-I cycle.

  17. 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

  18. 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.

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

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

    Department of Energy DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant DOE, NRC Issue Licensing Roadmap For Next-Generation Nuclear Plant August 15, 2008 - 3:15pm Addthis WASHINGTON, DC -The U.S. Department of Energy (DOE) and the U.S. Nuclear Regulatory Commission (NRC) today delivered to Congress the Next Generation Nuclear Plant (NGNP) Licensing Strategy Report which describes the licensing approach, the analytical tools, the research and development activities and the

  20. 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.

  1. 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

  2. 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.

  3. 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.

  4. 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.

  5. 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.

  6. 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.

  7. 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.

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

    Energy Savers [EERE]

    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

  9. 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 managing the R&D program elements; (2) Developing a specific work package for the R&D activities to be performed during each government fiscal year; (3) Reporting the status and progress of the work based on committed deliverables and milestones; (4) Developing collaboration in areas of materials R&D of benefit to the NGNP with countries that are a part of the Generation IV International Forum; and (5) Ensuring that the R&D work performed in support of the materials program is in conformance with established Quality Assurance and procurement requirements. The objective of the NGNP Materials R&D Program is to provide the essential materials R&D needed to support the design and licensing of the reactor and balance of plant, excluding the hydrogen plant. The materials R&D program is being initiated prior to the design effort to ensure that materials R&D activities are initiated early enough to support the design process and support the Project Integrator. The thermal, environmental, and service life conditions of the NGNP will make selection and qualification of some high-temperature materials a significant challenge; thus, new materials and approaches may be required.

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

    Energy Savers [EERE]

    Department of Energy to NEAC to Review the Next Generation Nuclear Plant Activities Letter to NEAC to Review the Next Generation Nuclear Plant Activities The Next Generation Nuclear Plant (NGNP) project was established under the Energy Policy Act in August 2005 (EPACT-2005). EPACT-2005 defined an overall plan and timetable for NGNP research, design, licensing, construction and operation by the end of FY 2021. At the time that EPACT-2005 was passed, it was envisioned that key aspects of the

  11. 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

  12. 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 in Section 4. The DOE-funded hydrogen production [DOE 2004] and energy conversion technologies programs are described elsewhere.

  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 -- 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.

  15. 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.

  16. 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 ...

  17. State Nuclear Profiles 2010

    Gasoline and Diesel Fuel Update (EIA)

    Primary energy source Summer capacity (mw) Share of State total (percent) Net generation ... Station Unit 1, Unit 2 2,330 19,200 20.0 Exelon Nuclear Byron Generating Station Unit 1, ...

  18. State Nuclear Profiles 2010

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    Share of State total (percent) Net generation (thousand mwh) New Jersey nuclear power plants, summer capacity and net generation, 2010 Oyster Creek Unit 1 615 4,601 14.0 Exelon ...

  19. 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.

  20. 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.

  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 production [DOE 2004] and energy conversion technologies programs are described elsewhere.

  2. 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).

  3. Fostering the Next Generation of Nuclear Energy Technology |...

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

    this draft solicitation would support advanced nuclear energy technologies that will catalyze the deployment of future projects that replicate or extend a technological innovation. ...

  4. 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.

  5. 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...

  6. 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 application in heat exchangers and core internals for the NGNP. The primary candidates are Inconel 617, Haynes 230, Incoloy 800H and Hastelloy XR. Based on the technical maturity, availability in required product forms, experience base, and high temperature mechanical properties all of the vendor pre-conceptual design studies have specified Alloy 617 as the material of choice for heat exchangers. Also a draft code case for Alloy 617 was developed previously. Although action was suspended before the code case was accepted by ASME, this draft code case provides a significant head start for achieving codification of the material. Similarly, Alloy 800H is the material of choice for control rod sleeves. In addition to the above listed considerations, Alloy 800H is already listed in the nuclear section of the ASME Code; although the maximum use temperature and time need to be increased.

  7. Commercial nuclear power 1990

    SciTech Connect (OSTI)

    Not Available

    1990-09-28

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

  8. Monthly Nuclear Utility Generation by State and Reactor, 2003

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

    3" "January through December 2003" ,"Net" "State of Location","Capacity",,"JAN","FEB","MAR","APR","MAY","JUNE","JULY","AUG","SEP","OCT","NOV","DEC","Year-To-Date" "and Reactor Name","MW(e)",,"Megawatt hours"

  9. Monthly Nuclear Utility Generation by State and Reactor, 2004

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

    4" "January through December 2004" ,"Net" "State of Location","Capacity",,"JAN","FEB","MAR","APR","MAY","JUNE","JULY","AUG","SEP","OCT","NOV","DEC","Year-To-Date" "and Reactor Name","MW(e)",,"Megawatt hours"

  10. Monthly Nuclear Utility Generation by State and Reactor, 2005

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

    5" "January through December 2005" ,"Net" "State of Location","Capacity",,"JAN","FEB","MAR","APR","MAY","JUNE","JULY","AUG","SEP","OCT","NOV","DEC","Year-To-Date" "and Reactor Name","MW(e)",,"Megawatt hours"

  11. Monthly Nuclear Utility Generation by State and Reactor, 2007

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

    7" "January through December 2007" ,"Net" "State of Location","Capacity",,"JAN","FEB","MAR","APR","MAY","JUNE","JULY","AUG","SEP","OCT","NOV","DEC","Year-To-Date" "and Reactor Name","MW(e)",,"Megawatt hours"

  12. Monthly Nuclear Utility Generation by State and Reactor, 2008

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

    8" "January through December 2008" ,"Net" "State of Location","Capacity",,"JAN","FEB","MAR","APR","MAY","JUNE","JULY","AUG","SEP","OCT","NOV","DEC","Year-To-Date" "and Reactor Name","MW(e)",,"Megawatt hours"

  13. Mix and mingle: Networking for the next nuclear generation | Y-12 National

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

    Security Complex Mix and mingle: Networking ... Mix and mingle: Networking for the next nuclear generation Posted: February 25, 2016 - 2:55pm Print version CNS offers groups to help early career professionals. Whether you're starting your first career or establishing a new one, transitioning into the nuclear industry from college, the military or another profession or organization can be an exciting and challenging experience. Consolidated Nuclear Security, LLC has three programs that offer

  14. 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.

  15. Development of New Generation of Adsorbents and Waste Forms for Nuclear

    Office of Scientific and Technical Information (OSTI)

    Waste Management. (Conference) | SciTech Connect Development of New Generation of Adsorbents and Waste Forms for Nuclear Waste Management. Citation Details In-Document Search Title: Development of New Generation of Adsorbents and Waste Forms for Nuclear Waste Management. Abstract not provided. Authors: Wang, Yifeng Publication Date: 2014-10-01 OSTI Identifier: 1242125 Report Number(s): SAND2014-19376C 540938 DOE Contract Number: AC04-94AL85000 Resource Type: Conference Resource Relation:

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

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

    Requests for Scholarship and Fellowship Applications. | Department of Energy Investing in the next generation: The Office of Nuclear Energy Issues Requests for Scholarship and Fellowship Applications. Investing in the next generation: The Office of Nuclear Energy Issues Requests for Scholarship and Fellowship Applications. As President Obama recognized in the State of the Union on January 28th, 2014, the best way to grow the economy and create jobs is to prepare students with the skills

  17. State Nuclear Profiles 2010

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    Primary energy source Summer capacity (mw) Share of State total (percent) Net generation ... Limerick Unit 1, Unit 2 2,264 18,926 24.3 Exelon Nuclear PPL Susquehanna Unit 1, Unit 2 ...

  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

    Broader source: Energy.gov [DOE]

    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. Massachusetts Nuclear Profile - Power Plants

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

    nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Pilgrim Nuclear Power Station Unit 1",685,"5,918",100.0,"Entergy Nuclear Generation Co" "1 Plant 1 Reactor",685,"5,918",100.0 "Note: Totals may not equal sum of components due to

  1. 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.

  2. 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.

  3. Illinois Nuclear Profile - Power Plants

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

    Illinois nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Braidwood Generation Station Unit 1, Unit 2","2,330","19,200",20.0,"Exelon Nuclear" "Byron Generating Station Unit 1, Unit 2","2,300","19,856",20.6,"Exelon

  4. 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.

  5. 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.

  6. New Jersey Nuclear Profile - Power Plants

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

    nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Oyster Creek Unit 1",615,"4,601",14.0,"Exelon Nuclear" "PSEG Hope Creek Generating Station Unit 1","1,161","9,439",28.8,"PSEG Nuclear LLC" "PSEG Salem Generating

  7. Ohio Nuclear Profile - Power Plants

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

    Ohio nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Davis Besse Unit 1",894,"5,185",32.8,"FirstEnergy Nuclear Operating Company" "Perry Unit 1","1,240","10,620",67.2,"FirstEnergy Nuclear Operating Company" "2

  8. Maryland Nuclear Profile - Power Plants

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

    nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Calvert Cliffs Nuclear Power Plant Unit 1, Unit 2","1,705","13,994",100.0,"Calvert Cliffs Nuclear PP Inc" "1 Plant 2 Reactors","1,705","13,994",100.0 "Note: Totals

  9. California Nuclear Profile - Power Plants

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

    California nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Diablo Canyon Unit 1, Unit 2","2,240","18,430",57.2,"Pacific Gas & Electric Co" "San Onofre Nuclear Generating Station Unit 2, Unit

  10. Kansas Nuclear Profile - Power Plants

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

    Kansas nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Wolf Creek Generating Station Unit 1","1,160","9,556",100.0,"Wolf Creek Nuclear Optg Corp" "1 Plant 1 Reactor","1,160","9,556",100.0

  11. 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.

  12. 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 starting point for those studies; but, the general level of understanding of safety in coupling nuclear and chemical plants is less than in other areas of high-temperature reactor safety.

  13. 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.

  14. 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.

  15. 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 operating envelope of both fission and fusion reactors. In advanced fission reactors composite materials are being designed in an effort to extend the life and improve the reliability of fuel rod cladding as well as structural materials. Composites are being considered for use as core internals in the next generation of gas-cooled reactors. Further, next-generation plasma-fusion reactors, such as the International Thermonuclear Experimental Reactor (ITER) will rely on the capabilities of advanced composites to safely withstand extremely high neutron fluxes while providing superior thermal shock resistance.

  16. 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.

  17. 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 selected thermochemical process and to define the selected reactor and process to the point that capital costs, operating costs and the resultant cost of hydrogen can be estimated. During original contract negotiation, it was necessary to reduce work scope to meet funding limits. As a result, the reactor interface and process will not be iterated to the point that only hydrogen is produced. Rather, hydrogen and electricity will be co-generated and the hydrogen cost will be stated as a function of the electricity sales price.

  18. Pennsylvania Nuclear Profile - Power Plants

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

    Pennsylvania nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Beaver Valley Unit 1, Unit 2","1,777","14,994",19.3,"FirstEnergy Nuclear Operating Company" "Limerick Unit 1, Unit 2","2,264","18,926",24.3,"Exelon

  19. Arkansas Nuclear Profile - Power Plants

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

    nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Arkansas Nuclear One Unit 1, Unit 2","1,835","15,023",100.0,"Entergy Arkansas Inc" "1 Plant 2 Reactors","1,835","15,023",100.0

  20. Connecticut Nuclear Profile - Power Plants

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

    Connecticut nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Millstone Unit 2, Unit 3","2,103","16,750",100.0,"Dominion Nuclear Conn Inc" "1 Plant 2 Reactors","2,103","16,750",100.0

  1. Vermont Nuclear Profile - Power Plants

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

    nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Vermont Yankee Unit 1",620,"4,782",100.0,"Entergy Nuclear Vermont Yankee" "1 Plant 1 Reactor",620,"4,782",100.0

  2. Wisconsin Nuclear Profile - Power Plants

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

    Wisconsin nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Kewaunee Unit 1",566,"4,990",37.6,"Dominion Energy Kewaunee Inc." "Point Beach Nuclear Plant Unit 1, Unit 2","1,018","8,291",62.4,"NextEra Energy Point Beach

  3. 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.

  4. World nuclear outlook 1994

    SciTech Connect (OSTI)

    1994-12-01

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

  5. World nuclear outlook 1995

    SciTech Connect (OSTI)

    1995-09-29

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

  6. 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 electric plant. Depending on the process heat temperature and power needs, up to 80 % of the nuclear heat is converted into useful power. An important feature of the design is the standardization of the heat source, as independent as possible of the process heat application. This should expedite licensing. The essential conditions for success include: 1. Timely adapted licensing process and regulations, codes and standards for such application and design; 2. An industry oriented R and D program to meet the technological challenges making the best use of the international collaboration. Gen IV could be the vector; 3. Identification of an end user (or a consortium of) willing to fund a FOAK. (authors)

  7. 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.

  8. 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.

  9. Washington Nuclear Profile - Power Plants

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

    Washington nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Columbia Generating Station Unit 2","1,097","9,241",100.0,"Energy Northwest" "1 Plant 1 Reactor","1,097","9,241",100.0

  10. 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).

  11. 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.

  12. 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.

  13. 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.

  14. 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) concepts, such as the NGNP, it is fully expected that the behavior of these graphites will conform to the recognized trends for near isotropic nuclear graphite. Thus, much of the data needed is confirmatory in nature. Theories that can explain graphite behavior have been postulated and, in many cases, shown to represent experimental data well. However, these theories need to be tested against data for the new graphites and extended to higher neutron doses and temperatures pertinent to the new Gen IV reactor concepts. It is anticipated that current and planned future graphite irradiation experiments will provide the data needed to validate many of the currently accepted models, as well as providing the needed data for design confirmation.

  15. 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 experiment. The first experiment was inserted in the ATR in August 2009 and started its irradiation in September 2009. It is anticipated to complete its irradiation in early calendar 2011. This paper will discuss the design of the experiment including the test train and the temperature and compressive load monitoring, control, and the irradiation experience to date.

  16. 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.

  17. 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.

  18. 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&E species take, consultations, and evaluations of potential effects of operation on T&E species. This search recovered a total of approximately 100 documents from 13 sites. Sites that were in the relicensing or decommissioning processes were excluded from the ADAMS search. In general the ADAMS search did not reveal any serious deficiencies or compliance problems. The most notable finds were reports of takes of green sea turtles at Diablo Canyon. While these events were reported to both the NRC and to NOAA Fisheries, no record of interaction between the two federal agencies was found. Species potentially present at each site were determined via querying the Geographical, Environmental, and Siting Information System (GEn&SIS) database developed for the NRC by Lawrence Livermore National Laboratory. The results of these queries were compared against the 1997 review, and in the cases of sites that were in the relicensing process, with the results of those site specific evaluations. A total of 452 T&E species were identified as potentially occurring near one or more of the operating commercial nuclear power generating plants. Information about each of these species was gathered to support an assessment of the probability of occurrence at each of the reactor sites. Based on the assessments of which species are potentially affected at each site, and the information gathered through the ADAMS search, each site was assigned a priority value for follow-up evaluations. The priority listing did not include any sites that had entered the relicensing process, those where the licensee has indicated that they intend to enter the relicensing process before the end of 2005, or those that have entered the decommissioning process. Of the 39 remaining sites, those that were identified as the highest priority for follow-on evaluations are: Diablo Canyon, San Onofre, Crystal River, Harris, and Vogtle, followed by South Texas, Palo Verde, Salem, and Cooper.

  19. Property:Capacity | Open Energy Information

    Open Energy Info (EERE)

    Capacity Jump to: navigation, search Property Name Capacity Property Type Quantity Description Potential electric energy generation, default units of megawatts. Use this property...

  20. 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.

  1. 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.

  2. 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.

  3. Louisiana Nuclear Profile - Power Plants

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

    Louisiana nuclear power plants, summer capacity and net generation, 2010" "Plant Name/Total Reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (Pprcent)","Owner" "River Bend Unit 1",974,"8,363",44.9,"Entergy Gulf States - LA LLC" "Waterford 3 Unit 3","1,168","10,276",55.1,"Entergy Louisiana Inc" "2 Plants 2

  4. Michigan Nuclear Profile - Power Plants

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

    nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Donald C Cook Unit 1, Unit 2","2,069","15,646",52.8,"Indiana Michigan Power Co" "Fermi Unit 2","1,085","7,738",26.1,"Detroit Edison Co" "Palisades Unit

  5. Minnesota Nuclear Profile - Power Plants

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

    Minnesota nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Monticello Unit 1",554,"4,695",34.8,"Northern States Power Co - Minnesota" "Prairie Island Unit 1, Unit 2","1,040","8,783",65.2,"Northern States Power Co -

  6. Mississippi Nuclear Profile - Power Plants

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

    Mississippi nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Grand Gulf Unit 1","1,251","9,643",100.0,"System Energy Resources, Inc" "1 Plant 1 Reactor","1,251","9,643",100.0

  7. Missouri Nuclear Profile - Power Plants

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

    nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Callaway Unit 1","1,190","8,996",100.0,"Union Electric Co" "1 Plant 1 Reactor","1,190","8,996",100.0 "Note: Totals may not equal sum of components due to

  8. Nebraska Nuclear Profile - Power Plants

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

    Nebraska nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Cooper Unit 1",767,"6,793",61.4,"Nebraska Public Power District" "Fort Calhoun Unit 1",478,"4,261",38.6,"Omaha Public Power District" "2 Plants 2

  9. Alabama Nuclear Profile - Power Plants

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

    nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Browns Ferry Unit 1, Unit 2, Unit 3","3,309","24,771",65.3,"Tennessee Valley Authority" "Joseph M Farley Unit 1, Unit 2","1,734","13,170",34.7,"Alabama Power

  10. Arizona Nuclear Profile - Power Plants

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

    nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Palo Verde Unit 1, Unit 2, Unit 3","3,937","31,200",100.0,"Arizona Public Service Co" "1 Plant 3 Reactors","3,937","31,200",100.0 "Note: Totals may not equal sum of

  11. Florida Nuclear Profile - Power Plants

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

    Florida nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Crystal River Unit 3",860,0,"--","Progress Energy Florida Inc" "St Lucie Unit 1, Unit 2","1,678","12,630",52.8,"Florida Power & Light Co" "Turkey Point

  12. Georgia Nuclear Profile - Power Plants

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

    nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Edwin I Hatch Unit 1, Unit 2","1,759","13,902",41.5,"Georgia Power Co" "Vogtle Unit 1, Unit 2","2,302","19,610",58.5,"Georgia Power Co" "2 Plants 4

  13. Iowa Nuclear Profile - Power Plants

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

    Iowa nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Duane Arnold Energy Center Unit 1",601,"4,451",100.0,"NextEra Energy Duane Arnold LLC" "1 Plant 1 Reactor",601,"4,451",100.0

  14. Virginia Nuclear Profile - Power Plants

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

    nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "North Anna Unit 1, Unit 2","1,863","13,399",50.4,"Virginia Electric & Power Co" "Surry Unit 1, Unit 2","1,638","13,172",49.6,"Virginia Electric & Power

  15. 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.

  16. New York Nuclear Profile - Power Plants

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

    nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Indian Point Unit 2, Unit 3","2,063","16,321",39.0,"Entergy Nuclear Indian Point" "James A Fitzpatrick Unit 1",855,"6,361",15.2,"Entergy Nuc Fitzpatrick LLC" "Nine

  17. EIA - State Nuclear Profiles

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

    Vermont profile Vermont total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 620 55.0 4,782 72.2 Hydro and Pumped Storage 324 28.7 1,347 20.3 Natural Gas - - 4 0.1 Other Renewable1 84 7.5 482 7.3 Petroleum 100 8.9 5 0.1 Total 1,128 100.0 6,620 100.0 1Municipal Solid Waste net generation is allocated according to the

  18. EIA - State Nuclear Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Vermont profile Vermont total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 620 55.0 4,782 72.2 Hydro and Pumped Storage 324 28.7 1,347 20.3 Natural Gas - - 4 0.1 Other Renewable1 84 7.5 482 7.3 Petroleum 100 8.9 5 0.1 Total 1,128 100.0 6,620 100.0 1Municipal Solid Waste net generation is allocated according to the

  19. 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.

  20. 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 concluded, however, that with adequate engineered cooling of the vessel, the A508/533 steels are also acceptable.

  1. 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 both the PBMR and prismatic design. The main focus of this report is the RPV for both design concepts with emphasis on material selection.

  2. State Nuclear Profiles 2010

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

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

  3. 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.

  4. 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.

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

    Broader source: Energy.gov [DOE]

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

  6. 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.

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

    SciTech Connect (OSTI)

    Hur, Jin-Suk; Roh, Myung- Sub

    2014-02-12

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

  8. 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 application in heat exchangers and core internals for the NGNP. The primary candidates are Inconel 617, Haynes 230, Incoloy 800H and Hastelloy XR. Based on the technical maturity, availability in required product forms, experience base, and high temperature mechanical properties all of the vendor pre-conceptual design studies have specified Alloy 617 as the material of choice for heat exchangers. Also a draft code case for Alloy 617 was developed previously. Although action was suspended before the code case was accepted by ASME, this draft code case provides a significant head start for achieving codification of the material. Similarly, Alloy 800H is the material of choice for control rod sleeves. In addition to the above listed considerations, Alloy 800H is already listed in the nuclear section of the ASME Code; although the maximum use temperature and time need to be increased.

  9. Property:Cooling Capacity | Open Energy Information

    Open Energy Info (EERE)

    Pages using the property "Cooling Capacity" Showing 2 pages using this property. D Distributed Generation Study615 kW Waukesha Packaged System + 90 + Distributed Generation...

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

    SciTech Connect (OSTI)

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

    2013-02-01

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

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

    SciTech Connect (OSTI)

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

    2013-07-01

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

  12. 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.

  13. 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.

  14. CHP Installed Capacity Optimizer Software

    Energy Science and Technology Software Center (OSTI)

    2004-11-30

    The CHP Installed Capacity Optimizer is a Microsoft Excel spreadsheet application that determines the most economic amount of capacity of distributed generation and thermal utilization equipment (e.g., absorption chillers) to install for any user-defined set of load and cost data. Installing the optimum amount of capacity is critical to the life-cycle economic viability of a distributed generation/cooling heat and power (CHP) application. Using advanced optimization algorithms, the software accesses the loads, utility tariffs, equipment costs,more » etc., and provides to the user the most economic amount of system capacity to install.« less

  15. CSTI high capacity power

    SciTech Connect (OSTI)

    Winter, J.M.

    1994-09-01

    The SP-100 program was established in 1983 by DOD, DOE, and NASA as a joint program to develop the technology necessary for space nuclear power systems for military and civil application. During FY86 and 87, the NASA SP-100 Advanced Technology Program was devised to maintain the momentum of promising technology advancement efforts started during Phase I of SP-100 and to strengthen, in key areas, the chances for successful development and growth capability of space nuclear reactor power systems for future space applications. In FY88, the Advanced Technology Program was incorporated into NASA`s new Civil Space Technology Initiative (CSTI). The CSTI Program was established to provide the foundation for technology development in automation and robotics, information, propulsion, and power. The CSTI High Capacity Power Program builds on the technology efforts of the SP-100 program, incorporates the previous NASA SP-100 Advanced Technology project, and provides a bridge to NASA Project Pathfinder. The elements of CSTI High Capacity Power development include Conversion Systems, Thermal Management, Power Management, System Diagnostics, and Environmental Interactions. Technology advancement in all areas, including materials, is required to assure the high reliability and 7 to 10 year lifetime demanded for future space nuclear power systems. The overall program will develop and demonstrate the technology base required to provide a wide range of modular power systems as well as allowing mission independence from solar and orbital attitude requirements. Several recent advancements in CSTI High Capacity power development will be discussed.

  16. 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-to-moderator ratio). We also learned how to perform design optimization calculations by using a genetic algorithm that automatically selects a sequence of design parameter sets to meet specified fitness criteria increasingly well. In the pebble-bed NGNP design work, we use the genetic algorithm to direct the INEELs PEBBED code to perform hundreds of code runs in less than a day to find optimized design configurations. And finally, we learned how to calculate cross sections more accurately for pebble bed reactors, and we identified research needs for the further refinement of the cross section calculations.

  17. New York Nuclear Profile - Nine Mile Point Nuclear Station

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

    Nine Mile Point Nuclear Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration date" 1,630,"5,294",95.9,"BWR","application/vnd.ms-excel","application/vnd.ms-excel"

  18. New York Nuclear Profile - R E Ginna Nuclear Power Plant

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

    R E Ginna Nuclear Power Plant" "Unit","Summer Capacity (MW)","Net Generation (Thousand MWh)","Summer Capacity Factor (Percent)","Type","Commercial Operation Date","License Expiration Date" 1,581,"4,948",97.2,"PWR","application/vnd.ms-excel","application/vnd.ms-excel" ,581,"4,948",97.2

  19. Maryland Nuclear Profile - Calvert Cliffs Nuclear Power Plant

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

    Calvert Cliffs Nuclear Power Plant" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration date" 1,855,"6,755",90.2,"PWR","application/vnd.ms-excel","application/vnd.ms-excel"

  20. World nuclear fuel cycle requirements 1991

    SciTech Connect (OSTI)

    Not Available

    1991-10-10

    The nuclear fuel cycle consists of mining and milling uranium ore, processing the uranium into a form suitable for generating electricity, burning'' the fuel in nuclear reactors, and managing the resulting spent nuclear fuel. This report presents projections of domestic and foreign requirements for natural uranium and enrichment services as well as projections of discharges of spent nuclear fuel. These fuel cycle requirements are based on the forecasts of future commercial nuclear power capacity and generation published in a recent Energy Information Administration (EIA) report. Also included in this report are projections of the amount of spent fuel discharged at the end of each fuel cycle for each nuclear generating unit in the United States. The International Nuclear Model is used for calculating the projected nuclear fuel cycle requirements. 14 figs., 38 tabs.

  1. North Carolina Nuclear Profile - Power Plants

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

    Carolina nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Brunswick Unit 1, Unit 2","1,858","14,808",36.3,"Progress Energy Carolinas Inc" "Harris Unit 1",900,"7,081",17.4,"Progress Energy Carolinas Inc" "McGuire

  2. South Carolina Nuclear Profile - Power Plants

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

    South Carolina nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Catawba Unit 1, Unit 2","2,258","18,964",36.5,"Duke Energy Carolinas, LLC" "H B Robinson Unit 2",724,"3,594",6.9,"Progress Energy Carolinas Inc"

  3. New Hampshire Nuclear Profile - Power Plants

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

    nuclear power plants, summer capacity and net generation, 2010" "Plant name/total reactors","Summer capacity (nw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Seabrook Unit 1","1,247","10,910",100.0,"NextEra Energy Seabrook LLC" "1 Plant 1 Reactor","1,247","10,910",100.0 "Note: Totals may not equal sum of components due

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

    Broader source: Energy.gov [DOE]

    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...

  5. Arkansas Nuclear Profile - Arkansas Nuclear One

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

    Nuclear One" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration date" 1,842,"6,607",89.6,"PWR","application/vnd.ms-excel","application/vnd.ms-excel" 2,993,"8,416",96.7,"PWR","application/vnd.ms-excel","application/vnd.ms-excel"

  6. Wisconsin Nuclear Profile - Point Beach Nuclear Plant

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

    Point Beach Nuclear Plant" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration date" 1,506,"3,954",89.2,"PWR","application/vnd.ms-excel","application/vnd.ms-excel" 2,512,"4,336",96.7,"PWR","application/vnd.ms-excel","application/vnd.ms-excel"

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

    DOE Patents [OSTI]

    Brown, Roger A.

    1994-01-01

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

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

    DOE Patents [OSTI]

    Brown, R.A.

    1994-04-19

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

  9. Massachusetts Nuclear Profile - Pilgrim Nuclear Power Station

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

    Pilgrim Nuclear Power Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer cpacity factor (percent)","Type","Commercial operation date","License expiration date" 1,685,"5,918",98.7,"BWR","application/vnd.ms-excel","application/vnd.ms-excel" ,685,"5,918",98.7

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

    SciTech Connect (OSTI)

    VanKuiken, J.C.; Guziel, K.A.; Tompkins, M.M.; Buehring, W.A.

    1997-09-01

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

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

    SciTech Connect (OSTI)

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

    1981-09-15

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

  12. nuclear

    National Nuclear Security Administration (NNSA)

    2%2A en U.S-, Japan Exchange Best Practices on Nuclear Emergency Response http:nnsa.energy.govmediaroompressreleasesu.s-japan-exchange-best-practices-nuclear-emergency-respon...

  13. NERI Final Project Report: On-Line Intelligent Self-Diagnostic Monitoring System for Next Generation Nuclear Power Plants

    SciTech Connect (OSTI)

    Bond, Leonard J.; Jarrell, Donald B.; Koehler, Theresa M.; Meador, Richard J.; Sisk, Daniel R.; Hatley, Darrel D.; Watkins, Kenneth S.; Chai, Jangbom; Kim, Wooshik

    2003-06-20

    This project provides a proof-of-principle technology demonstration for SDMS, where a distributed suite of sensors is integrated with active components and passive structures of types expected to be encountered in next generation nuclear power reactor and plant systems. The project employs state-of-the-art operational sensors, advanced stressor-based instrumentation, distributed computing, RF data network modules and signal processing to improve the monitoring and assessment of the power reactor system and gives data that is used to provide prognostics capabilities.

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

    SciTech Connect (OSTI)

    Timothy Shaw; Anthony Baratta; Vaughn Whisker

    2005-02-28

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

  15. Accelerated development of Zr-containing new generation ferritic steels for advanced nuclear reactors

    SciTech Connect (OSTI)

    Tan, Lizhen; Yang, Ying; Sridharan, K.

    2015-12-01

    The mission of the Nuclear Energy Enabling Technologies (NEET) program is to develop crosscutting technologies for nuclear energy applications. Advanced structural materials with superior performance at elevated temperatures are always desired for nuclear reactors, which can improve reactor economics, safety margins, and design flexibility. They benefit not only new reactors, including advanced light water reactors (LWRs) and fast reactors such as the sodium-cooled fast reactor (SFR) that is primarily designed for management of high-level wastes, but also life extension of the existing fleet when component exchange is needed. Developing and utilizing the modern materials science tools (experimental, theoretical, and computational tools) is an important path to more efficient alloy development and process optimization. The ultimate goal of this project is, with the aid of computational modeling tools, to accelerate the development of Zr-bearing ferritic alloys that can be fabricated using conventional steelmaking methods. The new alloys are expected to have superior high-temperature creep performance and excellent radiation resistance as compared to Grade 91. The designed alloys were fabricated using arc-melting and drop-casting, followed by hot rolling and conventional heat treatments. Comprehensive experimental studies have been conducted on the developed alloys to evaluate their hardness, tensile properties, creep resistance, Charpy impact toughness, and aging resistance, as well as resistance to proton and heavy ion (Fe2+) irradiation.

  16. Nuclear | Open Energy Information

    Open Energy Info (EERE)

    High construction costs for nuclear plants, especially relative to natural-gas-fired plants, make other options for new nuclear capacity uneconomical even in the alternative...

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

    SciTech Connect (OSTI)

    Stone, Timothy Amos

    2010-01-01

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

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

    SciTech Connect (OSTI)

    Brewer, Jeffrey D.

    2005-11-01

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

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

    SciTech Connect (OSTI)

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

    2012-07-01

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

  20. EIA - State Nuclear Profiles

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

    Alabama Nuclear Profile 2010 Alabama profile Alabama total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 5,043 15.6 37,941 24.9 Coal 11,441 35.3 63,050 41.4 Hydro and Pumped Storage 3,272 10.1 8,704 5.7 Natural Gas 11,936 36.8 39,235 25.8 Other1 100 0.3 643 0.4 Other Renewable1 583 1.8 2,377 1.6 Petroleum 43 0.1 200

  1. EIA - State Nuclear Profiles

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

    Arizona Nuclear Profile 2010 Arizona profile Arizona total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 1,937 14.9 31,200 27.9 Coal 6,233 23.6 43,644 39.1 Hydro and Pumped Storage 2,937 11.1 6,831 6.1 Natural Gas 13,012 49.3 29,676 26.6 Other 1 - - 15 * Other Renewable1 181 0.7 319 0.3 Petroleum 93 0.4 66 0.1 Total

  2. EIA - State Nuclear Profiles

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

    Arkansas Nuclear Profile 2010 Arkansas profile Arkansas total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State ttal (percent) Nuclear 1,835 11.5 15,023 24.6 Coal 4,535 28.4 28,152 46.2 Hydro and Pumped Storage 1,369 8.6 3,658 6.0 Natural Gas 7,894 49.4 12,469 20.4 Other 1 - - 28 * Other Renewable1 326 2.0 1,624 2.7 Petroleum 22 0.1 45 0.1 Total

  3. EIA - State Nuclear Profiles

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

    California Nuclear Profile 2010 California profile California total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 4,390 6.5 32,201 15.8 Coal 374 0.6 2,100 1.0 Hydro and Pumped Storage 13,954 20.7 33,260 16.3 Natural Gas 41,370 61.4 107,522 52.7 Other 1 220 0.3 2,534 1.2 Other Renewable1 6,319 9.4 25,450 12.5 Petroleum

  4. EIA - State Nuclear Profiles

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

    Connecticut Nuclear Profile 2010 Connecticut profile Connecticut total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 2,103 25.4 16,750 50.2 Coal 564 6.8 2,604 7.8 Hydro and Pumped Storage 151 1.8 400 1.2 Natural Gas 2,292 27.7 11,716 35.1 Other 1 27 0.3 730 2.2 Other Renewable1 159 1.9 740 2.2 Petroleum 2,989 36.1 409

  5. EIA - State Nuclear Profiles

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

    Florida Nuclear Profile 2010 Florida profile Florida total electric power industry, summer capacity and net generation, by energy source, 2010 Primary Energy Source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 3,924 6.6 23,936 10.4 Coal 9,975 16.9 59,897 26.1 Hydro and Pumped Storage 55 0.1 177 0.1 Natural Gas 31,563 53.4 128,634 56.1 Other1 544 0.9 2,842 1.2 Other Renewable1 1,053 1.8 4,487 2.0 Petroleum 12,033 20.3

  6. EIA - State Nuclear Profiles

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

    Georgia Nuclear Profile 2010 Georgia profile Georgia total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 4,061 11.1 33,512 24.6 Coal 13,230 36.1 73,298 54.0 Hydro and Pumped Storage 3,851 10.5 3,044 2.7 Natural Gas 12,668 34.6 23,884 15.9 Other 1 - - 18 * Other Renewable1 637 1.7 3,181 2.2 Petroleum 2,189 6.0 641 0.5

  7. EIA - State Nuclear Profiles

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

    Illinois Nuclear Profile 2010 Illinois profile Illinois total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 11,441 25.9 96,190 47.8 Coal 15,551 35.2 93,611 46.5 Hydro and Pumped Storage 34 0.1 119 0.1 Natural Gas 13,771 31.2 5,724 2.8 Other 1 145 0.3 461 0.2 Other Renewable1 2,078 4.7 5,138 2.6 Petroleum 1,106 2.5 110

  8. EIA - State Nuclear Profiles

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

    Iowa Nuclear Profile 2010 Iowa profile Iowa total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 601 4.1 4,451 7.7 Coal 6,956 47.7 41,283 71.8 Hydro and Pumped Storage 144 1.0 948 1.6 Natural Gas 2,299 15.8 1,312 2.3 Other Renewable1 3,584 24.6 9,360 16.3 Petroleum 1,007 6.9 154 .0.3 Total 14,592 100.0 57,509 100

  9. EIA - State Nuclear Profiles

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

    Kansas Nuclear Profile 2010 Kansas profile Kansas total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 1,160 9.2 9,556 19.9 Coal 5,179 41.3 32,505 67.8 Hydro and Pumped Storage 3 * 13 * Natural Gas 4,573 36.5 2,287 4.8 Other Renewable1 1,079 8.6 3,459 7.2 Petroleum 550 4.4 103 0.2 Total 12,543 100.0 47,924 100

  10. EIA - State Nuclear Profiles

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

    Louisiana Nuclear Profile 2010 Louisiana profile Louisiana total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (nw) Share of State total (percent) Net generation (thousand nwh) Share of State total (percent) Nuclear 2,142 8.0 18,639 18.1 Coal 3,417 12.8 23,924 23.3 Hydro and Pumped Storage 192 0.7 1,109 1.1 Natural Gas 19,574 73.2 51,344 49.9 Other 1 213 0.8 2,120 2.1 Other Renewable1 325 1.2 2,468 2.4 Petroleum 881 3.3

  11. EIA - State Nuclear Profiles

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

    Maryland Nuclear Profile 2010 Maryland profile Maryland total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (Percent) Nuclear 1,705 13.6 13,994 32.1 Coal 4,886 39.0 23,668 54.3 Hydro and Pumped Storage 590 4.7 1,667 3.8 Natural Gas 2,041 16.3 2,897 6.6 Other 1 152 1.2 485 1.1 Other Renewable1 209 1.7 574 1.3 Petroleum 2,933 23.4 322

  12. EIA - State Nuclear Profiles

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

    Massachusetts Nuclear Profile 2010 Massachusetts profile Massachusetts total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 685 5.0 5,918 13.8 Coal 1,669 12.2 8,306 19.4 Hydro and Pumped Storage 1,942 14.2 659 1.5 Natural Gas 6,063 44.3 25,582 59.8 Other 1 3 * 771 1.8 Other Renewable1 304 2.2 1,274 3.0 Petroleum 3,031

  13. EIA - State Nuclear Profiles

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

    Michigan Nuclear Profile 2010 Michigan profile Michigan total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 3,947 13.2 29,625 26.6 Coal 11,531 38.7 65,604 58.8 Hydro and Pumped Storage 2,109 7.1 228 0.2 Natural Gas 11,033 37.0 12,249 11.0 Other 1 - - 631 0.6 Other Renewable1 571 1.9 2,832 2.5 Petroleum 640 2.1 382 0.3

  14. EIA - State Nuclear Profiles

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

    Minnesota Nuclear Profile 2010 Minnesota profile Minnesota total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 1,549 10.8 13,478 25.1 Coal 4,789 32.5 28,083 52.3 Hydro and Pumped Storage 193 1.3 840 1.6 Natural Gas 4,936 33.5 4,341 8.1 Other 1 13 0.1 258 0.5 Other Renewable1 2,395 16.3 6,640 12.4 Petroleum 795 5.4 31

  15. EIA - State Nuclear Profiles

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

    Mississippi Nuclear Profile 2010 Mississippi profile Mississippi total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 1,251 8.0 9,643 17.7 Coal 2,526 16.1 13,629 25.0 Natural Gas 11,640 74.2 29,619 54.4 Other 1 4 * 10 * Other Renewable1 235 1.5 1,504 2.8 Petroleum 35 0.2 18 0.1 Total 15,691 100.0 54,487 100.0

  16. EIA - State Nuclear Profiles

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

    Missouri Nuclear Profile 2010 Missouri profile Missouri total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 1,190 5.5 8,996 9.7 Coal 12,070 55.5 75,047 81.3 Hydro and Pumped Storage 1,221 5.6 2,427 2.6 Natural Gas 5,579 25.7 4,690 5.1 Other 1 - - 39 * Other Renewable1 466 2.1 988 1.1 Petroleum 1,212 5.6 126 0.1 Total

  17. EIA - State Nuclear Profiles

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

    Nebraska Nuclear Profile 2010 Nebraska profile Nebraska total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 1,245 15.8 11,054 30.2 Coal 3,932 50.0 23,368 63.8 Hydro and Pumped Storage 278 3.5 1,314 3.6 Natural Gas 1,864 23.5 375 1.0 Other Renewable1 165 2.1 493 1.3 Petroleum 387 4.9 31 0.1 Total 7,857 100.0 36,630

  18. EIA - State Nuclear Profiles

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

    Hampshire Nuclear Profile 2010 New Hampshire profile New Hampshire total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 1,247 29.8 10,910 49.2 Coal 546 13.1 3,083 13.9 Hydro and Pumped Storage 489 11.7 1,478 6.7 Natural Gas 1,215 29.1 5,365 24.2 Other 1 - - 57 0.3 Other Renewable1 182 4.4 1,232 5.6 Petroleum 501 12.0

  19. EIA - State Nuclear Profiles

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

    Jersey Nuclear Profile 2010 New Jersey profile New Jersey total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 4,108 22.3 32,771 49.9 Coal 2,036 11.1 6,418 9.8 Hydro and Pumped Storage 404 2.2 -176 -0.3 Natural Gas 10,244 55.6 24,902 37.9 Other 1 56 0.3 682 1.0 Other Renewable1 226 1.2 850 1.3 Petroleum 1,351 7.3 235

  20. EIA - State Nuclear Profiles

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

    York Nuclear Profile 2010 New York profile New York total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 5,271 13.4 41,870 30.6 Coal 2,781 7.1 13,583 9.9 Hydro and Pumped Storage 5,714 14.5 24,942 18.2 Natural Gas 17,407 44.2 48,916 35.7 Other 1 45 0.1 832 0.6 Other Renewable1 1,719 4.4 4,815 3.5 Petroleum 6,421 16.3

  1. EIA - State Nuclear Profiles

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

    North Carolina Nuclear Profile 2010 North Carolina profile North Carolina total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 4,958 17.9 40,740 31.7 Coal 12,766 46.1 71,951 55.9 Hydro and Pumped Storage 2,042 7.4 4,757 3.7 Natural Gas 6,742 24.4 8,447 6.6 Other 1 50 0.2 407 0.3 Other Renewable1 543 2.0 2,083 1.6

  2. EIA - State Nuclear Profiles

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

    Ohio Nuclear Profile 2010 Ohio profile Ohio total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 2,134 6.5 15,805 11.0 Coal 21,360 64.6 117,828 82.1 Hydro and Pumped Storage 101 0.3 429 0.3 Natural Gas 8,203 24.8 7,128 5.0 Other 1 123 0.4 266 0.2 Other Renewable1 130 0.4 700 0.5 Petroleum 1,019 3.1 1,442 1.0 Total

  3. EIA - State Nuclear Profiles

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

    Pennsylvania Nuclear Profile 2010 Pennsylvania profile Pennsylvania total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 9,540 20.9 77,828 33.9 Coal 18,481 40.6 110,369 48.0 Hydro and Pumped Storage 2,268 5.0 1,624 0.7 Natural Gas 9,415 20.7 33,718 14.7 Other 1 100 0.2 1,396 0.6 Other Renewable1 1,237 2.7 4,245 1.8

  4. EIA - State Nuclear Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Massachusetts Nuclear Profile 2010 Massachusetts profile Massachusetts total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 685 5.0 5,918 13.8 Coal 1,669 12.2 8,306 19.4 Hydro and Pumped Storage 1,942 14.2 659 1.5 Natural Gas 6,063 44.3 25,582 59.8 Other 1 3 * 771 1.8 Other Renewable1 304 2.2 1,274 3.0 Petroleum 3,031

  5. EIA - State Nuclear Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Michigan Nuclear Profile 2010 Michigan profile Michigan total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 3,947 13.2 29,625 26.6 Coal 11,531 38.7 65,604 58.8 Hydro and Pumped Storage 2,109 7.1 228 0.2 Natural Gas 11,033 37.0 12,249 11.0 Other 1 - - 631 0.6 Other Renewable1 571 1.9 2,832 2.5 Petroleum 640 2.1 382 0.3

  6. EIA - State Nuclear Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Mississippi Nuclear Profile 2010 Mississippi profile Mississippi total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 1,251 8.0 9,643 17.7 Coal 2,526 16.1 13,629 25.0 Natural Gas 11,640 74.2 29,619 54.4 Other 1 4 * 10 * Other Renewable1 235 1.5 1,504 2.8 Petroleum 35 0.2 18 0.1 Total 15,691 100.0 54,487 100.0

  7. EIA - State Nuclear Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Missouri Nuclear Profile 2010 Missouri profile Missouri total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 1,190 5.5 8,996 9.7 Coal 12,070 55.5 75,047 81.3 Hydro and Pumped Storage 1,221 5.6 2,427 2.6 Natural Gas 5,579 25.7 4,690 5.1 Other 1 - - 39 * Other Renewable1 466 2.1 988 1.1 Petroleum 1,212 5.6 126 0.1 Total

  8. EIA - State Nuclear Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Nebraska Nuclear Profile 2010 Nebraska profile Nebraska total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 1,245 15.8 11,054 30.2 Coal 3,932 50.0 23,368 63.8 Hydro and Pumped Storage 278 3.5 1,314 3.6 Natural Gas 1,864 23.5 375 1.0 Other Renewable1 165 2.1 493 1.3 Petroleum 387 4.9 31 0.1 Total 7,857 100.0 36,630

  9. EIA - State Nuclear Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Hampshire Nuclear Profile 2010 New Hampshire profile New Hampshire total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 1,247 29.8 10,910 49.2 Coal 546 13.1 3,083 13.9 Hydro and Pumped Storage 489 11.7 1,478 6.7 Natural Gas 1,215 29.1 5,365 24.2 Other 1 - - 57 0.3 Other Renewable1 182 4.4 1,232 5.6 Petroleum 501 12.0

  10. EIA - State Nuclear Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Ohio Nuclear Profile 2010 Ohio profile Ohio total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 2,134 6.5 15,805 11.0 Coal 21,360 64.6 117,828 82.1 Hydro and Pumped Storage 101 0.3 429 0.3 Natural Gas 8,203 24.8 7,128 5.0 Other 1 123 0.4 266 0.2 Other Renewable1 130 0.4 700 0.5 Petroleum 1,019 3.1 1,442 1.0 Total

  11. EIA - State Nuclear Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Alabama Nuclear Profile 2010 Alabama profile Alabama total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 5,043 15.6 37,941 24.9 Coal 11,441 35.3 63,050 41.4 Hydro and Pumped Storage 3,272 10.1 8,704 5.7 Natural Gas 11,936 36.8 39,235 25.8 Other1 100 0.3 643 0.4 Other Renewable1 583 1.8 2,377 1.6 Petroleum 43 0.1 200

  12. EIA - State Nuclear Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Arizona Nuclear Profile 2010 Arizona profile Arizona total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 1,937 14.9 31,200 27.9 Coal 6,233 23.6 43,644 39.1 Hydro and Pumped Storage 2,937 11.1 6,831 6.1 Natural Gas 13,012 49.3 29,676 26.6 Other 1 - - 15 * Other Renewable1 181 0.7 319 0.3 Petroleum 93 0.4 66 0.1 Total

  13. EIA - State Nuclear Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Arkansas Nuclear Profile 2010 Arkansas profile Arkansas total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State ttal (percent) Nuclear 1,835 11.5 15,023 24.6 Coal 4,535 28.4 28,152 46.2 Hydro and Pumped Storage 1,369 8.6 3,658 6.0 Natural Gas 7,894 49.4 12,469 20.4 Other 1 - - 28 * Other Renewable1 326 2.0 1,624 2.7 Petroleum 22 0.1 45 0.1 Total

  14. EIA - State Nuclear Profiles

    Gasoline and Diesel Fuel Update (EIA)

    California Nuclear Profile 2010 California profile California total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 4,390 6.5 32,201 15.8 Coal 374 0.6 2,100 1.0 Hydro and Pumped Storage 13,954 20.7 33,260 16.3 Natural Gas 41,370 61.4 107,522 52.7 Other 1 220 0.3 2,534 1.2 Other Renewable1 6,319 9.4 25,450 12.5 Petroleum

  15. EIA - State Nuclear Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Connecticut Nuclear Profile 2010 Connecticut profile Connecticut total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 2,103 25.4 16,750 50.2 Coal 564 6.8 2,604 7.8 Hydro and Pumped Storage 151 1.8 400 1.2 Natural Gas 2,292 27.7 11,716 35.1 Other 1 27 0.3 730 2.2 Other Renewable1 159 1.9 740 2.2 Petroleum 2,989 36.1 409

  16. EIA - State Nuclear Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Florida Nuclear Profile 2010 Florida profile Florida total electric power industry, summer capacity and net generation, by energy source, 2010 Primary Energy Source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 3,924 6.6 23,936 10.4 Coal 9,975 16.9 59,897 26.1 Hydro and Pumped Storage 55 0.1 177 0.1 Natural Gas 31,563 53.4 128,634 56.1 Other1 544 0.9 2,842 1.2 Other Renewable1 1,053 1.8 4,487 2.0 Petroleum 12,033 20.3

  17. EIA - State Nuclear Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Georgia Nuclear Profile 2010 Georgia profile Georgia total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 4,061 11.1 33,512 24.6 Coal 13,230 36.1 73,298 54.0 Hydro and Pumped Storage 3,851 10.5 3,044 2.7 Natural Gas 12,668 34.6 23,884 15.9 Other 1 - - 18 * Other Renewable1 637 1.7 3,181 2.2 Petroleum 2,189 6.0 641 0.5

  18. EIA - State Nuclear Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Illinois Nuclear Profile 2010 Illinois profile Illinois total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 11,441 25.9 96,190 47.8 Coal 15,551 35.2 93,611 46.5 Hydro and Pumped Storage 34 0.1 119 0.1 Natural Gas 13,771 31.2 5,724 2.8 Other 1 145 0.3 461 0.2 Other Renewable1 2,078 4.7 5,138 2.6 Petroleum 1,106 2.5 110

  19. EIA - State Nuclear Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Iowa Nuclear Profile 2010 Iowa profile Iowa total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 601 4.1 4,451 7.7 Coal 6,956 47.7 41,283 71.8 Hydro and Pumped Storage 144 1.0 948 1.6 Natural Gas 2,299 15.8 1,312 2.3 Other Renewable1 3,584 24.6 9,360 16.3 Petroleum 1,007 6.9 154 .0.3 Total 14,592 100.0 57,509 100

  20. EIA - State Nuclear Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Kansas Nuclear Profile 2010 Kansas profile Kansas total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 1,160 9.2 9,556 19.9 Coal 5,179 41.3 32,505 67.8 Hydro and Pumped Storage 3 * 13 * Natural Gas 4,573 36.5 2,287 4.8 Other Renewable1 1,079 8.6 3,459 7.2 Petroleum 550 4.4 103 0.2 Total 12,543 100.0 47,924 100

  1. EIA - State Nuclear Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Maryland Nuclear Profile 2010 Maryland profile Maryland total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (Percent) Nuclear 1,705 13.6 13,994 32.1 Coal 4,886 39.0 23,668 54.3 Hydro and Pumped Storage 590 4.7 1,667 3.8 Natural Gas 2,041 16.3 2,897 6.6 Other 1 152 1.2 485 1.1 Other Renewable1 209 1.7 574 1.3 Petroleum 2,933 23.4 322

  2. Mechanisms Governing the Creep Behavior of High Temperature Alloys for Generation IV Nuclear Energy Systems

    SciTech Connect (OSTI)

    Vasudevan, Vijay; Carroll, Laura; Sham, Sam

    2015-04-06

    This research project, which includes collaborators from INL and ORNL, focuses on the study of alloy 617 and alloy 800H that are candidates for applications as intermediate heat exchangers in GEN IV nuclear reactors, with an emphasis on the effects of grain size, grain boundaries and second phases on the creep properties; the mechanisms of dislocation creep, diffusional creep and cavitation; the onset of tertiary creep; and theoretical modeling for long-term predictions of materials behavior and for high temperature alloy design.

  3. Nuclear Energy Response in the EMF27 Study

    SciTech Connect (OSTI)

    Kim, Son H.; Wada, Kenichi; Kurosawa, Atsushi; Roberts, Matthew

    2014-03-25

    The nuclear energy response for mitigating global climate change across eighteen participating models of the EMF27 study is investigated. Diverse perspectives on the future role of nuclear power in the global energy system are evident in the broad range of nuclear power contributions from participating models of the study. In the Baseline scenario without climate policy, nuclear electricity generation and shares span 0 – 66 EJ/ year and 0 - 25% in 2100 for all models, with a median nuclear electricity generation of 39 EJ/year (1,389 GWe at 90% capacity factor) and median share of 9%. The role of nuclear energy increased under the climate policy scenarios. The median of nuclear energy use across all models doubled in the 450 ppm CO2e scenario with a nuclear electricity generation of 67 EJ/year (2,352 GWe at 90% capacity factor) and share of 17% in 2100. The broad range of nuclear electricity generation (11 – 214 EJ/year) and shares (2 - 38%) in 2100 of the 450 ppm CO2e scenario reflect differences in the technology choice behavior, technology assumptions and competitiveness of low carbon technologies. Greater clarification of nuclear fuel cycle issues and risk factors associated with nuclear energy use are necessary for understanding the nuclear deployment constraints imposed in models and for improving the assessment of the nuclear energy potential in addressing climate change.

  4. Socio-economic impacts of nuclear generating stations: Crystal River Unit 3 case study

    SciTech Connect (OSTI)

    Bergmann, P.A.

    1982-07-01

    This report documents a case study of the socio-economic impacts of the construction and operation of the Crystal River Unit 3 nuclear power station. It is part of a major post-licensing study of the socio-economic impacts at twelve nuclear power stations. The case study covers the period beginning with the announcement of plans to construct the reactor and ending in the period 1980 to 1981. The case study deals with changes in the economy, population, settlement patterns and housing, local government and public services, social structure, and public response in the study area during the construction/operation of the reactor. A regional modeling approach is used to trace the impact of construction/operation on the local economy, labor market, and housing market. Emphasis in the study is on the attribution of socio-economic impacts to the reactor or other causal factors. As part of the study of local public response to the construction/operation of the reactor, the effects of the Three Mile Island accident are examined.

  5. Increasing the Capacity of Existing Power Lines

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

    ... Improved line capacity forecasting The research team continues to validate and refine its weather simulation model to run faster and generate increasingly more accurate results for ...

  6. Ohio Nuclear Profile - All Fuels

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

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","2,134",6.5,"15,805",11.0 "Coal","21,360",64.6,"117,828",82.1 "Hydro and Pumped Storage",101,0.3,429,0.3 "Natural

  7. Pennsylvania Nuclear Profile - All Fuels

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

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","9,540",20.9,"77,828",33.9 "Coal","18,481",40.6,"110,369",48.0 "Hydro and Pumped

  8. Louisiana Nuclear Profile - All Fuels

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

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","2,142",8.0,"18,639",18.1 "Coal","3,417",12.8,"23,924",23.3 "Hydro and Pumped Storage",192,0.7,"1,109",1.1

  9. Maryland Nuclear Profile - All Fuels

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

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","1,705",13.6,"13,994",32.1 "Coal","4,886",39.0,"23,668",54.3 "Hydro and Pumped Storage",590,4.7,"1,667",3.8

  10. Massachusetts Nuclear Profile - All Fuels

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

    total electric power industry, smmer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear",685,5.0,"5,918",13.8 "Coal","1,669",12.2,"8,306",19.4 "Hydro and Pumped Storage","1,942",14.2,659,1.5 "Natural

  11. Michigan Nuclear Profile - All Fuels

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

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy Source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","3,947",13.2,"29,625",26.6 "Coal","11,531",38.7,"65,604",58.8 "Hydro and Pumped Storage","2,109",7.1,228,0.2

  12. Minnesota Nuclear Profile - All Fuels

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

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","1,594",10.8,"13,478",25.1 "Coal","4,789",32.5,"28,083",52.3 "Hydro and Pumped Storage",193,1.3,840,1.6 "Natural

  13. Mississippi Nuclear Profile - All Fuels

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

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","1,251",8.0,"9,643",17.7 "Coal","2,526",16.1,"13,629",25.0 "Natural Gas","11,640",74.2,"29,619",54.4

  14. Nebraska Nuclear Profile - All Fuels

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

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","1,245",15.8,"11,054",30.2 "Coal","3,932",50.0,"23,363",63.8 "Hydro and Pumped Storage",278,3.5,"1,314",3.6

  15. Alabama Nuclear Profile - All Fuels

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

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","5,043",15.6,"37,941",24.9 "Coal","11,441",35.3,"63,050",41.4 "Hydro and Pumped

  16. Arizona Nuclear Profile - All Fuels

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

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (nw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear",3937,14.9,"31,200",27.9 "Coal","6,233",23.6,"43,644",39.1 "Hydro and Pumped Storage","2,937",11.1,"6,831",6.1

  17. Arkansas Nuclear Profile - All Fuels

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

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","1,835",11.5,"15,023",24.6 "Coal","4,535",28.4,"28,152",46.2 "Hydro and Pumped

  18. California Nuclear Profile - All Fuels

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

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","4,390",6.5,"32,201",15.8 "Coal",374,0.6,"2,100",1.0 "Hydro and Pumped Storage","13,954",20.7,"33,260",16.3

  19. Connecticut Nuclear Profile - All Fuels

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

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","2,103",25.4,"16,750",50.2 "Coal",564,6.8,"2,604",7.8 "Hydro and Pumped Storage",151,1.8,400,1.2 "Natural

  20. Florida Nuclear Profile - All Fuels

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

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (nw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","3,924",6.6,"23,936",10.4 "Coal","9,975",16.9,"59,897",26.1 "Hydro and Pumped Storage",55,0.1,177,0.1 "Natural

  1. Georgia Nuclear Profile - All Fuels

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

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","4,061",11.1,"33,512",24.4 "Coal","13,230",36.1,"73,298",53.3 "Hydro and Pumped

  2. Illinois Nuclear Profile - All Fuels

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

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","11,441",25.9,"96,190",47.8 "Coal","15,551",35.2,"93,611",46.5 "Hydro and Pumped Storage",34,0.1,119,0.1 "Natural

  3. Iowa Nuclear Profile - All Fuels

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

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear",601,4.1,"4,451",7.7 "Coal","6,956",47.7,"41,283",71.8 "Hydro and Pumped Storage",144,1.0,948,1.6 "Natural

  4. Kansas Nuclear Profile - All Fuels

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

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","1,160",9.2,"9,556",19.9 "Coal","5,179",41.3,"32,505",67.8 "Hydro and Pumped Storage",3,"*",13,"*"

  5. Vermont Nuclear Profile - All Fuels

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

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear",620,55.0,"4,782",72.2 "Hydro and Pumped Storage",324,28.7,"1,347",20.3 "Natural Gas","-","-",4,0.1 "Other

  6. Virginia Nuclear Profile - All Fuels

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

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","3,501",14.5,"26,572",36.4 "Coal","5,868",24.3,"25,459",34.9 "Hydro and Pumped Storage","4,107",17.0,10,"*"

  7. Wisconsin Nuclear Profile - All Fuels

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

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (nw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","1,584",8.9,"13,281",20.7 "Coal","8,063",45.2,"40,169",62.5 "Hydro and Pumped Storage",492,2.8,"2,112",3.3

  8. Fuzzy Logic Controller Architecture for Water Level Control in Nuclear Power Plant Steam Generator (SG) Using ANFIS Training Method

    SciTech Connect (OSTI)

    Vosoughi, Naser; Naseri, Zahra

    2002-07-01

    Since suitable control of water level can greatly enhance the operation of a power station, a Fuzzy logic controller architecture is applied to show desired control of the water level in a Nuclear steam generator. with regard to the physics of the system, it is shown that two inputs, a single output and the least number of rules (9 rules) are considered for a controller, and the ANFIS training method is employed to model functions in a controlled system. By using ANFIS training method, initial member functions will be trained and appropriate functions are generated to control water level inside the steam generators while using the stated rules. The proposed architecture can construct an input output mapping based on both human knowledge (in from of Fuzzy if then rules) and stipulated input output data. In this paper with a simple test it has been shown that the architecture fuzzy logic controller has a reasonable response to one step input at a constant power. Through computer simulation, it is found that Fuzzy logic controller is suitable, especially for the water level deviation and abrupt steam flow disturbances that are typical in the existing power plant. (authors)

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

    Broader source: Energy.gov [DOE]

    As clean energy increasingly becomes part of the national dialogue, lenders, utilities, and lawmakers need the most comprehensive and accurate information on GHG emissions from various sources of energy to inform policy, planning, and investment decisions. The National Renewable Energy Laboratory (NREL) recently led the Life Cycle Assessment (LCA) Harmonization Project, a study that gives decision makers and investors more precise estimates of life cycle GHG emissions for renewable and conventional generation, clarifying inconsistent and conflicting estimates in the published literature, and reducing uncertainty.

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

    SciTech Connect (OSTI)

    Michael W. Patterson

    2008-05-01

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

  11. Tennessee Nuclear Profile - Sequoyah

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

    Sequoyah" "Unit","Summer Capacity (MW)","Net Generation (Thousand MWh)","Summer Capacity Factor (Percent)","Type","Commercial Operation Date","License Expiration Date" ...

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

    SciTech Connect (OSTI)

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

    2005-06-03

    The overall purpose of this Nuclear Engineering Education Research (NEER) project was to integrate new, innovative, and existing technologies to develop a fault diagnostics and characterization system for nuclear plant steam generators (SG) and heat exchangers (HX). Issues related to system level degradation of SG and HX tubing, including tube fouling, performance under reduced heat transfer area, and the damage caused by stress corrosion cracking, are the important factors that influence overall plant operation, maintenance, and economic viability of nuclear power systems. The research at The University of Tennessee focused on the development of techniques for monitoring process and structural integrity of steam generators and heat exchangers. The objectives of the project were accomplished by the completion of the following tasks. All the objectives were accomplished during the project period. This report summarizes the research and development activities, results, and accomplishments during June 2001 ???????????????????????????????? September 2004. ???????????????????????????????· Development and testing of a high-fidelity nodal model of a U-tube steam generator (UTSG) to simulate the effects of fouling and to generate a database representing normal and degraded process conditions. Application of the group method of data handling (GMDH) method for process variable prediction. ???????????????????????????????· Development of a laboratory test module to simulate particulate fouling of HX tubes and its effect on overall thermal resistance. Application of the GMDH technique to predict HX fluid temperatures, and to compare with the calculated thermal resistance. ???????????????????????????????· Development of a hybrid modeling technique for process diagnosis and its evaluation using laboratory heat exchanger test data. ???????????????????????????????· Development and testing of a sensor suite using piezo-electric devices for monitoring structural integrity of both flat plates (beams) and tubing. Experiments were performed in air, and in water with and without bubbly flow. ???????????????????????????????· Development of advanced signal processing methods using wavelet transforms and image processing techniques for isolating flaw types. ???????????????????????????????· Development and implementation of a new nonlinear and non-stationary signal processing method, called the Hilbert-Huang transform (HHT), for flaw detection and location. This is a more robust and adaptive approach compared to the wavelet transform

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

    SciTech Connect (OSTI)

    Belle R. Upadhyaya; J. Wesley Hines

    2004-09-27

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

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

    SciTech Connect (OSTI)

    Bud'ko, I. O.; Zhukov, A. G.

    2013-11-15

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

  15. 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

  16. nuclear testing | National Nuclear Security Administration

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

    controls Nuclear Verification Challenge: Maintain the U.S. ability to monitor and verify nuclear reduction agreements and detect violations of treaties and other nuclear nonproliferation commitments. Solution: Develop and deploy measures to ensure verifiable compliance with treaties and other international agreements,... International Nuclear Safeguards Challenge: Detect/deter undeclared nuclear materials and activities. Solution: Build capacity of the International Atomic Energy Agency and

  17. FAQs about Storage Capacity

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    about Storage Capacity How do I determine if my tanks are in operation or idle or ... Do I have to report storage capacity every month? No, only report storage capacity with ...

  18. Capacity planning in a transitional economy: What issues? Which models?

    SciTech Connect (OSTI)

    Mubayi, V.; Leigh, R.W.; Bright, R.N.

    1996-03-01

    This paper is devoted to an exploration of the important issues facing the Russian power generation system and its evolution in the foreseeable future and the kinds of modeling approaches that capture those issues. These issues include, for example, (1) trade-offs between investments in upgrading and refurbishment of existing thermal (fossil-fired) capacity and safety enhancements in existing nuclear capacity versus investment in new capacity, (2) trade-offs between investment in completing unfinished (under construction) projects based on their original design versus investment in new capacity with improved design, (3) incorporation of demand-side management options (investments in enhancing end-use efficiency, for example) within the planning framework, (4) consideration of the spatial dimensions of system planning including investments in upgrading electric transmission networks or fuel shipment networks and incorporating hydroelectric generation, (5) incorporation of environmental constraints and (6) assessment of uncertainty and evaluation of downside risk. Models for exploring these issues include low power shutdown (LPS) which are computationally very efficient, though approximate, and can be used to perform extensive sensitivity analyses to more complex models which can provide more detailed answers but are computationally cumbersome and can only deal with limited issues. The paper discusses which models can usefully treat a wide range of issues within the priorities facing decision makers in the Russian power sector and integrate the results with investment decisions in the wider economy.

  19. ISO standardization of scaling factor method for low and intermediate level radioactive wastes generated at nuclear power plants

    SciTech Connect (OSTI)

    Kashiwagi, Makoto; Masui, Hideki; Denda, Yasutaka; James, David; Lantes, Bertrand; Mueller, Wolfgang; Garamszeghy, Mike; Leganes, Jose Luis; Maxeiner, Harald; Van Velzen, Leo

    2007-07-01

    Low- and intermediate-level radioactive wastes (L-ILW ) generated at nuclear power plants are disposed of in various countries. In the disposal of such wastes, it is required that the radioactivity concentrations of waste packages should be declared with respect to difficult-to-measure nuclides (DTM nuclides), such as C-14, Ni-63 and a-emitting nuclides, which are often limited to maximum values in disposal licenses, safety cases and/or regulations for maximum radioactive concentrations. To fulfill this requirement, the Scaling Factor method (SF method) has been applied in various countries as a principal method for determining the concentrations of DTM nuclides. In the SF method, the concentrations of DTM nuclides are determined by multiplying the concentrations of certain key nuclides by SF values (the determined ratios of radioactive concentration between DTM nuclides and those key nuclides). The SF values used as conversion factors are determined from the correlation between DTM nuclides and key nuclides such as Co-60. The concentrations of key nuclides are determined by {gamma} ray measurements which can be made comparatively easily from outside the waste package. The SF values are calculated based on the data obtained from the radiochemical analysis of waste samples. The use of SFs, which are empirically based on analytical data, has become established as a widely recognized 'de facto standard'. A number of countries have independently collected nuclide data by analysis over many years and each has developed its own SF method, but all the SF methods that have been adopted are similar. The project team for standardization had been organized for establishing this SF method as a 'de jure standard' in the international standardization system of the International Organization for Standardization (ISO). The project team for standardization has advanced the standardization through technical studies, based upon each country's study results and analysis data. The conclusions reached by the project team was published as ISO International Standard 21238:2007 'The Scaling Factor method to determine the radioactivity of low- and intermediate-level radioactive waste packages generated at nuclear power plants'. This paper gives an introduction to the international standardization process for the SF method and the contents of the recently published International Standard. (authors)

  20. Property:GeneratingCapacity | Open Energy Information

    Open Energy Info (EERE)

    1000 kW,kWe,KW,kilowatt,KiloWatt,KILOWATT,kilowatts,KiloWatts,KILOWATT,KILOWATTS 1000000 W,We,watt,watts,Watt,Watts,WATT,WATTS 1000000000 mW,milliwatt,milliwatts,MILLIWATT,MILLIWA...

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

    SciTech Connect (OSTI)

    Not Available

    2010-12-01

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

  2. EIA - State Nuclear Profiles

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

    South Carolina profile South Carolina total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 6,486 27.0 51,988 49.9 Coal 7,230 30.1 37,671 36.2 Hydro and Pumped Storage 4,006 16.7 1,442 1.4 Natural Gas 5,308 22.1 10,927 10.5 Other 1 - - 61 0.1 Other Renewable1 284 1.2 1,873 1.8 Petroleum 670 2.8 191 0.2 Total 23,982

  3. EIA - State Nuclear Profiles

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

    Tennessee profile Tennessee total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 3,401 15.9 27,739 33.7 Coal 8,805 41.1 43,670 53.0 Hydro and Pumped Storage 4,277 20.0 7,416 9.0 Natural Gas 4,655 21.7 2,302 2.8 Other 1 - - 16 * Other Renewable1 222 1.0 988 1.2 Petroleum 58 0.3 217 0.3 Total 21,417 100.0 82,349 100.0

  4. EIA - State Nuclear Profiles

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

    Texas profile Texas total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 4,966 4.6 41,335 10.0 Coal 22,335 20.6 150,173 36.5 Hydro and Pumped Storage 689 0.6 1,262 0.3 Natural Gas 69,291 64.0 186,882 45.4 Other 1 477 0.4 3,630 0.9 Other Renewable1 10,295 9.5 27,705 6.7 Petroleum 204 0.2 708 0.2 Total 108,258 100.0

  5. EIA - State Nuclear Profiles

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

    Virginia profile Virginia total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 3,501 14.5 26,572 36.4 Coal 5,868 24.3 25,459 34.9 Hydro and Pumped Storage 4,107 17.0 10 * Natural Gas 7,581 31.4 16,999 23.3 Other 1 - - 414 0.6 Other Renewable1 621 2.6 2,220 3.0 Petroleum 2,432 10.1 1,293 1.8 Total 24,109 100.0 72,966

  6. EIA - State Nuclear Profiles

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

    Washington profile Washington total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 1,097 3.6 9,241 8.9 Coal 1,340 4.4 8,527 8.2 Hydro and Pumped Storage 21,495 70.5 68,342 66.0 Natural Gas 3,828 12.6 10,359 10.0 Other 1 - - 354 0.3 Other Renewable1 2,703 8.9 6,617 6.4 Petroleum 15 * 32 * Total 30,478 100.0 103,473

  7. EIA - State Nuclear Profiles

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

    Wisconsin profile Wisconsin total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 1,584 8.9 13,281 20.7 Coal 8,063 45.2 40,169 62.5 Hydro and Pumped Storage 492 2.8 2,112 3.3 Natural Gas 6,110 34.3 5,497 8.5 Other 1 21 0.1 63 0.1 Other Renewable1 775 4.3 2,474 3.8 Petroleum 790 4.4 718 1.1 Total 17,836 100.0 64,314

  8. EIA - State Nuclear Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Tennessee profile Tennessee total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 3,401 15.9 27,739 33.7 Coal 8,805 41.1 43,670 53.0 Hydro and Pumped Storage 4,277 20.0 7,416 9.0 Natural Gas 4,655 21.7 2,302 2.8 Other 1 - - 16 * Other Renewable1 222 1.0 988 1.2 Petroleum 58 0.3 217 0.3 Total 21,417 100.0 82,349 100.0

  9. EIA - State Nuclear Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Texas profile Texas total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 4,966 4.6 41,335 10.0 Coal 22,335 20.6 150,173 36.5 Hydro and Pumped Storage 689 0.6 1,262 0.3 Natural Gas 69,291 64.0 186,882 45.4 Other 1 477 0.4 3,630 0.9 Other Renewable1 10,295 9.5 27,705 6.7 Petroleum 204 0.2 708 0.2 Total 108,258 100.0

  10. EIA - State Nuclear Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Virginia profile Virginia total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 3,501 14.5 26,572 36.4 Coal 5,868 24.3 25,459 34.9 Hydro and Pumped Storage 4,107 17.0 10 * Natural Gas 7,581 31.4 16,999 23.3 Other 1 - - 414 0.6 Other Renewable1 621 2.6 2,220 3.0 Petroleum 2,432 10.1 1,293 1.8 Total 24,109 100.0 72,966

  11. EIA - State Nuclear Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Washington profile Washington total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 1,097 3.6 9,241 8.9 Coal 1,340 4.4 8,527 8.2 Hydro and Pumped Storage 21,495 70.5 68,342 66.0 Natural Gas 3,828 12.6 10,359 10.0 Other 1 - - 354 0.3 Other Renewable1 2,703 8.9 6,617 6.4 Petroleum 15 * 32 * Total 30,478 100.0 103,473

  12. EIA - State Nuclear Profiles

    Gasoline and Diesel Fuel Update (EIA)

    Wisconsin profile Wisconsin total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 1,584 8.9 13,281 20.7 Coal 8,063 45.2 40,169 62.5 Hydro and Pumped Storage 492 2.8 2,112 3.3 Natural Gas 6,110 34.3 5,497 8.5 Other 1 21 0.1 63 0.1 Other Renewable1 775 4.3 2,474 3.8 Petroleum 790 4.4 718 1.1 Total 17,836 100.0 64,314

  13. Capacity utilization and fuel consumption in the electric power industry, 1970-1981

    SciTech Connect (OSTI)

    Lewis, E.W.

    1982-07-01

    This report updates the 1980 Energy Information Administration (EIA) publication entitled Trends in the Capacity Utilization and Fuel Consumption of Electric Utility Powerplants, 1970-1978, DOE/EIA-184/32. The analysis covers the period from 1970 through 1981, and examines trends during the period prior to the 1973 Arab oil embargo (1970-1973), after the embargo (1974-1977), and during the immediate past (1978-1981). The report also addresses other factors affecting the electric utility industry since the oil embargo: the reduction in foreign oil supplies as a result of the 1979 Iranian crisis, the 1977 drought in the western United States, the 1978 coal strike by the United Mine Workers Union, and the shutdown of nuclear plants in response to the accident at Three Mile Island. Annual data on electric utility generating capacity, net generation, and fuel consumption are provided to identify changes in patterns of power plant capacity utilization and dispatching.

  14. Nuclear Data Links

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

    Control Nuclear Controls Challenge: Detect/deter illicit transfers of nuclear/dual-use materials, technology, and commodities. Solution: Build domestic and international capacity to implement and meet export control obligations. Related Topics international security international security policy NIS nuclear controls safeguards safeguards and security verification Related News Nuclear Verification Nonproliferation International Nuclear Safeguards Nonproliferation Policy Nonproliferation and Arms

  15. Next Generation Nuclear Plant Phenomena Identification and Ranking Tables (PIRTs) Volume 2: Accident and Thermal Fluids Analysis PIRTs

    SciTech Connect (OSTI)

    Ball, Sydney J; Corradini, M.; Fisher, Stephen Eugene; Gauntt, R.; Geffraye, G.; Gehin, Jess C; Hassan, Y.; Moses, David Lewis; Renier, John-Paul; Schultz, R.; Wei, T.

    2008-03-01

    An accident, thermal fluids, and reactor physics phenomena identification and ranking process was conducted by a panel of experts on the next generation nuclear plant (NGNP) design (consideration given to both pebble-bed and prismatic gas-cooled reactor configurations). Safety-relevant phenomena, importance, and knowledge base were assessed for the following event classes: (1) normal operation (including some reactor physics aspects), (2) general loss of forced circulation (G-LOFC), (3) pressurized loss-of-forced circulation (P-LOFC), (4) depressurized loss-of-forced circulation (D-LOFC), (5) air ingress (following D-LOFC), (6) reactivity transients - including anticipated transients without scram (ATWS), (7) processes coupled via intermediate heat exchanger (IHX) (IHX failure with molten salt), and (8) steam/water ingress. The panel's judgment of the importance ranking of a given phenomenon (or process) was based on the effect it had on one or more figures of merit or evaluation criteria. These included public and worker dose, fuel failure, and primary (and other safety) system integrity. The major phenomena of concern that were identified and categorized as high importance combined with medium to low knowledge follow: (1) core coolant bypass flows (normal operation), (2) power/flux profiles (normal operation), (3) outlet plenum flows (normal operation), (4) reactivity-temperature feedback coefficients for high-plutonium-content cores (normal operation and accidents), (5) fission product release related to the transport of silver (normal operation), (6)emissivity aspects for the vessel and reactor cavity cooling system (G-LOFC), (7) reactor vessel cavity air circulation and heat transfer (G-LOFC), and (8)convection/radiation heating of upper vessel area (P-LOFC).

  16. New York Nuclear Profile - All Fuels

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

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","5,271",13.4,"41,870",30.6 "Coal","2,781",7.1,"13,583",9.9 "Hydro and Pumped

  17. North Carolina Nuclear Profile - All Fuels

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

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","4,958",17.9,"40,740",31.7 "Coal","12,766",46.1,"71,951",55.9 "Hydro and Pumped

  18. South Carolina Nuclear Profile - All Fuels

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

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","6,486",27.0,"51,988",49.9 "Coal","7,230",30.1,"37,671",36.2 "Hydro and Pumped

  19. New Hampshire Nuclear Profile - All Fuels

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

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","1,247",29.8,"10,910",49.2 "Coal",546,13.1,"3,083",13.9 "Hydro and Pumped Storage",489,11.7,"1,478",6.7 "Natural

  20. New Jersey Nuclear Profile - All Fuels

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

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","4,108",22.3,"32,771",49.9 "Coal","2,036",11.1,"6,418",9.8 "Hydro and Pumped Storage",404,2.2,-176,-0.3 "Natural

  1. Refinery Capacity Report

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    Storage Capacity at Operable Refineries by PAD District as of January 1, 2006 PDF 9 Shell Storage Capacity at Operable Refineries by PAD District as of January 1, 2006 PDF 10...

  2. ORISE: Capacity Building

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

    Capacity Building Because public health agencies must maintain the resources to respond to public health challenges, critical situations and emergencies, the Oak Ridge Institute for Science and Education (ORISE) helps government agencies and organizations develop a solid infrastructure through capacity building. Capacity building refers to activities that improve an organization's ability to achieve its mission or a person's ability do his or her job more effectively. For organizations, capacity

  3. Table 16. Renewable energy generating capacity and generation

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    ... 0.48 0.48 1.73 1.73 1.73 1.73 1.73 4.7% Solar photovoltaic 5 ... 1.05 2.49 7.90 7.96 8.62 10.33...

  4. Levelized Power Generation Cost Codes

    Energy Science and Technology Software Center (OSTI)

    1996-04-30

    LPGC is a set of nine microcomputer programs for estimating power generation costs for large steam-electric power plants. These programs permit rapid evaluation using various sets of economic and technical ground rules. The levelized power generation costs calculated may be used to compare the relative economics of nuclear and coal-fired plants based on life-cycle costs. Cost calculations include capital investment cost, operation and maintenance cost, fuel cycle cost, decommissioning cost, and total levelized power generationmore » cost. These programs can be used for quick analyses of power generation costs using alternative economic parameters, such as interest rate, escalation rate, inflation rate, plant lead times, capacity factor, fuel prices, etc. The two major types of electric generating plants considered are pressurized water reactor (PWR) and pulverized coal-fired plants. Data are also provided for the Large Scale Prototype Breeder (LSPB) type liquid metal reactor.« less

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

    SciTech Connect (OSTI)

    Corwin, William R; Ballinger, R.; Majumdar, S.; Weaver, K. D.

    2008-03-01

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

  6. Wind Gains ground, hitting 33 GW of installed capacity

    SciTech Connect (OSTI)

    2010-06-15

    The U.S. currently has 33 GW of installed wind capacity. Wind continues to gain ground, accounting for 42 percent of new capacity additions in the US in 2008.Globally, there are now 146 GW of wind capacity with an impressive and sustained growth trajectory that promises to dominate new generation capacities in many developing countries. The U.S., however, lags many European countries, with wind providing roughly 2 percent of electricity generation.

  7. Texas Nuclear Profile - Comanche Peak

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

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

  8. United States-Japan Nuclear Security Working Group | National...

    National Nuclear Security Administration (NNSA)

    Goal 1: Cooperation within the Integrated Support Center for Nuclear Non-proliferation and ... strengthening international capacity in nuclear non-proliferation and nuclear security. ...

  9. United States-Japan Nuclear Security Working Group Fact Sheet...

    National Nuclear Security Administration (NNSA)

    Goal 1: Co-operation within the Integrated Support Centre for Nuclear Non-proliferation ... for strengthening nuclear non-proliferation and nuclear security capacity mainly ...

  10. Refinery Capacity Report

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

    Vacuum State/Refiner/Location Barrels per Atmospheric Crude Oil Distillation Capacity Barrels per Operating Idle Operating Idle Downstream Charge Capacity Thermal Cracking Delayed Fluid Coking Visbreaking Other/Gas Calendar Day Stream Day Distillation Coking Oil Table 3. Capacity of Operable Petroleum Refineries by State as of January 1, 2015 (Barrels per Stream Day, Except Where Noted) ......................................................... Alabama 120,100 0 135,000 0 45,000 32,000 0 0 0

  11. Total Natural Gas Underground Storage Capacity

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

    Storage Capacity Salt Caverns Storage Capacity Aquifers Storage Capacity Depleted Fields Storage Capacity Total Working Gas Capacity Working Gas Capacity of Salt Caverns Working...

  12. Nuclear Regulatory Commission Information Digest 1992 edition. Volume 4

    SciTech Connect (OSTI)

    Olive, K

    1992-03-01

    The Nuclear Regulatory Commission Information Digest provides a summary of information about the US Nuclear Regulatory Commission (NRC), NRC's regulatory responsibilities, the activities NRC licenses, and general information on domestic and worldwide nuclear energy. This digest is a compilation of nuclear- and NRC-related data and is designed to provide a quick reference to major facts about the agency and industry it regulates. In general, the data cover 1975 through 1991, with exceptions noted. Information on generating capacity and average capacity factor for operating US commercial nuclear power reactors is obtained from monthly operating reports that are submitted directly to the NRC by the licensee. This information is reviewed by the NRC for consistency only and no independent validation and/or verification is performed.

  13. Nuclear Regulatory Commission Information Digest 1994 edition. Volume 6

    SciTech Connect (OSTI)

    Stadler, L.

    1994-03-01

    The Nuclear Regulatory Commission Information Digest (digest) provides a summary of information about the US Nuclear Regulatory Commission (NRC), NRCs regulatory responsibility the activities NRC licenses, and general information on domestic and worldwide nuclear energy. The digest, published annually, is a compilation of nuclear-and NRC-related data and is designed to provide a quick reference to major facts about the agency and the industry it regulates. In general, the data cover 1975 through 1993, with exceptions noted. Information on generating capacity and average capacity factor for operating US commercial nuclear power reactors is obtained from monthly operating reports that are submitted directly to the NRC by the information is reviewed by the NRC for consistency only and no independent validation and/or verification is performed.

  14. Representation of the Solar Capacity Value in the ReEDS Capacity Expansion Model: Preprint

    SciTech Connect (OSTI)

    Sigrin, B.; Sullivan, P.; Ibanez, E.; Margolis, R.

    2014-08-01

    An important emerging issue is the estimation of renewables' contributions to reliably meeting system demand, or their capacity value. While the capacity value of thermal generation can be estimated easily, assessment of wind and solar requires a more nuanced approach due to resource variability. Reliability-based methods, particularly, effective load-carrying capacity (ELCC), are considered to be the most robust techniques for addressing this resource variability. The Regional Energy Deployment System (ReEDS) capacity expansion model and other long-term electricity capacity planning models require an approach to estimating CV for generalized PV and system configurations with low computational and data requirements. In this paper we validate treatment of solar photovoltaic (PV) capacity value by ReEDS capacity expansion model by comparing model results to literature for a range of energy penetration levels. Results from the ReEDS model are found to compare well with both comparisons--despite not being resolved at an hourly scale.

  15. Refinery Capacity Report

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

    CORPORATION / Refiner / Location Table 5. Refiners' Total Operable Atmospheric Crude Oil Distillation Capacity as of January 1, 2015 Calendar Day Barrels per CORPORATION / Refiner / Location Calendar Day Barrels per Companies with Capacity Over 100,000 bbl/cd .............................................................................................................................. VALERO ENERGY CORP 1,964,300 Valero Refining Co Texas LP

  16. Variable capacity gasification burner

    SciTech Connect (OSTI)

    Saxon, D.I.

    1985-03-05

    A variable capacity burner that may be used in gasification processes, the burner being adjustable when operating in its intended operating environment to operate at two different flow capacities, with the adjustable parts being dynamically sealed within a statically sealed structural arrangement to prevent dangerous blow-outs of the reactants to the atmosphere.

  17. Liquid heat capacity lasers

    DOE Patents [OSTI]

    Comaskey, Brian J. (Walnut Creek, CA); Scheibner, Karl F. (Tracy, CA); Ault, Earl R. (Livermore, CA)

    2007-05-01

    The heat capacity laser concept is extended to systems in which the heat capacity lasing media is a liquid. The laser active liquid is circulated from a reservoir (where the bulk of the media and hence waste heat resides) through a channel so configured for both optical pumping of the media for gain and for light amplification from the resulting gain.

  18. Knudsen heat capacity

    SciTech Connect (OSTI)

    Babac, Gulru; Reese, Jason M.

    2014-05-15

    We present a Knudsen heat capacity as a more appropriate and useful fluid property in micro/nanoscale gas systems than the constant pressure heat capacity. At these scales, different fluid processes come to the fore that are not normally observed at the macroscale. For thermodynamic analyses that include these Knudsen processes, using the Knudsen heat capacity can be more effective and physical. We calculate this heat capacity theoretically for non-ideal monatomic and diatomic gases, in particular, helium, nitrogen, and hydrogen. The quantum modification for para and ortho hydrogen is also considered. We numerically model the Knudsen heat capacity using molecular dynamics simulations for the considered gases, and compare these results with the theoretical ones.

  19. Refinery Capacity Report

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

    Cokers Catalytic Crackers Hydrocrackers Capacity Inputs Capacity Inputs Capacity Inputs Table 8. Capacity and Fresh Feed Input to Selected Downstream Units at U.S. Refineries, 2013 - 2015 (Barrels per Calendar Day) Reformers Capacity Inputs 2013 2,596,369 5,681,643 1,887,024 2,302,764 4,810,611 1,669,540 2,600,518 3,405,017 74,900 543,800 41,500 47,537 387,148 33,255 PADD I 162,249 240,550 450,093 1,196,952 303,000 414,732 1,028,003 263,238 PADD II 648,603 818,718 1,459,176 2,928,673 981,114

  20. Nuclear reactor characteristics and operational history

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    Nuclear > U.S. reactor operation status tables Nuclear Reactor Operational Status Tables Release date: November 22, 2011 Next release date: TBD See also: Table 1. Capacity and ...

  1. The Future of Energy from Nuclear Fission

    SciTech Connect (OSTI)

    Kim, Son H.; Taiwo, Temitope

    2013-04-13

    Nuclear energy is an important part of our current global energy system, and contributes to supplying the significant demand for electricity for many nations around the world. There are 433 commercial nuclear power reactors operating in 30 countries with an installed capacity of 367 GWe as of October 2011 (IAEA PRIS, 2011). Nuclear electricity generation totaled 2630 TWh in 2010 representing 14% the worlds electricity generation. The top five countries of total installed nuclear capacity are the US, France, Japan, Russia and South Korea at 102, 63, 45, 24, and 21 GWe, respectively (WNA, 2012a). The nuclear capacity of these five countries represents more than half, 68%, of the total global nuclear capacity. The role of nuclear power in the global energy system today has been motivated by several factors including the growing demand for electric power, the regional availability of fossil resources and energy security concerns, and the relative competitiveness of nuclear power as a source of base-load electricity. There is additional motivation for the use of nuclear power because it does not produce greenhouse gas (GHG) emissions or local air pollutants during its operation and contributes to low levels of emissions throughout the lifecycle of the nuclear energy system (Beerten, J. et. al., 2009). Energy from nuclear fission primarily in the form of electric power and potentially as a source of industrial heat could play a greater role for meeting the long-term growing demand for energy worldwide while addressing the concern for climate change from rising GHG emissions. However, the nature of nuclear fission as a tremendously compact and dense form of energy production with associated high concentrations of radioactive materials has particular and unique challenges as well as benefits. These challenges include not only the safety and cost of nuclear reactors, but proliferation concerns, safeguard and storage of nuclear materials associated with nuclear fuel cycles. In March of 2011, an unprecedented earthquake of 9 magnitude and ensuing tsunami off the east coast of Japan caused a severe nuclear accident in Fukushima, Japan (Prime Minister of Japan and His Cabinet, 2011). The severity of the nuclear accident in Japan has brought about a reinvestigation of nuclear energy policy and deployment activities for many nations around the world, most notably in Japan and Germany (BBC, 2011; Reuter, 2011). The response to the accident has been mixed and its full impact may not be realized for many years to come. The nuclear accident in Fukushima, Japan has not directly affected the significant on-going nuclear deployment activities in many countries. China, Russia, India, and South Korea, as well as others, are continuing with their deployment plans. As of October 2011, China had the most reactors under construction at 27, while Russia, India, and South Korea had 11, 6, and 5 reactors under construction, respectively (IAEA PRIS, 2011). Ten other nations have one or two reactors currently under construction. Many more reactors are planned for future deployment in China, Russia, and India, as well as in the US. Based on the World Nuclear Associations data, the realization of Chinas deployment plan implies that China will surpass the US in total nuclear capacity some time in the future.

  2. An interactive ontology-driven information system for simulating background radiation and generating scenarios for testing special nuclear materials detection algorithms

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

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

    2015-01-01

    This paper describes an original approach to generating scenarios for the purpose of testing the algorithms used to detect special nuclear materials (SNM) that incorporates the use of ontologies. Separating the signal of SNM from the background requires sophisticated algorithms. To assist in developing such algorithms, there is a need for scenarios that capture a very wide range of variables affecting the detection process, depending on the type of detector being used. To provide such a cpability, we developed an ontology-driven information system (ODIS) for generating scenarios that can be used in creating scenarios for testing of algorithms for SNMmore » detection. The ontology-driven scenario generator (ODSG) is an ODIS based on information supplied by subject matter experts and other documentation. The details of the creation of the ontology, the development of the ontology-driven information system, and the design of the web user interface (UI) are presented along with specific examples of scenarios generated using the ODSG. We demonstrate that the paradigm behind the ODSG is capable of addressing the problem of semantic complexity at both the user and developer levels. Compared to traditional approaches, an ODIS provides benefits such as faithful representation of the users' domain conceptualization, simplified management of very large and semantically diverse datasets, and the ability to handle frequent changes to the application and the UI. The approach makes possible the generation of a much larger number of specific scenarios based on limited user-supplied information« less

  3. Tsiklauri-Durst combined cycle (T-D Cycle{trademark}) application for nuclear and fossil-fueled power generating plants

    SciTech Connect (OSTI)

    Tsiklauri, B.; Korolev, V.N.; Durst, B.M.; Shen, P.K.

    1998-07-01

    The Tsiklauri-Durst combined cycle is a combination of the best attributes of both nuclear power and combined cycle gas power plants. A technology patented in 1994 by Battelle Memorial Institute offers a synergistic approach to power generation. A typical combined cycle is defined as the combination of gas turbine Brayton Cycle, topping steam turbine Rankine Cycle. Exhaust from the gas turbine is used in heat recovery steam generators to produce steam for a steam turbine. In a standard combined cycle gas turbine-steam turbine application, the gas turbine generates about 65 to 70 percent of system power. The thermal efficiency for such an installation is typically about 45 to 50 percent. A T-D combined cycle takes a new, creative approach to combined cycle design by directly mixing high enthalpy steam from the heat recovery steam generator, involving the steam generator at more than one pressure. Direct mixing of superheated and saturated steam eliminates the requirement for a large heat exchanger, making plant modification simple and economical.

  4. An interactive ontology-driven information system for simulating background radiation and generating scenarios for testing special nuclear materials detection algorithms

    SciTech Connect (OSTI)

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

    2015-01-01

    This paper describes an original approach to generating scenarios for the purpose of testing the algorithms used to detect special nuclear materials (SNM) that incorporates the use of ontologies. Separating the signal of SNM from the background requires sophisticated algorithms. To assist in developing such algorithms, there is a need for scenarios that capture a very wide range of variables affecting the detection process, depending on the type of detector being used. To provide such a cpability, we developed an ontology-driven information system (ODIS) for generating scenarios that can be used in creating scenarios for testing of algorithms for SNM detection. The ontology-driven scenario generator (ODSG) is an ODIS based on information supplied by subject matter experts and other documentation. The details of the creation of the ontology, the development of the ontology-driven information system, and the design of the web user interface (UI) are presented along with specific examples of scenarios generated using the ODSG. We demonstrate that the paradigm behind the ODSG is capable of addressing the problem of semantic complexity at both the user and developer levels. Compared to traditional approaches, an ODIS provides benefits such as faithful representation of the users' domain conceptualization, simplified management of very large and semantically diverse datasets, and the ability to handle frequent changes to the application and the UI. The approach makes possible the generation of a much larger number of specific scenarios based on limited user-supplied information

  5. International Nuclear Safeguards | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    International Nuclear Safeguards Challenge: Detect/deter undeclared nuclear materials and activities. Solution: Build capacity of the International Atomic Energy Agency and Member States to implement and meet safeguards obligations. The Office of International Nuclear Safeguards develops and supports the policies, concepts, technologies, expertise, and international safeguards infrastructure necessary to strengthen and sustain the international safeguards system as it evolves to meet new

  6. Nuclear Regulatory Commission Information Digest, 1991 edition

    SciTech Connect (OSTI)

    Olive, K L

    1991-03-01

    The Nuclear Regulatory Commission Information Digest provides a summary of information about the US Nuclear Regulatory Commission (NRC), NRC's regulatory responsibilities, and the areas NRC licenses. This digest is a compilation of NRC-related data and is designed to provide a quick reference to major facts about the agency and the industry it regulates. In general, the data cover 1975 through 1990, with exceptions noted. For operating US commercial nuclear power reactors, information on generating capacity and average capacity factor is obtained from Monthly Operating Reports submitted to the NRC directly by the licensee. This information is reviewed for consistency only. No independent validation and/or verification is performed by the NRC. For detailed and complete information about tables and figures, refer to the source publications. This digest is published annually for the general use of the NRC staff and is available to the public. 30 figs., 12 tabs.

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

    SciTech Connect (OSTI)

    1993-12-31

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

  8. Low-level radioactive waste from nuclear power generating stations: Characterization, classification and assessment of activated metals and waste streams

    SciTech Connect (OSTI)

    Thomas, V.W.; Robertson, D.E.; Thomas, C.W.

    1993-02-01

    Since the enactment of 10 CFR Part 61, additional difficult-to-measure long-lived radionuclides, not specified in Tables 1 2 of Part 61, have been identified (e.g., {sup 108m}Ag, {sup 93}Mo, {sup 36}Cl, {sup 10}Be, {sup 113m}Cd, {sup 121m}Sn, {sup 126}Sn, {sup 93m}Nb) that may be of concern in certain types of waste. These nuclides are primarily associated with activated metal and perhaps other nuclear power low-level waste (LLW) being sent to disposal facilities. The concentration of a radionuclide in waste materials is normally determined by direct measurement or by indirect calculational methods, such as using a scaling factor to relate inferred concentration of a difficult-to-measure radionuclide to another that is easily measured. The total disposal site inventory of certain difficult-to-measure radionuclides (e.g., {sup 14}C, {sup 129}I, and {sup 99}Tc) often control the total quantities of radioactive waste permitted in LLW burial facilities. Overly conservative scaling factors based on lower limits of detection (LLD), often used in the nuclear power industry to estimate these controlling nuclides, could lead to premature closure of a disposal facility. Samples of LLW (Class B and C activated metals [AM] and other waste streams) are being collected from operating nuclear power stations and analyzed for radionuclides covered in 10 CFR Part 61 and the additional difficult-to-measure radionuclides. This analysis will enhance the NRC`s understanding of the distribution and projected quantities of radionuclides within AM and LLW streams from commercial nuclear power stations. This research will also provide radiological characterization of AM specimens for others to use in leach-rate and lysimeter experiments to determine nuclide releases and subsequent movement in natural soil environments.

  9. Low-level radioactive waste from nuclear power generating stations: Characterization, classification and assessment of activated metals and waste streams

    SciTech Connect (OSTI)

    Thomas, V.W.; Robertson, D.E.; Thomas, C.W.

    1993-02-01

    Since the enactment of 10 CFR Part 61, additional difficult-to-measure long-lived radionuclides, not specified in Tables 1 2 of Part 61, have been identified (e.g., [sup 108m]Ag, [sup 93]Mo, [sup 36]Cl, [sup 10]Be, [sup 113m]Cd, [sup 121m]Sn, [sup 126]Sn, [sup 93m]Nb) that may be of concern in certain types of waste. These nuclides are primarily associated with activated metal and perhaps other nuclear power low-level waste (LLW) being sent to disposal facilities. The concentration of a radionuclide in waste materials is normally determined by direct measurement or by indirect calculational methods, such as using a scaling factor to relate inferred concentration of a difficult-to-measure radionuclide to another that is easily measured. The total disposal site inventory of certain difficult-to-measure radionuclides (e.g., [sup 14]C, [sup 129]I, and [sup 99]Tc) often control the total quantities of radioactive waste permitted in LLW burial facilities. Overly conservative scaling factors based on lower limits of detection (LLD), often used in the nuclear power industry to estimate these controlling nuclides, could lead to premature closure of a disposal facility. Samples of LLW (Class B and C activated metals [AM] and other waste streams) are being collected from operating nuclear power stations and analyzed for radionuclides covered in 10 CFR Part 61 and the additional difficult-to-measure radionuclides. This analysis will enhance the NRC's understanding of the distribution and projected quantities of radionuclides within AM and LLW streams from commercial nuclear power stations. This research will also provide radiological characterization of AM specimens for others to use in leach-rate and lysimeter experiments to determine nuclide releases and subsequent movement in natural soil environments.

  10. Emerging nuclear programs in Asia: The Phillipines, Thailand, Indonesia, and Pakistan

    SciTech Connect (OSTI)

    Williams, M.L.

    1993-12-01

    This article is a review of the potential for nuclear energy development in the developing nations of Pakistan, Indonesia, Thailand, and the Philippines. In each country, there is a substantial need for new generating capacity, and each is exploring the idea of having nuclear energy supply a meaningful portion of this new capacity. Of the four countries, only Pakistan is currently a nuclear operator, and one vintage CANDU plant in operation and the Chashma unit under construction. Thailand and Indonesia have ambitious plans to have 12 reactors in service by the year 2015.

  11. Missouri Nuclear Profile - All Fuels

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

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary energy source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","1,190",5.5,"8,996",9.7 "Coal","12,070",55.5,"75,047",81.3 "Hydro and Pumped Storage","1,221",5.6,"2,427",2.6

  12. Washington Nuclear Profile - All Fuels

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

    total electric power industry, summer capacity and net generation, by energy source, 2010" "Primary Energy Source","Summer capacity (mw)","Share of State total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","1,097",3.6,"9,241",8.9 "Coal","1,340",4.4,"8,527",8.2 "Hydro and Pumped Storage","21,495",70.5,"68,342",66.0

  13. WINDExchange: Potential Wind Capacity

    Wind Powering America (EERE)

    Potential Wind Capacity Potential wind capacity maps are provided for a 2014 industry standard wind turbine installed on a 110-m tower, which represents plausible current technology options, and a wind turbine on a 140-m tower, which represents near-future technology options. Enlarge image This map shows the wind potential at a 110-m height for the United States. Download a printable map. Click on a state to view the wind map for that state. * Grid Granularity = 400 sq km* 35% Gross Capacity

  14. Development of low-level radioactive waste disposal capacity in the United States - progress or stalemate?

    SciTech Connect (OSTI)

    Devgun, J.S. [Argonne National Lab., IL (United States); Larson, G.S. [Midwest Low-Level Radioactive Waste Commission, St. Paul, MN (United States)

    1995-12-31

    It has been fifteen years since responsibility for the disposal of commercially generated low-level radioactive waste (LLW) was shifted to the states by the United States Congress through the Low-Level Radioactive Waste Policy Act of 1980 (LLRWPA). In December 1985, Congress revisited the issue and enacted the Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA). No new disposal sites have opened yet, however, and it is now evident that disposal facility development is more complex, time-consuming, and controversial than originally anticipated. For a nation with a large nuclear power industry, the lack of availability of LLW disposal capacity coupled with a similar lack of high-level radioactive waste disposal capacity could adversely affect the future viability of the nuclear energy option. The U.S. nuclear power industry, with 109 operating reactors, generates about half of the LLW shipped to commercial disposal sites and faces dwindling access to waste disposal sites and escalating waste management costs. The other producers of LLW - industries, government (except the defense related research and production waste), academic institutions, and medical institutions that account for the remaining half of the commercial LLW - face the same storage and cost uncertainties. This paper will summarize the current status of U.S. low-level radioactive waste generation and the status of new disposal facility development efforts by the states. The paper will also examine the factors that have contributed to delays, the most frequently suggested alternatives, and the likelihood of change.

  15. Nuclear | Department of Energy

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

    Nuclear Nuclear Radioisotope Power Systems, a strong partnership between the Energy Department's Office of Nuclear Energy and NASA, has been providing the energy for deep space exploration. Nuclear power is the use of sustained nuclear fission to generate heat and electricity. Nuclear power plants provide about 6 percent of the world's energy and 13-14 percent of the world's electricity. Featured Moving Forward to Address Nuclear Waste Storage and Disposal Three trucks transport nuclear waste

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

    SciTech Connect (OSTI)

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

    2014-07-01

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

  17. Refinery Capacity Report

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

    Refinery Capacity Report With Data as of January 1, 2015 | Release Date: June 19, 2015 | Next Release Date: June 24, 2016 Previous Issues Year: 2015 2014 2013 2012 2011 2010 2009 2008 2007 2006 prior issues Go Data series include fuel, electricity, and steam purchased for consumption at the refinery; refinery receipts of crude oil by method of transportation; and current and projected atmospheric crude oil distillation, downstream charge, and production capacities. Respondents are operators of

  18. Forward capacity market CONEfusion

    SciTech Connect (OSTI)

    Wilson, James F.

    2010-11-15

    In ISO New England and PJM it was assumed that sponsors of new capacity projects would offer them into the newly established forward centralized capacity markets at prices based on their levelized net cost of new entry, or ''Net CONE.'' But the FCCMs have not operated in the way their proponents had expected. To clear up the CONEfusion, FCCM designs should be reconsidered to adapt them to the changing circumstances and to be grounded in realistic expectations of market conduct. (author)

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

    SciTech Connect (OSTI)

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

    2003-12-01

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

  20. verification | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    verification Nuclear Verification Challenge: Maintain the U.S. ability to monitor and verify nuclear reduction agreements and detect violations of treaties and other nuclear nonproliferation commitments. Solution: Develop and deploy measures to ensure verifiable compliance with treaties and other international agreements,... International Nuclear Safeguards Challenge: Detect/deter undeclared nuclear materials and activities. Solution: Build capacity of the International Atomic Energy Agency and

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

    SciTech Connect (OSTI)

    Nagy, Peter

    2013-09-30

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

  2. State Nuclear Profiles 2010

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

    5 Iowa Iowa total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 601 4.1 4,451 7.7 Coal 6,956 47.7 41,283 71.8 Hydro and Pumped Storage 144 1.0 948 1.6 Natural Gas 2,299 15.8 1,312 2.3 Other Renewable 1 3,584 24.6 9,360 16.3 Petroleum 1,007 6.9 154 0.3 Total 14,592 100.0 57,509 100.0 Source: Form EIA-860, "Annual Electric Generator Report," and Form EIA-923, "Power Plant Operations Report." Share of State total (percent) 1

  3. State Nuclear Profiles 2010

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

    20 Kansas Kansas total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 1,160 9.2 9,556 19.9 Coal 5,179 41.3 32,505 67.8 Hydro and Pumped Storage 3 * 13 * Natural Gas 4,573 36.5 2,287 4.8 Other Renewable 1 1,079 8.6 3,459 7.2 Petroleum 550 4.4 103 0.2 Total 12,543 100.0 47,924 100.0 * = Absolute percentage less than 0.05. Source: Form EIA-860, "Annual Electric Generator Report," and Form EIA-923, "Power Plant Operations Report."

  4. State Nuclear Profiles 2010

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

    7 Nebraska Nebraska total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 1,245 15.8 11,054 30.2 Coal 3,932 50.0 23,363 63.8 Hydro and Pumped Storage 278 3.5 1,314 3.6 Natural Gas 1,849 23.5 375 1.0 Other Renewable 1 165 2.1 493 1.3 Petroleum 387 4.9 31 0.1 Total 7,857 100.0 36,630 100.0 Source: Form EIA-860, "Annual Electric Generator Report," and Form EIA-923, "Power Plant Operations Report." Share of State total (percent) 1

  5. State Nuclear Profiles 2010

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

    60 Vermont Vermont total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 620 55.0 4,782 72.2 Hydro and Pumped Storage 324 28.7 1,347 20.3 Natural Gas - - 4 0.1 Other Renewable 1 84 7.5 482 7.3 Petroleum 100 8.9 5 0.1 Total 1,128 100.0 6,620 100.0 - = No data reported. Source: Form EIA-860, "Annual Electric Generator Report," and Form EIA-923, "Power Plant Operations Report." Share of State total (percent) 1 Municipal Solid Waste net

  6. State Nuclear Profiles 2010

    Gasoline and Diesel Fuel Update (EIA)

    5 Iowa Iowa total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 601 4.1 4,451 7.7 Coal 6,956 47.7 41,283 71.8 Hydro and Pumped Storage 144 1.0 948 1.6 Natural Gas 2,299 15.8 1,312 2.3 Other Renewable 1 3,584 24.6 9,360 16.3 Petroleum 1,007 6.9 154 0.3 Total 14,592 100.0 57,509 100.0 Source: Form EIA-860, "Annual Electric Generator Report," and Form EIA-923, "Power Plant Operations Report." Share of State total (percent) 1

  7. State Nuclear Profiles 2010

    Gasoline and Diesel Fuel Update (EIA)

    20 Kansas Kansas total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 1,160 9.2 9,556 19.9 Coal 5,179 41.3 32,505 67.8 Hydro and Pumped Storage 3 * 13 * Natural Gas 4,573 36.5 2,287 4.8 Other Renewable 1 1,079 8.6 3,459 7.2 Petroleum 550 4.4 103 0.2 Total 12,543 100.0 47,924 100.0 * = Absolute percentage less than 0.05. Source: Form EIA-860, "Annual Electric Generator Report," and Form EIA-923, "Power Plant Operations Report."

  8. State Nuclear Profiles 2010

    Gasoline and Diesel Fuel Update (EIA)

    7 Nebraska Nebraska total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 1,245 15.8 11,054 30.2 Coal 3,932 50.0 23,363 63.8 Hydro and Pumped Storage 278 3.5 1,314 3.6 Natural Gas 1,849 23.5 375 1.0 Other Renewable 1 165 2.1 493 1.3 Petroleum 387 4.9 31 0.1 Total 7,857 100.0 36,630 100.0 Source: Form EIA-860, "Annual Electric Generator Report," and Form EIA-923, "Power Plant Operations Report." Share of State total (percent) 1

  9. State Nuclear Profiles 2010

    Gasoline and Diesel Fuel Update (EIA)

    60 Vermont Vermont total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 620 55.0 4,782 72.2 Hydro and Pumped Storage 324 28.7 1,347 20.3 Natural Gas - - 4 0.1 Other Renewable 1 84 7.5 482 7.3 Petroleum 100 8.9 5 0.1 Total 1,128 100.0 6,620 100.0 - = No data reported. Source: Form EIA-860, "Annual Electric Generator Report," and Form EIA-923, "Power Plant Operations Report." Share of State total (percent) 1 Municipal Solid Waste net

  10. Next Generation Nuclear Plant Project Technology Development Roadmaps: The Technical Path Forward for 750800C Reactor Outlet Temperature

    SciTech Connect (OSTI)

    John Collins

    2009-08-01

    This document presents the NGNP Critical PASSCs and defines their technical maturation path through Technology Development Roadmaps (TDRMs) and their associated Technology Readiness Levels (TRLs). As the critical PASSCs advance through increasing levels of technical maturity, project risk is reduced and the likelihood of within-budget and on-schedule completion is enhanced. The current supplier-generated TRLs and TDRMs for a 750800C reactor outlet temperature (ROT) specific to each supplier are collected in Appendix A.

  11. Dual capacity reciprocating compressor

    DOE Patents [OSTI]

    Wolfe, R.W.

    1984-10-30

    A multi-cylinder compressor particularly useful in connection with northern climate heat pumps and in which different capacities are available in accordance with reversing motor rotation is provided with an eccentric cam on a crank pin under a fraction of the connecting rods, and arranged for rotation upon the crank pin between opposite positions 180[degree] apart so that with cam rotation on the crank pin such that the crank throw is at its normal maximum value all pistons pump at full capacity, and with rotation of the crank shaft in the opposite direction the cam moves to a circumferential position on the crank pin such that the overall crank throw is zero. Pistons whose connecting rods ride on a crank pin without a cam pump their normal rate with either crank rotational direction. Thus a small clearance volume is provided for any piston that moves when in either capacity mode of operation. 6 figs.

  12. Dual capacity reciprocating compressor

    DOE Patents [OSTI]

    Wolfe, Robert W.

    1984-01-01

    A multi-cylinder compressor 10 particularly useful in connection with northern climate heat pumps and in which different capacities are available in accordance with reversing motor 16 rotation is provided with an eccentric cam 38 on a crank pin 34 under a fraction of the connecting rods, and arranged for rotation upon the crank pin between opposite positions 180.degree. apart so that with cam rotation on the crank pin such that the crank throw is at its normal maximum value all pistons pump at full capacity, and with rotation of the crank shaft in the opposite direction the cam moves to a circumferential position on the crank pin such that the overall crank throw is zero. Pistons 24 whose connecting rods 30 ride on a crank pin 36 without a cam pump their normal rate with either crank rotational direction. Thus a small clearance volume is provided for any piston that moves when in either capacity mode of operation.

  13. Geothermal Plant Capacity Factors

    SciTech Connect (OSTI)

    Greg Mines; Jay Nathwani; Christopher Richard; Hillary Hanson; Rachel Wood

    2015-01-01

    The capacity factors recently provided by the Energy Information Administration (EIA) indicated this plant performance metric had declined for geothermal power plants since 2008. Though capacity factor is a term commonly used by geothermal stakeholders to express the ability of a plant to produce power, it is a term frequently misunderstood and in some instances incorrectly used. In this paper we discuss how this capacity factor is defined and utilized by the EIA, including discussion on the information that the EIA requests from operations in their 923 and 860 forms that are submitted both monthly and annually by geothermal operators. A discussion is also provided regarding the entities utilizing the information in the EIA reports, and how those entities can misinterpret the data being supplied by the operators. The intent of the paper is to inform the facility operators as the importance of the accuracy of the data that they provide, and the implications of not providing the correct information.

  14. NNSA: Working to Prevent Nuclear Proliferation | National Nuclear...

    National Nuclear Security Administration (NNSA)

    NNSA: Working to Prevent Nuclear Proliferation February 01, 2011 NNSA's Office of ... systems of control and building regional capacity to detect and deter proliferation. ...

  15. Experimental investigation on the chemical precipitation generation under the loss of coolant accident of nuclear power plants

    SciTech Connect (OSTI)

    Kim, C. H.; Sung, J. J.; Chung, Y. W.

    2012-07-01

    The PWR containment buildings are designed to facilitate core cooling in the event of a Loss of Coolant Accident (LOCA). The cooling process requires water discharged from the break and containment spray to be collected in a sump for recirculation. The containment sump contains screens to protect the components of the Emergency Core Cooling System (ECCS) and Containment Spray System (CSS) from debris. Since the containment materials may dissolve or corrode when exposed to the reactor coolant and spray solutions, various chemical precipitations can be generated in a post-LOCA environment. These chemical precipitations may become another source of debris loading to be considered in sump screen performance and downstream effects. In this study, new experimental methodology to predict the type and quantity of chemical precipitations has been developed. To generate the plant-specific chemical precipitation in a post-LOCA environment, the plant specific chemical condition of the recirculation sump during post-LOCA is simulated with the experimental reactor for the chemical effect. The plant-specific containment materials are used in the present experiment such as glass fibers, concrete blocks, aluminum specimens, and chemical reagent - boric acid, spray additives or buffering chemicals (sodium hydroxide, Tri-Sodium Phosphate (TSP), or others). The inside temperature of the reactor is controlled to simulate the plant-specific temperature profile of the recirculation sump. The total amount of aluminum released from aluminum specimens is evaluated by ICP-AES analysis to determine the amount of AlOOH and NaAlSi{sub 3}O{sub 8} which induce very adverse effect on the head loss across the sump screens. The amount of these precipitations generated in the present experimental study is compared with the results of WCAP-16530-NP-A. (authors)

  16. Refinery Capacity Report

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

    District and State Production Capacity Alkylates Aromatics Asphalt and Road Oil Isomers Lubricants Marketable Petroleum Coke Sulfur (short tons/day) Hydrogen (MMcfd) Table 2. Production Capacity of Operable Petroleum Refineries by PAD District and State as of January 1, 2015 (Barrels per Stream Day, Except Where Noted) a 83,429 10,111 26,500 87,665 21,045 21,120 69 1,159 PAD District I Delaware 11,729 5,191 0 6,000 0 13,620 40 596 New Jersey 29,200 0 65,000 4,000 12,000 7,500 26 280 Pennsylvania

  17. Refinery Capacity Report

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

    Distillation Crude Oil Atmospheric Distillation Vacuum Cracking Thermal Catalytic Cracking Fresh Recycled Catalytic Hydro- Cracking Catalytic Reforming Desulfurization Hydrotreating/ Fuels Solvent Deasphalting Downstream Charge Capacity Table 6. Operable Crude Oil and Downstream Charge Capacity of Petroleum Refineries, January 1, 1986 to (Thousand Barrels per Stream Day, Except Where Noted) January 1, 2015 JAN 1, 1986 16,346 6,892 1,880 5,214 463 1,125 3,744 8,791 NA JAN 1, 1987 16,460 6,935

  18. Refinery Capacity Report

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

    Alkylates Aromatics Road Oil and Lubricants Petroleum Coke (MMcfd) Hydrogen Sulfur (short tons/day) Production Capacity Asphalt Isomers Marketable Table 7. Operable Production Capacity of Petroleum Refineries, January 1, 1986 to January 1, 2015 (Thousand Barrels per Stream Day, Except Where Noted) a JAN 1, 1986 941 276 804 258 246 356 2,357 NA JAN 1, 1987 974 287 788 326 250 364 2,569 23,806 JAN 1, 1988 993 289 788 465 232 368 2,418 27,639 JAN 1, 1989 1,015 290 823 469 230 333 2,501 28,369 JAN

  19. Exelôn. Generation

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

    Exeln. Generation 4300 Winfield Road Warrenville, Illinois 60555 Writer's Direct Dial: ... On March 14, 2011, representatives of Exelon Generation Company, LLC and Exelon Nuclear ...

  20. A preliminary user-friendly, digital console for the control room parameters supervision in old-generation Nuclear Plants

    SciTech Connect (OSTI)

    Memmi, F.; Falconi, L.; Cappelli, M.; Palomba, M.; Santoro, E.; Bove, R.; Sepielli, M.

    2012-07-01

    Improvements in the awareness of a system status is an essential requirement to achieve safety in every kind of plant. In particular, in the case of Nuclear Power Plants (NPPs), a progress is crucial to enhance the Human Machine Interface (HMI) in order to optimize monitoring and analyzing processes of NPP operational states. Firstly, as old-fashioned plants are concerned, an upgrading of the whole console instrumentation is desirable in order to replace an analog visualization with a full-digital system. In this work, we present a novel instrument able to interface the control console of a nuclear reactor, developed by using CompactRio, a National Instruments embedded architecture and its dedicated programming language. This real-time industrial controller composed by a real-time processor and FPGA modules has been programmed to visualize the parameters coming from the reactor, and to storage and reproduce significant conditions anytime. This choice has been made on the basis of the FPGA properties: high reliability, determinism, true parallelism and re-configurability, achieved by a simple programming method, based on LabVIEW real-time environment. The system architecture exploits the FPGA capabilities of implementing custom timing and triggering, hardware-based analysis and co-processing, and highest performance control algorithms. Data stored during the supervisory phase can be reproduced by loading data from a measurement file, re-enacting worthwhile operations or conditions. The system has been thought to be used in three different modes, namely Log File Mode, Supervisory Mode and Simulation Mode. The proposed system can be considered as a first step to develop a more complete Decision Support System (DSS): indeed this work is part of a wider project that includes the elaboration of intelligent agents and meta-theory approaches. A synoptic has been created to monitor every kind of action on the plant through an intuitive sight. Furthermore, another important aim of this work is the possibility to have a front panel available on a web interface: CompactRio acts as a remote server and it is accessible on a dedicated LAN. This supervisory system has been tested and validated on the basis of the real control console for the 1-MW TRIGA reactor RC-1 at the ENEA, Casaccia Research Center. In this paper we show some results obtained by recording each variable as the reactor reaches its maximum level of power. The choice of a research reactor for testing the developed system relies on its training and didactic importance for the education of plant operators: in this context a digital instrument can offer a better user-friendly tool for learning and training. It is worthwhile to remark that such a system does not interfere with the console instrumentation, the latter continuing to preserve the total control. (authors)

  1. Texas Nuclear Profile - South Texas Project

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

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

  2. Acceptance Priority Ranking & Annual Capacity Report

    SciTech Connect (OSTI)

    2004-07-31

    The Nuclear Waste Policy Act of 1982, as amended (the Act), assigns the Federal Government the responsibility for the disposal of spent nuclear fuel and high-level waste. Section 302(a) of the Act authorizes the Secretary to enter into contracts with the owners and generators of commercial spent nuclear fuel and/or high-level waste. The Standard Contract for Disposal of Spent Nuclear Fuel and/or High-Level Radioactive Waste (Standard Contract) established the contractual mechanism for the Department's acceptance and disposal of spent nuclear fuel and high-level waste. It includes the requirements and operational responsibilities of the parties to the Standard Contract in the areas of administrative matters, fees, terms of payment, waste acceptance criteria, and waste acceptance procedures. The Standard Contract provides for the acquisition of title to the spent nuclear fuel and/or high-level waste by the Department, its transportation to Federal facilities, and its subsequent disposal.

  3. REGULATORY STRATEGIES TO MINIMIZE GENERATION OF REGULATED WASTES FROM CLEANUP, CONTINUED USE OR DECOMMISSIONING OF NUCLEAR FACILITIES CONTAMINATED WITH POLYCHLORINATED BIPHENYLS (PCBS) - 11198

    SciTech Connect (OSTI)

    Lowry, N.

    2010-11-05

    Disposal costs for liquid PCB radioactive waste are among the highest of any category of regulated waste. The high cost is driven by the fact that disposal options are extremely limited. Toxic Substances Control Act (TSCA) regulations require most liquids with PCBs at concentration of {ge} 50 parts-per-million to be disposed by incineration or equivalent destructive treatment. Disposal fees can be as high as $200 per gallon. This figure does not include packaging and the cost to transport the waste to the disposal facility, or the waste generator's labor costs for managing the waste prior to shipment. Minimizing the generation of liquid radioactive PCB waste is therefore a significant waste management challenge. PCB spill cleanups often generate large volumes of waste. That is because the removal of PCBs typically requires the liberal use of industrial solvents followed by a thorough rinsing process. In a nuclear facility, the cleanup process may be complicated by the presence of radiation and other occupational hazards. Building design and construction features, e.g., the presence of open grating or trenches, may also complicate cleanup. In addition to the technical challenges associated with spill cleanup, selection of the appropriate regulatory requirements and approach may be challenging. The TSCA regulations include three different sections relating to the cleanup of PCB contamination or spills. EPA has also promulgated a separate guidance policy for fresh PCB spills that is published as Subpart G of 40 CFR 761 although it is not an actual regulation. Applicability is based on the circumstances of each contamination event or situation. Other laws or regulations may also apply. Identification of the allowable regulatory options is important. Effective communication with stakeholders, particularly regulators, is just as important. Depending on the regulatory path that is taken, cleanup may necessitate the generation of large quantities of regulated waste. Allowable options must be evaluated carefully in order to reduce compliance risks, protect personnel, limit potential negative impacts on facility operations, and minimize the generation of wastes subject to TSCA. This paper will identify critical factors in selecting the appropriate TSCA regulatory path in order to minimize the generation of radioactive PCB waste and reduce negative impacts to facilities. The importance of communicating pertinent technical issues with facility staff, regulatory personnel, and subsequently, the public, will be discussed. Key points will be illustrated by examples from five former production reactors at the DOE Savannah River Site. In these reactors a polyurethane sealant was used to seal piping penetrations in the biological shield walls. During the intense neutron bombardment that occurred during reactor operation, the sealant broke down into a thick, viscous material that seeped out of the piping penetrations over adjacent equipment and walls. Some of the walls were painted with a PCB product. PCBs from the paint migrated into the degraded sealant, creating PCB 'spill areas' in some of these facilities. The regulatory cleanup approach selected for each facility was based on its operational status, e.g., active, inactive or undergoing decommissioning. The selected strategies served to greatly minimize the generation of radioactive liquid PCB waste. It is expected that this information would be useful to other DOE sites, DOD facilities, and commercial nuclear facilities constructed prior to the 1979 TSCA ban on most manufacturing and uses of PCBs.

  4. Refinery Capacity Report

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

    5 Idle Operating Total Stream Day Barrels per Idle Operating Total Calendar Day Barrels per Atmospheric Crude Oil Distillation Capacity Idle Operating Total Operable Refineries Number of State and PAD District a b b 9 9 0 1,268,500 1,236,500 32,000 1,332,000 1,297,000 35,000 ............................................................................................................................................... PAD District I 1 1 0 182,200 182,200 0 190,200 190,200 0

  5. Refinery Capacity Report

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

    State/Refiner/Location Alkylates Aromatics Isobutane Lubricants Isomers Isopentane and Isohexane Asphalt and Road Oil Marketable Petroleum Coke Hydrogen (MMcfd) Sulfur (short tons per day) Table 4. Production Capacity of Operable Petroleum Refineries by State as of January 1, 2015 (Barrels per Stream Day, Except Where Noted) Isooctane a ..................................................................... Alabama 0 0 15,000 711 3,500 0 7,120 33 245 0 Hunt Refining Co 0 0 15,000 0 3,500 0 7,120

  6. Representation of Solar Capacity Value in the ReEDS Capacity Expansion Model

    SciTech Connect (OSTI)

    Sigrin, B.; Sullivan, P.; Ibanez, E.; Margolis, R.

    2014-03-01

    An important issue for electricity system operators is the estimation of renewables' capacity contributions to reliably meeting system demand, or their capacity value. While the capacity value of thermal generation can be estimated easily, assessment of wind and solar requires a more nuanced approach due to the resource variability. Reliability-based methods, particularly assessment of the Effective Load-Carrying Capacity, are considered to be the most robust and widely-accepted techniques for addressing this resource variability. This report compares estimates of solar PV capacity value by the Regional Energy Deployment System (ReEDS) capacity expansion model against two sources. The first comparison is against values published by utilities or other entities for known electrical systems at existing solar penetration levels. The second comparison is against a time-series ELCC simulation tool for high renewable penetration scenarios in the Western Interconnection. Results from the ReEDS model are found to compare well with both comparisons, despite being resolved at a super-hourly temporal resolution. Two results are relevant for other capacity-based models that use a super-hourly resolution to model solar capacity value. First, solar capacity value should not be parameterized as a static value, but must decay with increasing penetration. This is because -- for an afternoon-peaking system -- as solar penetration increases, the system's peak net load shifts to later in the day -- when solar output is lower. Second, long-term planning models should determine system adequacy requirements in each time period in order to approximate LOLP calculations. Within the ReEDS model we resolve these issues by using a capacity value estimate that varies by time-slice. Within each time period the net load and shadow price on ReEDS's planning reserve constraint signals the relative importance of additional firm capacity.

  7. Atmospheric Crude Oil Distillation Operable Capacity

    Gasoline and Diesel Fuel Update (EIA)

    Catalytic Hydrotreating Gasoline Charge Capacity (BSD) Catalytic Hydrotreating Heavy Gas Oil Charge Capacity (BSD) Catalytic Hydrotreating Distillate Charge Capacity (BSD) ...

  8. Nuclear power programs in developing countries of the world: Southeast Asia

    SciTech Connect (OSTI)

    1995-05-01

    This article reviews the present and future status of the nuclear industry in the developing nations of China, North Korea, Thailand, Indonesia, and the Philippines. Each of the countries has a booming export-driven economy, which is turn requires considerable new generating capacity. The nuclear option is being considered as a provider of much of this additional capacity. China is committed to an extensive nuclear power program, and Indonesia has an ambitious plan to have seven to twelve reactors in service by the year 2015. North Korea will receive two LWRs to replace its current non-power nuclear units. The nuclear option is still under discussion in the Philippines and in Thailand.

  9. Proliferation Persuasion. Coercive Bargaining with Nuclear Technology

    SciTech Connect (OSTI)

    Volpe, Tristan A.

    2015-08-31

    Why do states wait for prolonged periods of time with the technical capacity to produce nuclear weapons? Only a handful of countries have ever acquired the sensitive nuclear fuel cycle technology needed to produce fissile material for nuclear weapons. Yet the enduring trend over the last five decades is for these states to delay or forgo exercising the nuclear weapons option provided by uranium enrichment or plutonium reprocessing capabilities. I show that states pause at this threshold stage because they use nuclear technology to bargain for concessions from both allies and adversaries. But when does nuclear latency offer bargaining benefits? My central argument is that challengers must surmount a dilemma to make coercive diplomacy work: the more they threaten to proliferate, the harder it becomes to reassure others that compliance will be rewarded with nuclear restraint. I identify a range of mechanisms able to solve this credibility problem, from arms control over breakout capacity to third party mediation and confidence building measures. Since each step towards the bomb raises the costs of implementing these policies, a state hits a sweet spot when it first acquires enrichment and/or reprocessing (ENR) technology. Subsequent increases in proliferation capability generate diminishing returns at the bargaining table for two reasons: the state must go to greater lengths to make a credible nonproliferation promise, and nuclear programs exhibit considerable path dependency as they mature over time. Contrary to the conventional wisdom about power in world politics, less nuclear latency thereby yields more coercive threat advantages. I marshal new primary source evidence from archives and interviews to identify episodes in the historical record when states made clear decisions to use ENR technology as a bargaining chip, and employ this theory of proliferation persuasion to explain how Japan, North Korea, and Iran succeeded and failed to barter concessions from the United States. By clarifying when countries are able to leverage steps towards the bomb for international political gain, my work advances our understanding of proliferation and coercive diplomacy.

  10. Nuclear Security Centers of Excellence: Fact Sheet | National...

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

    Nuclear Security Centers of Excellence: Fact Sheet March 23, 2012 "We the Participating States... Acknowledge the need for capacity building for nuclear security and cooperation ...

  11. Refinery Capacity Report

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

    Capacity Report June 2015 With Data as of January 1, 2015 Independent Statistics & Analysis www.eia.gov U.S. Department of Energy Washington, DC 20585 This report was prepared by the U.S. Energy Information Administration (EIA), the statistical and analytical agency within the U.S. Department of Energy. By law, EIA's data, analyses, and forecasts are independent of approval by any other officer or employee of the United States Government. The views in this report therefore should not be

  12. Refinery Capacity Report

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

    Former Corporation/Refiner Total Atmospheric Crude Oil Distillation Capacity (bbl/cd) New Corporation/Refiner Date of Sale Table 12. Refinery Sales During 2014 Lindsay Goldberg LLC/Axeon Speciality Products LLC Nustar Asphalt LLC/Nustar Asphalt Refining LLC 2/14 Savannah, GA 28,000 Lindsay Goldberg LLC/Axeon Specialty Products LLC Nustar Asphalt LLC/Nustar Asphalt Refining LLC 2/14 Paulsboro, NJ 70,000 bbl/cd= Barrels per calendar day Sources: Energy Information Administration (EIA) Form

  13. State Nuclear Profiles 2010

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

    Alabama Alabama total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 5,043 15.6 37,941 24.9 Coal 11,441 35.3 63,050 41.4 Hydro and Pumped Storage 3,272 10.1 8,704 5.7 Natural Gas 11,936 36.8 39,235 25.8 Other 1 100 0.3 643 0.4 Other Renewable 1 583 1.8 2,377 1.6 Petroleum 43 0.1 200 0.1 Total 32,417 100.0 152,151 100.0 Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas, sludge waste, agriculture

  14. State Nuclear Profiles 2010

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

    Arizona Arizona Total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 3,937 14.9 31,200 27.9 Coal 6,233 23.6 43,644 39.1 Hydro and Pumped Storage 2,937 11.1 6,831 6.1 Natural Gas 13,012 49.3 29,676 26.6 Other 1 - - 15 * Other Renewable 1 181 0.7 319 0.3 Petroleum 93 0.4 66 0.1 Total 26,392 100.0 111,751 100.0 * = Absolute percentage less than 0.05. - = No data reported. Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid

  15. State Nuclear Profiles 2010

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

    Arkansas Arkansas total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 1,835 11.5 15,023 24.6 Coal 4,535 28.4 28,152 46.2 Hydro and Pumped Storage 1,369 8.6 3,658 6.0 Natural Gas 7,894 49.4 12,469 20.4 Other 1 - - 28 * Other Renewable 1 326 2.0 1,624 2.7 Petroleum 22 0.1 45 0.1 Total 15,981 100.0 61,000 100.0 * = Absolute percentage less than 0.05. - = No data reported. Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid

  16. State Nuclear Profiles 2010

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

    7 California California total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 4,390 6.5 32,201 15.8 Coal 374 0.6 2,100 1.0 Hydro and Pumped Storage 13,954 20.7 33,260 16.3 Natural Gas 41,370 61.4 107,522 52.7 Other 1 220 0.3 2,534 1.2 Other Renewable 1 6,319 9.4 25,450 12.5 Petroleum 701 1.0 1,059 0.5 Total 67,328 100.0 204,126 100.0 Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas, sludge waste,

  17. State Nuclear Profiles 2010

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

    9 Connecticut Connecticut total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 2,103 25.4 16,750 50.2 Coal 564 6.8 2,604 7.8 Hydro and Pumped Storage 151 1.8 400 1.2 Natural Gas 2,292 27.7 11,716 35.1 Other 1 27 0.3 730 2.2 Other Renewable 1 159 1.9 740 2.2 Petroleum 2,989 36.1 409 1.2 Total 8,284 100.0 33,350 100.0 Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas, sludge waste, agriculture

  18. State Nuclear Profiles 2010

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

    1 Florida Florida total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 3,924 6.6 23,936 10.4 Coal 9,975 16.9 59,897 26.1 Hydro and Pumped Storage 55 0.1 177 0.1 Natural Gas 31,563 53.4 128,634 56.1 Other 1 544 0.9 2,842 1.2 Other Renewable 1 1,053 1.8 4,487 2.0 Petroleum 12,033 20.3 9,122 4.0 Total 59,147 100.0 229,096 100.0 Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas, sludge waste, agriculture

  19. State Nuclear Profiles 2010

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

    3 Georgia Georgia total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 4,061 11.1 33,512 24.4 Coal 13,230 36.1 73,298 53.3 Hydro and Pumped Storage 3,851 10.5 3,044 2.2 Natural Gas 12,668 34.6 23,884 17.4 Other 1 - - 18 * Other Renewable 1 637 1.7 3,181 2.3 Petroleum 2,189 6.0 641 0.5 Total 36,636 100.0 137,577 100.0 * = Absolute percentage less than 0.05. - = No data reported. Other Renewable: Wood, black liquor, other wood waste, biogenic municipal

  20. State Nuclear Profiles 2010

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

    7 Illinois Illinois total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 11,441 25.9 96,190 47.8 Coal 15,551 35.2 93,611 46.5 Hydro and Pumped Storage 34 0.1 119 0.1 Natural Gas 13,771 31.2 5,724 2.8 Other 1 145 0.3 461 0.2 Other Renewable 1 2,078 4.7 5,138 2.6 Petroleum 1,106 2.5 110 0.1 Total 44,127 100.0 201,352 100.0 Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas, sludge waste, agriculture

  1. State Nuclear Profiles 2010

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

    21 Louisiana Louisiana total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 2,142 8.0 18,639 18.1 Coal 3,417 12.8 23,924 23.3 Hydro and Pumped Storage 192 0.7 1,109 1.1 Natural Gas 19,574 73.2 51,344 49.9 Other 1 213 0.8 2,120 2.1 Other Renewable 1 325 1.2 2,468 2.4 Petroleum 881 3.3 3,281 3.2 Total 26,744 100.0 102,885 100.0 Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas, sludge waste, agriculture

  2. State Nuclear Profiles 2010

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

    5 Maryland Maryland total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 1,705 13.6 13,994 32.1 Coal 4,886 39.0 23,668 54.3 Hydro and Pumped Storage 590 4.7 1,667 3.8 Natural Gas 2,041 16.3 2,897 6.6 Other 1 152 1.2 485 1.1 Other Renewable 1 209 1.7 574 1.3 Petroleum 2,933 23.4 322 0.7 Total 12,516 100.0 43,607 100.0 Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas, sludge waste, agriculture

  3. State Nuclear Profiles 2010

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

    3 Massachusetts Massachusetts total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 685 5.0 5,918 13.8 Coal 1,669 12.2 8,306 19.4 Hydro and Pumped Storage 1,942 14.2 659 1.5 Natural Gas 6,063 44.3 25,582 59.8 Other 1 3 * 771 1.8 Other Renewable 1 304 2.2 1,274 3.0 Petroleum 3,031 22.1 296 0.7 Total 13,697 100.0 42,805 100.0 * = Absolute percentage less than 0.05. Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste,

  4. State Nuclear Profiles 2010

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

    7 Michigan Michigan total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 3,947 13.2 29,625 26.6 Coal 11,531 38.7 65,604 58.8 Hydro and Pumped Storage 2,109 7.1 228 0.2 Natural Gas 11,033 37.0 12,249 11.0 Other 1 - - 631 0.6 Other Renewable 1 571 1.9 2,832 2.5 Petroleum 640 2.1 382 0.3 Total 29,831 100.0 111,551 100.0 - = No data reported. Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas, sludge waste,

  5. State Nuclear Profiles 2010

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

    9 Minnesota Minnesota total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 1,594 10.8 13,478 25.1 Coal 4,789 32.5 28,083 52.3 Hydro and Pumped Storage 193 1.3 840 1.6 Natural Gas 4,936 33.5 4,341 8.1 Other 1 13 0.1 258 0.5 Other Renewable 1 2,395 16.3 6,640 12.4 Petroleum 795 5.4 31 0.1 Total 14,715 100.0 53,670 100.0 Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas, sludge waste, agriculture

  6. State Nuclear Profiles 2010

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

    3 Mississippi Mississippi total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 1,251 8.0 9,643 17.7 Coal 2,526 16.1 13,629 25.0 Natural Gas 11,640 74.2 29,619 54.4 Other 1 4 * 10 * Other Renewable 1 235 1.5 1,504 2.8 Petroleum 35 0.2 81 0.1 Total 15,691 100.0 54,487 100.0 * = Absolute percentage less than 0.05. Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas, sludge waste, agriculture byproducts,

  7. State Nuclear Profiles 2010

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

    1 Missouri Missouri total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 1,190 5.5 8,996 9.7 Coal 12,070 55.5 75,047 81.3 Hydro and Pumped Storage 1,221 5.6 2,427 2.6 Natural Gas 5,579 25.7 4,690 5.1 Other 1 - - 39 * Other Renewable 1 466 2.1 988 1.1 Petroleum 1,212 5.6 126 0.1 Total 21,739 100.0 92,313 100.0 * = Absolute percentage less than 0.05. - = No data reported. Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid

  8. State Nuclear Profiles 2010

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

    9 New Hampshire New Hampshire total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 1,247 29.8 10,910 49.2 Coal 546 13.1 3,083 13.9 Hydro and Pumped Storage 489 11.7 1,478 6.7 Natural Gas 1,215 29.1 5,365 24.2 Other 1 - - 57 0.3 Other Renewable 1 182 4.4 1,232 5.6 Petroleum 501 12.0 72 0.3 Total 4,180 100.0 22,196 100.0 - = No data reported. Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas, sludge

  9. State Nuclear Profiles 2010

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

    41 New Jersey New Jersey total electric power industry, summer capacity and net generation, by source, 2010 Nuclear 4,108 22.3 32,771 49.9 Coal 2,036 11.1 6,418 9.8 Hydro and Pumped Storage 404 2.2 -176 -0.3 Natural Gas 10,244 55.6 24,902 37.9 Other 1 56 0.3 682 1.0 Other Renewable 1 226 1.2 850 1.3 Petroleum 1,351 7.3 235 0.4 Total 18,424 100.0 65,682 100.0 Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas, sludge waste, agriculture byproducts,

  10. State Nuclear Profiles 2010

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

    3 New York New York total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 5,271 13.4 41,870 30.6 Coal 2,781 7.1 13,583 9.9 Hydro and Pumped Storage 5,714 14.5 24,942 18.2 Natural Gas 17,407 44.2 48,916 35.7 Other 1 45 0.1 832 0.6 Other Renewable 1 1,719 4.4 4,815 3.5 Petroleum 6,421 16.3 2,005 1.5 Total 39,357 100.0 136,962 100.0 Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas, sludge waste,

  11. State Nuclear Profiles 2010

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

    34 North Carolina North Carolina total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 4,958 17.9 40,740 31.7 Coal 12,766 46.1 71,951 55.9 Hydro and Pumped Storage 2,042 7.4 4,757 3.7 Natural Gas 6,742 24.4 8,447 6.6 Other 1 50 0.2 407 0.3 Other Renewable 1 543 2.0 2,083 1.6 Petroleum 573 2.1 293 0.2 Total 27,674 100.0 128,678 100.0 Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas, sludge waste,

  12. State Nuclear Profiles 2010

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

    6 Ohio Ohio total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 2,134 6.5 15,805 11.0 Coal 21,360 64.6 117,828 82.1 Hydro and Pumped Storage 101 0.3 429 0.3 Natural Gas 8,203 24.8 7,128 5.0 Other 1 123 0.4 266 0.2 Other Renewable 1 130 0.4 700 0.5 Petroleum 1,019 3.1 1,442 1.0 Total 33,071 100.0 143,598 100.0 Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas, sludge waste, agriculture byproducts,

  13. State Nuclear Profiles 2010

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

    48 Pennsylvania Pennsylvania total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 9,540 20.9 77,828 33.9 Coal 18,481 40.6 110,369 48.0 Hydro and Pumped Storage 2,268 5.0 1,624 0.7 Natural Gas 9,415 20.7 33,718 14.7 Other 1 100 0.2 1,396 0.6 Other Renewable 1 1,237 2.7 4,245 1.8 Petroleum 4,534 9.9 571 0.2 Total 45,575 100.0 229,752 100.0 Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas, sludge waste,

  14. State Nuclear Profiles 2010

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

    1 South Carolina South Carolina total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 6,486 27.0 51,988 49.9 Coal 7,230 30.1 37,671 36.2 Hydro and Pumped Storage 4,006 16.7 1,442 1.4 Natural Gas 5,308 22.1 10,927 10.5 Other 1 - - 61 0.1 Other Renewable 1 284 1.2 1,873 1.8 Petroleum 670 2.8 191 0.2 Total 23,982 100.0 104,153 100.0 - = No data reported. Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas,

  15. State Nuclear Profiles 2010

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

    4 Tennessee Tennessee total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 3,401 15.9 27,739 33.7 Coal 8,805 41.1 43,670 53.0 Hydro and Pumped Storage 4,277 20.0 7,416 9.0 Natural Gas 4,655 21.7 2,302 2.8 Other 1 - - 16 * Other Renewable 1 222 1.0 988 1.2 Petroleum 58 0.3 217 0.3 Total 21,417 100.0 82,349 100.0 * = Absolute percentage less than 0.05. - = No data reported. Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid

  16. State Nuclear Profiles 2010

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

    6 Texas Texas total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 4,966 4.6 41,335 10.0 Coal 22,335 20.6 150,173 36.5 Hydro and Pumped Storage 689 0.6 1,262 0.3 Natural Gas 69,291 64.0 186,882 45.4 Other 1 477 0.4 3,630 0.9 Other Renewable 1 10,295 9.5 27,705 6.7 Petroleum 204 0.2 708 0.2 Total 108,258 100.0 411,695 100.0 Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas, sludge waste, agriculture

  17. State Nuclear Profiles 2010

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

    8 Virginia Virginia total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 3,501 14.5 26,572 36.4 Coal 5,868 24.3 25,459 34.9 Hydro and Pumped Storage 4,107 17.0 10 * Natural Gas 7,581 31.4 16,999 23.3 Other 1 - - 414 0.6 Other Renewable 1 621 2.6 2,220 3.0 Petroleum 2,432 10.1 1,293 1.8 Total 24,109 100.0 72,966 100.0 * = Absolute percentage less than 0.05. - = No data reported. Other Renewable: Wood, black liquor, other wood waste, biogenic municipal

  18. State Nuclear Profiles 2010

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

    63 Wisconsin Wisconsin total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 1,584 8.9 13,281 20.7 Coal 8,063 45.2 40,169 62.5 Hydro and Pumped Storage 492 2.8 2,112 3.3 Natural Gas 6,110 34.3 5,497 8.5 Other 1 21 0.1 63 0.1 Other Renewable 1 775 4.3 2,474 3.8 Petroleum 790 4.4 718 1.1 Total 17,836 100.0 64,314 100.0 Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas, sludge waste, agriculture

  19. State Nuclear Profiles 2010

    Gasoline and Diesel Fuel Update (EIA)

    Arizona Arizona Total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 3,937 14.9 31,200 27.9 Coal 6,233 23.6 43,644 39.1 Hydro and Pumped Storage 2,937 11.1 6,831 6.1 Natural Gas 13,012 49.3 29,676 26.6 Other 1 - - 15 * Other Renewable 1 181 0.7 319 0.3 Petroleum 93 0.4 66 0.1 Total 26,392 100.0 111,751 100.0 * = Absolute percentage less than 0.05. - = No data reported. Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid

  20. State Nuclear Profiles 2010

    Gasoline and Diesel Fuel Update (EIA)

    Arkansas Arkansas total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 1,835 11.5 15,023 24.6 Coal 4,535 28.4 28,152 46.2 Hydro and Pumped Storage 1,369 8.6 3,658 6.0 Natural Gas 7,894 49.4 12,469 20.4 Other 1 - - 28 * Other Renewable 1 326 2.0 1,624 2.7 Petroleum 22 0.1 45 0.1 Total 15,981 100.0 61,000 100.0 * = Absolute percentage less than 0.05. - = No data reported. Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid

  1. State Nuclear Profiles 2010

    Gasoline and Diesel Fuel Update (EIA)

    7 California California total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 4,390 6.5 32,201 15.8 Coal 374 0.6 2,100 1.0 Hydro and Pumped Storage 13,954 20.7 33,260 16.3 Natural Gas 41,370 61.4 107,522 52.7 Other 1 220 0.3 2,534 1.2 Other Renewable 1 6,319 9.4 25,450 12.5 Petroleum 701 1.0 1,059 0.5 Total 67,328 100.0 204,126 100.0 Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas, sludge waste,

  2. State Nuclear Profiles 2010

    Gasoline and Diesel Fuel Update (EIA)

    9 Connecticut Connecticut total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 2,103 25.4 16,750 50.2 Coal 564 6.8 2,604 7.8 Hydro and Pumped Storage 151 1.8 400 1.2 Natural Gas 2,292 27.7 11,716 35.1 Other 1 27 0.3 730 2.2 Other Renewable 1 159 1.9 740 2.2 Petroleum 2,989 36.1 409 1.2 Total 8,284 100.0 33,350 100.0 Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas, sludge waste, agriculture

  3. State Nuclear Profiles 2010

    Gasoline and Diesel Fuel Update (EIA)

    1 Florida Florida total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 3,924 6.6 23,936 10.4 Coal 9,975 16.9 59,897 26.1 Hydro and Pumped Storage 55 0.1 177 0.1 Natural Gas 31,563 53.4 128,634 56.1 Other 1 544 0.9 2,842 1.2 Other Renewable 1 1,053 1.8 4,487 2.0 Petroleum 12,033 20.3 9,122 4.0 Total 59,147 100.0 229,096 100.0 Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas, sludge waste, agriculture

  4. State Nuclear Profiles 2010

    Gasoline and Diesel Fuel Update (EIA)

    3 Georgia Georgia total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 4,061 11.1 33,512 24.4 Coal 13,230 36.1 73,298 53.3 Hydro and Pumped Storage 3,851 10.5 3,044 2.2 Natural Gas 12,668 34.6 23,884 17.4 Other 1 - - 18 * Other Renewable 1 637 1.7 3,181 2.3 Petroleum 2,189 6.0 641 0.5 Total 36,636 100.0 137,577 100.0 * = Absolute percentage less than 0.05. - = No data reported. Other Renewable: Wood, black liquor, other wood waste, biogenic municipal

  5. State Nuclear Profiles 2010

    Gasoline and Diesel Fuel Update (EIA)

    5 Maryland Maryland total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 1,705 13.6 13,994 32.1 Coal 4,886 39.0 23,668 54.3 Hydro and Pumped Storage 590 4.7 1,667 3.8 Natural Gas 2,041 16.3 2,897 6.6 Other 1 152 1.2 485 1.1 Other Renewable 1 209 1.7 574 1.3 Petroleum 2,933 23.4 322 0.7 Total 12,516 100.0 43,607 100.0 Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas, sludge waste, agriculture

  6. State Nuclear Profiles 2010

    Gasoline and Diesel Fuel Update (EIA)

    3 Massachusetts Massachusetts total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 685 5.0 5,918 13.8 Coal 1,669 12.2 8,306 19.4 Hydro and Pumped Storage 1,942 14.2 659 1.5 Natural Gas 6,063 44.3 25,582 59.8 Other 1 3 * 771 1.8 Other Renewable 1 304 2.2 1,274 3.0 Petroleum 3,031 22.1 296 0.7 Total 13,697 100.0 42,805 100.0 * = Absolute percentage less than 0.05. Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste,

  7. State Nuclear Profiles 2010

    Gasoline and Diesel Fuel Update (EIA)

    7 Michigan Michigan total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 3,947 13.2 29,625 26.6 Coal 11,531 38.7 65,604 58.8 Hydro and Pumped Storage 2,109 7.1 228 0.2 Natural Gas 11,033 37.0 12,249 11.0 Other 1 - - 631 0.6 Other Renewable 1 571 1.9 2,832 2.5 Petroleum 640 2.1 382 0.3 Total 29,831 100.0 111,551 100.0 - = No data reported. Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas, sludge waste,

  8. State Nuclear Profiles 2010

    Gasoline and Diesel Fuel Update (EIA)

    3 Mississippi Mississippi total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 1,251 8.0 9,643 17.7 Coal 2,526 16.1 13,629 25.0 Natural Gas 11,640 74.2 29,619 54.4 Other 1 4 * 10 * Other Renewable 1 235 1.5 1,504 2.8 Petroleum 35 0.2 81 0.1 Total 15,691 100.0 54,487 100.0 * = Absolute percentage less than 0.05. Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas, sludge waste, agriculture byproducts,

  9. State Nuclear Profiles 2010

    Gasoline and Diesel Fuel Update (EIA)

    1 Missouri Missouri total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 1,190 5.5 8,996 9.7 Coal 12,070 55.5 75,047 81.3 Hydro and Pumped Storage 1,221 5.6 2,427 2.6 Natural Gas 5,579 25.7 4,690 5.1 Other 1 - - 39 * Other Renewable 1 466 2.1 988 1.1 Petroleum 1,212 5.6 126 0.1 Total 21,739 100.0 92,313 100.0 * = Absolute percentage less than 0.05. - = No data reported. Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid

  10. State Nuclear Profiles 2010

    Gasoline and Diesel Fuel Update (EIA)

    9 New Hampshire New Hampshire total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 1,247 29.8 10,910 49.2 Coal 546 13.1 3,083 13.9 Hydro and Pumped Storage 489 11.7 1,478 6.7 Natural Gas 1,215 29.1 5,365 24.2 Other 1 - - 57 0.3 Other Renewable 1 182 4.4 1,232 5.6 Petroleum 501 12.0 72 0.3 Total 4,180 100.0 22,196 100.0 - = No data reported. Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas, sludge

  11. State Nuclear Profiles 2010

    Gasoline and Diesel Fuel Update (EIA)

    3 New York New York total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 5,271 13.4 41,870 30.6 Coal 2,781 7.1 13,583 9.9 Hydro and Pumped Storage 5,714 14.5 24,942 18.2 Natural Gas 17,407 44.2 48,916 35.7 Other 1 45 0.1 832 0.6 Other Renewable 1 1,719 4.4 4,815 3.5 Petroleum 6,421 16.3 2,005 1.5 Total 39,357 100.0 136,962 100.0 Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas, sludge waste,

  12. State Nuclear Profiles 2010

    Gasoline and Diesel Fuel Update (EIA)

    34 North Carolina North Carolina total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 4,958 17.9 40,740 31.7 Coal 12,766 46.1 71,951 55.9 Hydro and Pumped Storage 2,042 7.4 4,757 3.7 Natural Gas 6,742 24.4 8,447 6.6 Other 1 50 0.2 407 0.3 Other Renewable 1 543 2.0 2,083 1.6 Petroleum 573 2.1 293 0.2 Total 27,674 100.0 128,678 100.0 Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas, sludge waste,

  13. State Nuclear Profiles 2010

    Gasoline and Diesel Fuel Update (EIA)

    6 Ohio Ohio total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 2,134 6.5 15,805 11.0 Coal 21,360 64.6 117,828 82.1 Hydro and Pumped Storage 101 0.3 429 0.3 Natural Gas 8,203 24.8 7,128 5.0 Other 1 123 0.4 266 0.2 Other Renewable 1 130 0.4 700 0.5 Petroleum 1,019 3.1 1,442 1.0 Total 33,071 100.0 143,598 100.0 Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas, sludge waste, agriculture byproducts,

  14. State Nuclear Profiles 2010

    Gasoline and Diesel Fuel Update (EIA)

    1 South Carolina South Carolina total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 6,486 27.0 51,988 49.9 Coal 7,230 30.1 37,671 36.2 Hydro and Pumped Storage 4,006 16.7 1,442 1.4 Natural Gas 5,308 22.1 10,927 10.5 Other 1 - - 61 0.1 Other Renewable 1 284 1.2 1,873 1.8 Petroleum 670 2.8 191 0.2 Total 23,982 100.0 104,153 100.0 - = No data reported. Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas,

  15. State Nuclear Profiles 2010

    Gasoline and Diesel Fuel Update (EIA)

    4 Tennessee Tennessee total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 3,401 15.9 27,739 33.7 Coal 8,805 41.1 43,670 53.0 Hydro and Pumped Storage 4,277 20.0 7,416 9.0 Natural Gas 4,655 21.7 2,302 2.8 Other 1 - - 16 * Other Renewable 1 222 1.0 988 1.2 Petroleum 58 0.3 217 0.3 Total 21,417 100.0 82,349 100.0 * = Absolute percentage less than 0.05. - = No data reported. Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid

  16. State Nuclear Profiles 2010

    Gasoline and Diesel Fuel Update (EIA)

    6 Texas Texas total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 4,966 4.6 41,335 10.0 Coal 22,335 20.6 150,173 36.5 Hydro and Pumped Storage 689 0.6 1,262 0.3 Natural Gas 69,291 64.0 186,882 45.4 Other 1 477 0.4 3,630 0.9 Other Renewable 1 10,295 9.5 27,705 6.7 Petroleum 204 0.2 708 0.2 Total 108,258 100.0 411,695 100.0 Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas, sludge waste, agriculture

  17. State Nuclear Profiles 2010

    Gasoline and Diesel Fuel Update (EIA)

    8 Virginia Virginia total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 3,501 14.5 26,572 36.4 Coal 5,868 24.3 25,459 34.9 Hydro and Pumped Storage 4,107 17.0 10 * Natural Gas 7,581 31.4 16,999 23.3 Other 1 - - 414 0.6 Other Renewable 1 621 2.6 2,220 3.0 Petroleum 2,432 10.1 1,293 1.8 Total 24,109 100.0 72,966 100.0 * = Absolute percentage less than 0.05. - = No data reported. Other Renewable: Wood, black liquor, other wood waste, biogenic municipal

  18. State Nuclear Profiles 2010

    Gasoline and Diesel Fuel Update (EIA)

    63 Wisconsin Wisconsin total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 1,584 8.9 13,281 20.7 Coal 8,063 45.2 40,169 62.5 Hydro and Pumped Storage 492 2.8 2,112 3.3 Natural Gas 6,110 34.3 5,497 8.5 Other 1 21 0.1 63 0.1 Other Renewable 1 775 4.3 2,474 3.8 Petroleum 790 4.4 718 1.1 Total 17,836 100.0 64,314 100.0 Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas, sludge waste, agriculture

  19. Enhanced capacity and stability for the separation of cesium in electrically switched ion exchange

    SciTech Connect (OSTI)

    Tawfic, A.F.; Dickson, S.E.; Kim, Y.; Mekky, W.

    2015-03-15

    Electrically switched ion exchange (ESIX) can be used to separate ionic contaminants from industrial wastewater, including that generated by the nuclear industry. The ESIX method involves sequential application of reduction and oxidation potentials to an ion exchange film to induce the respective loading and unloading of cesium. This technology is superior to conventional methods (e.g electrodialysis reversal or reverse osmosis) as it requires very little energy for ionic separation. In previous studies, ESIX films have demonstrated relatively low ion exchange capacities and limited film stabilities over repeated potential applications. In this study, the methodology for the deposition of electro-active films (nickel hexacyanoferrate) on nickel electrodes was modified to improve the ion exchange capacity for cesium removal using ESIX. Cyclic voltammetry was used to investigate the ion exchange capacity and stability. Scanning electron microscopy (SEM) was used to characterize the modified film surfaces. Additionally, the films were examined for the separation of cesium ions. This modified film preparation technique enhanced the ion exchange capacity and improves the film stability compared to previous methods for the deposition of ESIX films. (authors)

  20. Capacity Requirements to Support Inter-Balancing Area Wind Delivery

    SciTech Connect (OSTI)

    Kirby, B.; Milligan, M.

    2009-07-01

    Paper examines the capacity requirements that arise as wind generation is integrated into the power system and how those requirements change depending on where the wind energy is delivered.

  1. Why Are We Talking About Capacity Markets? (Presentation)

    SciTech Connect (OSTI)

    Milligan, M.

    2011-06-01

    Capacity markets represent a new and novel way to achieve greater economic use of variable generation assets such as wind and solar, and this concept is discussed in this presentation.

  2. Electricity Generation Cost Simulation Model

    Energy Science and Technology Software Center (OSTI)

    2003-04-25

    The Electricity Generation Cost Simulation Model (GENSIM) is a user-friendly, high-level dynamic simulation model that calculates electricity production costs for variety of electricity generation technologies, including: pulverized coal, gas combustion turbine, gas combined cycle, nuclear, solar (PV and thermal), and wind. The model allows the user to quickly conduct sensitivity analysis on key variables, including: capital, O&M, and fuel costs; interest rates; construction time; heat rates; and capacity factors. The model also includes consideration ofmore » a wide range of externality costs and pollution control options for carbon dioxide, nitrogen oxides, sulfur dioxide, and mercury. Two different data sets are included in the model; one from the U.S. Department of Energy (DOE) and the other from Platt's Research Group. Likely users of this model include executives and staff in the Congress, the Administration and private industry (power plant builders, industrial electricity users and electric utilities). The model seeks to improve understanding of the economic viability of various generating technologies and their emission trade-offs. The base case results using the DOE data, indicate that in the absence of externality costs, or renewable tax credits, pulverized coal and gas combined cycle plants are the least cost alternatives at 3.7 and 3.5 cents/kwhr, respectively. A complete sensitivity analysis on fuel, capital, and construction time shows that these results coal and gas are much more sensitive to assumption about fuel prices than they are to capital costs or construction times. The results also show that making nuclear competitive with coal or gas requires significant reductions in capital costs, to the $1000/kW level, if no other changes are made. For renewables, the results indicate that wind is now competitive with the nuclear option and is only competitive with coal and gas for grid connected applications if one includes the federal production tax credit of 1.8 cents/kwhr.« less

  3. 2013 Nuclear Workforce Development Day

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

    Nuclear Myths Topics:  Can a Nuclear Reactor Explode Like a Bomb?  Will Nuclear Waste Be Around for Millions of Years?  Is Nuclear Energy Dangerous? Moderator: Suzy Hobbs Baker Founder, PopAtomic Studios & Director of Nuclear Literacy Project Panel Members: TJ Corder - Nuclear Engineer, Vogtle 3 & 4 Southern Company Jana Thames - Communications Specialist Southern Company Brian Dyke - Nuclear Auxiliary Operator Duke Energy Nathan Zohner North American Young Generation in Nuclear

  4. nuclear bombs | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    nuclear bombs

  5. nuclear fusion | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    nuclear fusion

  6. nuclear reactors | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    nuclear reactors

  7. international security policy | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    security policy Nuclear Verification Challenge: Maintain the U.S. ability to monitor and verify nuclear reduction agreements and detect violations of treaties and other nuclear nonproliferation commitments. Solution: Develop and deploy measures to ensure verifiable compliance with treaties and other international agreements,... International Nuclear Safeguards Challenge: Detect/deter undeclared nuclear materials and activities. Solution: Build capacity of the International Atomic Energy Agency

  8. international security | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    security Nuclear Verification Challenge: Maintain the U.S. ability to monitor and verify nuclear reduction agreements and detect violations of treaties and other nuclear nonproliferation commitments. Solution: Develop and deploy measures to ensure verifiable compliance with treaties and other international agreements,... International Nuclear Safeguards Challenge: Detect/deter undeclared nuclear materials and activities. Solution: Build capacity of the International Atomic Energy Agency and

  9. High capacity oil burner

    SciTech Connect (OSTI)

    Pedrosa, O.A. Jr.; Couto, N.C.; Fanqueiro, R.C.C.

    1983-11-01

    The present invention relates to a high capacity oil burner comprising a cylindrical atomizer completely surrounded by a protective cylindrical housing having a diameter from 2 to 3 times greater than the diameter of said atomizer; liquid fuels being injected under pressure into said atomizer and accumulating within said atomizer in a chamber for the accumulation of liquid fuels, and compressed air being injected into a chamber for the accumulation of air; cylindrical holes communicating said chamber for the accumulation of liquid fuels with the outside and cylindrical holes communicating said chamber for the accumulation of air with said cylindrical holes communicating the chamber for the accumulation of liquids with the outside so that the injection of compressed air into said liquid fuel discharge holes atomizes said fuel which is expelled to the outside through the end portions of said discharge holes which are circumferentially positioned to be burnt by a pilot flame; said protecting cylindrical housing having at its ends perforated circular rings into which water is injected under pressure to form a protecting fan-like water curtain at the rear end of the housing and a fan-like water curtain at the flame to reduce the formation of soot; the burning efficiency of said burner being superior to 30 barrels of liquid fuel per day/kg of the apparatus.

  10. The role of actinide burning and the Integral Fast Reactor in the future of nuclear power

    SciTech Connect (OSTI)

    Hollaway, W.R.; Lidsky, L.M.; Miller, M.M.

    1990-12-01

    A preliminary assessment is made of the potential role of actinide burning and the Integral Fast Reactor (IFR) in the future of nuclear power. The development of a usable actinide burning strategy could be an important factor in the acceptance and implementation of a next generation of nuclear power. First, the need for nuclear generating capacity is established through the analysis of energy and electricity demand forecasting models which cover the spectrum of bias from anti-nuclear to pro-nuclear. The analyses take into account the issues of global warming and the potential for technological advances in energy efficiency. We conclude, as do many others, that there will almost certainly be a need for substantial nuclear power capacity in the 2000--2030 time frame. We point out also that any reprocessing scheme will open up proliferation-related questions which can only be assessed in very specific contexts. The focus of this report is on the fuel cycle impacts of actinide burning. Scenarios are developed for the deployment of future nuclear generating capacity which exploit the advantages of actinide partitioning and actinide burning. Three alternative reactor designs are utilized in these future scenarios: The Light Water Reactor (LWR); the Modular Gas-Cooled Reactor (MGR); and the Integral Fast Reactor (FR). Each of these alternative reactor designs is described in some detail, with specific emphasis on their spent fuel streams and the back-end of the nuclear fuel cycle. Four separation and partitioning processes are utilized in building the future nuclear power scenarios: Thermal reactor spent fuel preprocessing to reduce the ceramic oxide spent fuel to metallic form, the conventional PUREX process, the TRUEX process, and pyrometallurgical reprocessing.

  11. Advanced Nuclear Technologies

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

    Advanced Nuclear Reactors Advanced Nuclear Reactors Turbulent Flow of Coolant in an Advanced Nuclear Reactor Visualizing Coolant Flow in Sodium Reactor Subassemblies Sodium-cooled Fast Reactor (SFR) Coolant Flow At the heart of a nuclear power plant is the reactor. The fuel assembly is placed inside a reactor vessel where all the nuclear reactions occur to produce the heat and steam used for power generation. Nonetheless, an entire power plant consists of many other support components and key

  12. 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

  13. Distributed generation hits market

    SciTech Connect (OSTI)

    1997-10-01

    The pace at which vendors are developing and marketing gas turbines and reciprocating engines for small-scale applications may signal the widespread growth of distributed generation. Loosely defined to refer to applications in which power generation equipment is located close to end users who have near-term power capacity needs, distributed generation encompasses a broad range of technologies and load requirements. Disagreement is inevitable, but many industry observers associate distributed generation with applications anywhere from 25 kW to 25 MW. Ten years ago, distributed generation users only represented about 2% of the world market. Today, that figure has increased to about 4 or 5%, and probably could settle in the 20% range within a 3-to-5-year period, according to Michael Jones, San Diego, Calif.-based Solar Turbines Inc. power generation marketing manager. The US Energy Information Administration predicts about 175 GW of generation capacity will be added domestically by 2010. If 20% comes from smaller plants, distributed generation could account for about 35 GW. Even with more competition, it`s highly unlikely distributed generation will totally replace current market structures and central stations. Distributed generation may be best suited for making market inroads when and where central systems need upgrading, and should prove its worth when the system can`t handle peak demands. Typical applications include small reciprocating engine generators at remote customer sites or larger gas turbines to boost the grid. Additional market opportunities include standby capacity, peak shaving, power quality, cogeneration and capacity rental for immediate demand requirements. Integration of distributed generation systems--using gas-fueled engines, gas-fired combustion engines and fuel cells--can upgrade power quality for customers and reduce operating costs for electric utilities.

  14. Property:USGSMeanCapacity | Open Energy Information

    Open Energy Info (EERE)

    USGSMeanCapacity Jump to: navigation, search Property Name USGSMeanCapacity Property Type String Description Mean capacity potential at location based on the USGS 2008 Geothermal...

  15. Peak Underground Working Natural Gas Storage Capacity

    Gasoline and Diesel Fuel Update (EIA)

    of capacity that may understate the amount that can actually be stored. Working Gas Design Capacity: This measure estimates a natural gas facility's working gas capacity, as...

  16. Principles of providing inherent self-protection and passive safety characteristics of the SVBR-75/100 type modular reactor installation for nuclear power plants of different capacity and purpose

    SciTech Connect (OSTI)

    Toshinsky, G.I.; Komlev, O.G.; Novikova, N.N.; Tormyshev, I.V.; Stepanov, V.S.; Klimov, N.N.; Dedoul, A.V.

    2007-07-01

    The report presents a brief description of the reactor installation SVBR-75/100, states a concept of providing the RI safety and presents the basic results of the analysis of the most dangerous pre-accidental situations and beyond the design basis accidents, which have been obtained in the process of validating the RI safety. It has been shown that the safety functions concerning the accidental shutdown of the reactor, total blacking out of the NPP and localization of the accidental situation relating to the postulated simultaneous rupture of several steam-generator tubes are not subject to influence of the human factor and are entirely realized in a passive way. (authors)

  17. EIS-0171: Pacificorp Capacity Sale

    Broader source: Energy.gov [DOE]

    The Bonneville Power Administration (BPA) EIS assesses the proposed action of providing surplus power from its facilites to PacifiCorp in response to its request for a continued supply of firm capacity. BPA has surplus electrical capacity (peakload energy) that BPA projects will not be required to meet its existing obligations.

  18. Atmospheric Crude Oil Distillation Operable Capacity

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    Charge Capacity (BSD) Catalytic Hydrotreating NaphthaReformer Feed Charge Cap (BSD) Catalytic Hydrotreating Gasoline Charge Capacity (BSD) Catalytic Hydrotreating...

  19. "Estimated Distributed Solar PV Capacity and Generation- Current...

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

    ... 2014,2,"MA","Final",55.128,193.258,17.089,265.475,5792.251,20341.06,1824.998,27958.309 2014,2,"MD","Final",31.882,84.41,3.217,119.51,3537.726,9481.699,357.4,133...

  20. Table 2. Ten largest plants by generation capacity, 2014

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

    Power & Light Co",1912 9,"Hines Energy Complex","Natural gas","Duke Energy Florida, Inc",1912 10,"H L Culbreath Bayside Power Station","Natural gas","Tampa Electric Co",1854

  1. Doubling Geothermal Generation Capacity by 2020. A Strategic Analysis

    SciTech Connect (OSTI)

    Wall, Anna; Young, Katherine

    2016-01-01

    This report identifies the potential of U.S. geothermal resource and the current market to add an additional 3 GW of geothermal by 2020, in order to meet the goal set forth in the Climate Action Plan.

  2. Table 2. Ten largest plants by generation capacity, 2014

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

    Peck","Hydroelectric","USCE-Missouri River District",200 8,"NaturEner Rim Rock Energy","Wind","NaturEner Rim Rock Energy LLC",184.6 9,"Judith Gap Wind Energy ...

  3. "Estimated Distributed Solar PV Capacity and Generation- Current...

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

    ...41,".",0.207,9.084,1.99,".",11.075 2015,12,"NE","Preliminary",0.687,0.234,"NM",0.992,61.18...41,".",0.234,9.814,1.888,".",11.702 2015,1,"NE","Preliminary",0.482,0.23,0.057,0.769,46.66...

  4. "Estimated Distributed Solar PV Capacity and Generation- Current...

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

    ...1,".",0.212,13.665,3.261,".",16.926 2016,2,"NE","Preliminary",0.737,0.234,"NM",1.044,81.28...041,".",0.212,8.342,1.888,".",10.23 2016,1,"NE","Preliminary",0.713,0.305,"NM",1.091,69.83...

  5. Doubling Geothermal Generation Capacity by 2020: A Strategic...

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

    ... https:www.whitehouse.govthe-press-office...anning-federal-sustainability-next- decade vi ... Each project must meet certain criteria to be ... within agency processes (i.e., NEPA) as ...

  6. Interconnection Standards for Small Generators | Department of...

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

    (FERC) adopted new "small generator" interconnection standards for distributed energy resources up to 20 megawatts (MW) in capacity in November 2013 and September 2014,...

  7. The NASA CSTI High Capacity Power Project

    SciTech Connect (OSTI)

    Winter, J.; Dudenhoefer, J.; Juhasz, A.; Schwarze, G.; Patterson, R.; Ferguson, D.; Titran, R.; Schmitz, P.; Vandersande, J.

    1994-09-01

    The SP-100 Space Nuclear Power Program was established in 1983 by DOD, DOE, and NASA as a joint program to develop technology for military and civil applications. Starting in 1986, NASA has funded a technology program to maintain the momentum of promising aerospace technology advancement started during Phase I of SP-100 and to strengthen, in key areas, the changes for successful development and growth capability of space nuclear reactor power systems for a wide range of future space applications. The elements of the CSTI High Capacity Power Project include Systems Analysis, Stirling Power Conversion, Thermoelectric Power Conversion, Thermal Management, Power Management, Systems Diagnostics, Environmental Interactions, and Material/Structural Development. Technology advancement in all elements is required to provide the growth capability, high reliability and 7 to 10 year lifetime demanded for future space nuclear power systems. The overall project with develop and demonstrate the technology base required to provide a wide range of modular power systems compatible with the SP-100 reactor which facilitates operation during lunar and planetary day/night cycles as well as allowing spacecraft operation at any attitude or distance from the sun. Significant accomplishments in all of the project elements will be presented, along with revised goals and project timelines recently developed.

  8. Nuclear Energy University Program | Department of Energy

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

    Energy University Program Nuclear Energy University Program NEUP Award Recipients FY2009 ... Drag and zoom map to see more recipients. Investing in the next generation of nuclear ...

  9. Quarterly Nuclear Deployment Scorecard - April 2014 | Department...

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

    4 Quarterly Nuclear Deployment Scorecard - April 2014 News Updates On February 20, ... construction of two new nuclear reactors at the Alvin W. Vogtle Electric Generating Plant. ...

  10. COMMUNITY CAPACITY BUILDING THROUGH TECHNOLOGY

    Energy Savers [EERE]

    COMMUNITY CAPACITY BUILDING THROUGH TECHNOLOGY Empowering Communities in the Age of E-Government Prepared by Melinda Downing, Environmental Justice Program Manager, U.S. Department of Energy MAR 06 MARCH 2006 Since 1999, the Department of Energy has worked with the National Urban Internet and others to create community capacity through technology.  Empowering Communities in the Age of E-Government Table of Contents Message from the Environmental Justice Program Manager . . . . . . . . 3

  11. 1,"Millstone","Nuclear","Dominion Nuclear Conn Inc",2122.5

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

    Connecticut" ,"Plant","Primary energy source","Operating company","Net summer capacity (MW)" 1,"Millstone","Nuclear","Dominion Nuclear Conn Inc",2122.5 2,"Middletown","Petroleum","...

  12. Natural Gas Underground Storage Capacity (Summary)

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

    Salt Caverns Storage Capacity Aquifers Storage Capacity Depleted Fields Storage Capacity Total Working Gas Capacity Working Gas Capacity of Salt Caverns Working Gas Capacity of Aquifers Working Gas Capacity of Depleted Fields Total Number of Existing Fields Number of Existing Salt Caverns Number of Existing Aquifers Number of Depleted Fields Period: Monthly Annual Download Series History Download Series History Definitions, Sources & Notes Definitions, Sources & Notes Show Data By: Data

  13. NMAC 17.9.568 Interconnection of Generating Facilities with a...

    Open Energy Info (EERE)

    a Rated Capacity up to and including 10 MWLegal Abstract These rules outline the procedures for interconnection of generating facilities with a rated capacity up to and...

  14. Spray dryer capacity stretched 50%

    SciTech Connect (OSTI)

    Paraskevas, J.

    1983-01-01

    This article describes plant equipment modifications which has resulted in a 50% increase in spray drying capacity. The installation of a new atomizer and screening system in NL Chemicals' Newberry Springs plant which produces natural clays for use as rheological additives in industrial coatings, cosmetics and other products, resulted in a 50% increase in spray drying capacity. Energy consumption per pound of product was reduced by 7%, and product quality improved. This was achieved in less than three months at an investment of less than 10% of what an additional spray dryer would have cost.

  15. ,"Minnesota Natural Gas Underground Storage Capacity (MMcf)"

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

    Data for" ,"Data 1","Minnesota Natural Gas Underground Storage Capacity ... 7:00:58 AM" "Back to Contents","Data 1: Minnesota Natural Gas Underground Storage Capacity ...

  16. ,"Virginia Natural Gas Underground Storage Capacity (MMcf)"

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

    Data for" ,"Data 1","Virginia Natural Gas Underground Storage Capacity ... 11:44:46 AM" "Back to Contents","Data 1: Virginia Natural Gas Underground Storage Capacity ...

  17. Working and Net Available Shell Storage Capacity

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

    Working and Net Available Shell Storage Capacity With Data for September 2015 | Release ... Containing storage capacity data for crude oil, petroleum products, and selected biofuels. ...

  18. Washington Working Natural Gas Underground Storage Capacity ...

    Gasoline and Diesel Fuel Update (EIA)

    Working Natural Gas Underground Storage Capacity (Million Cubic Feet) Washington Working Natural Gas Underground Storage Capacity (Million Cubic Feet) Year Jan Feb Mar Apr May Jun...

  19. Mississippi Working Natural Gas Underground Storage Capacity...

    Gasoline and Diesel Fuel Update (EIA)

    Working Natural Gas Underground Storage Capacity (Million Cubic Feet) Mississippi Working Natural Gas Underground Storage Capacity (Million Cubic Feet) Year Jan Feb Mar Apr May Jun...

  20. Pennsylvania Working Natural Gas Underground Storage Capacity...

    Gasoline and Diesel Fuel Update (EIA)

    Working Natural Gas Underground Storage Capacity (Million Cubic Feet) Pennsylvania Working Natural Gas Underground Storage Capacity (Million Cubic Feet) Year Jan Feb Mar Apr May...

  1. Peak Underground Working Natural Gas Storage Capacity

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    Capacity Peak Underground Working Natural Gas Storage Capacity Released: September 3, 2010 for data as of April 2010 Next Release: August 2011 References Methodology Definitions...

  2. Worldwide Energy Efficiency Action through Capacity Building...

    Open Energy Info (EERE)

    Capacity Building and Training (WEACT) Jump to: navigation, search Logo: Worldwide Energy Efficiency Action through Capacity Building and Training (WEACT) Name Worldwide...

  3. California Working Natural Gas Underground Storage Capacity ...

    Annual Energy Outlook [U.S. Energy Information Administration (EIA)]

    Working Natural Gas Underground Storage Capacity (Million Cubic Feet) California Working Natural Gas Underground Storage Capacity (Million Cubic Feet) Year Jan Feb Mar Apr May Jun...

  4. MERCURY-NITRITE-RHODIUM-RUTHENIUM INTERACTIONS IN NOBLE METAL CATALYZED HYDROGEN GENERATION FROM FORMIC ACID DURING NUCLEAR WASTE PROCESSING AT THE SAVANNAH RIVER SITE - 136C

    SciTech Connect (OSTI)

    Koopman, D.; Pickenheim, B.; Lambert, D.; Newell, J; Stone, M.

    2009-09-02

    Chemical pre-treatment of radioactive waste at the Savannah River Site is performed to prepare the waste for vitrification into a stable waste glass form. During pre-treatment, compounds in the waste become catalytically active. Mercury, rhodium, and palladium become active for nitrite destruction by formic acid, while rhodium and ruthenium become active for catalytic conversion of formic acid into hydrogen and carbon dioxide. Nitrite ion is present during the maximum activity of rhodium, but is consumed prior to the activation of ruthenium. Catalytic hydrogen generation during pre-treatment can exceed radiolytic hydrogen generation by several orders of magnitude. Palladium and mercury impact the maximum catalytic hydrogen generation rates of rhodium and ruthenium by altering the kinetics of nitrite ion decomposition. New data are presented that illustrate the interactions of these various species.

  5. Electric power transmission for a Hanford Nuclear Energy Center (HNEC)

    SciTech Connect (OSTI)

    Harty, H.; Dowis, W.J.

    1983-06-01

    The original study of transmission for a Hanford Nuclear Energy Center (HNEC), which was completed in September 1975, was updated in June 1978. The present 1983 revision takes cognizance of recent changes in the electric power situation of the PNW with respect to: (1) forecasts of load growth, (2) the feasibility of early use of 1100 kV transmission, and (3) the narrowing opportunities for siting nuclear plants in the region. The purpose of this update is to explore and describe additions to the existing transmission system that would be necessary to accommodate three levels of generation at HNEC. Comparisons with a PNW system having new thermal generating capacity distributed throughout the marketing region are not made as was done in earlier versions.

  6. Nuclear-Renewable Hybrid System Economic Basis for Electricity, Fuel, and Hydrogen

    SciTech Connect (OSTI)

    Charles Forsberg; Steven Aumeier

    2014-04-01

    Concerns about climate change and altering the ocean chemistry are likely to limit the use of fossil fuels. That implies a transition to a low-carbon nuclear-renewable electricity grid. Historically variable electricity demand was met using fossil plants with low capital costs, high operating costs, and substantial greenhouse gas emissions. However, the most easily scalable very-low-emissions generating options, nuclear and non-dispatchable renewables (solar and wind), are capital-intensive technologies with low operating costs that should operate at full capacities to minimize costs. No combination of fully-utilized nuclear and renewables can meet the variable electricity demand. This implies large quantities of expensive excess generating capacity much of the time. In a free market this results in near-zero electricity prices at times of high nuclear renewables output and low electricity demand with electricity revenue collapse. Capital deployment efficiency—the economic benefit derived from energy systems capital investment at a societal level—strongly favors high utilization of these capital-intensive systems, especially if low-carbon nuclear renewables are to replace fossil fuels. Hybrid energy systems are one option for better utilization of these systems that consumes excess energy at times of low prices to make some useful product.The economic basis for development of hybrid energy systems is described for a low-carbon nuclear renewable world where much of the time there are massivequantities of excess energy available from the electric sector.Examples include (1) high-temperature electrolysis to generate hydrogen for non-fossil liquid fuels, direct use as a transport fuel, metal reduction, etc. and (2) biorefineries.Nuclear energy with its concentrated constant heat output may become the enabling technology for economically-viable low-carbon electricity grids because hybrid nuclear systems may provide an economic way to produce dispatachable variable electricity with economic base-load operation of the reactor.

  7. Socioeconomic impacts of nuclear generating stations: Crystal River Unit 3 case study. Technical report 1 Oct 78-4 Jan 82

    SciTech Connect (OSTI)

    Bergmann, P.A.

    1982-07-01

    The report documents a case study of the socioeconomic impacts of the construction and operation of the Crystal River Unit 3 nuclear power station. It is part of a major post-licensing study of the socioeconomic impacts at twelve nuclear power stations. The case study covers the period beginning with the announcement of plans to construct the reactor and ending in the period, 1980-81. The case study deals with changes in the economy, population, settlement patterns and housing, local government and public services, social structure, and public response in the study area during the construction/operation of the reactor. A regional modeling approach is used to trace the impact of construction/operation on the local economy, labor market, and housing market. Emphasis in the study is on the attribution of socioeconomic impacts to the reactor or other causal factors. As part of the study of local public response to the construction/operation of the reactor, the effects of the Three Mile Island accident are examined.

  8. The use of filtered bags to increase waste payload capacity

    SciTech Connect (OSTI)

    Dustin, D.F.; Thorp, D.T.; Rivera, M.A.

    1998-03-03

    For the past few years, the Department of Energy has favored the direct disposal of low plutonium content residue materials from Rocky Flats rather than engage in expensive and time consuming plutonium recovery operations. One impediment to direct disposal has been the wattage limit imposed by the Waste Isolation Pilot Plant on hydrogenous materials such as combustibles and sludges. The issue of concern is the radiolytic generation and accumulation of hydrogen and other explosive gases in waste containers. The wattage limits that existed through 1996 restricted the amount of plutonium bearing hydrogenous materials that could be packaged in a WIPP bound waste drum to only a fraction of the capacity of a drum. Typically, only about one kilogram of combustible residue could be packaged in a waste drum before the wattage limit was exceeded resulting in an excessively large number of drums to be procured, stored, shipped, and interred. The Rocky Flats Environmental Technology Site has initiated the use of filtered plastic bags (called bag-out bags) used to remove transuranic waste materials from glove box lines. The bags contain small, disk like HEPA filters which are effective in containing radioactively contaminated particulate material but allow for the diffusion of hydrogen gas. Used in conjunction with filtered 55 gallon drums, filtered bag-out bags were pursued as a means to increase the allowable wattage limits for selected residue materials. In February 1997, the Nuclear Regulatory Commission approved the use of filtered bag-out bags for transuranic waste materials destined for WIPP. The concomitant increase in wattage limits now allows for approximately four times the payload per waste drum for wattage limited materials.

  9. Naval Nuclear Propulsion | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Naval Nuclear Propulsion

  10. High capacity carbon dioxide sorbent

    DOE Patents [OSTI]

    Dietz, Steven Dean; Alptekin, Gokhan; Jayaraman, Ambalavanan

    2015-09-01

    The present invention provides a sorbent for the removal of carbon dioxide from gas streams, comprising: a CO.sub.2 capacity of at least 9 weight percent when measured at 22.degree. C. and 1 atmosphere; an H.sub.2O capacity of at most 15 weight percent when measured at 25.degree. C. and 1 atmosphere; and an isosteric heat of adsorption of from 5 to 8.5 kilocalories per mole of CO.sub.2. The invention also provides a carbon sorbent in a powder, a granular or a pellet form for the removal of carbon dioxide from gas streams, comprising: a carbon content of at least 90 weight percent; a nitrogen content of at least 1 weight percent; an oxygen content of at most 3 weight percent; a BET surface area from 50 to 2600 m.sup.2/g; and a DFT micropore volume from 0.04 to 0.8 cc/g.

  11. winter_capacity_2010.xls

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

    Table 4.B Winter Net Internal Demand, Capacity Resources, and Capacity Margins by North American Electric Reliability Corporation Region, 2001-2010 Actual, 2011-2015 Projected (Megawatts and Percent) Interconnection NERC Regional Assesment Area 2001/2002 2002/2003 2003/2004 2004/2005 2005/2006 2006/2007 2007/2008 2008/2009 2009/2010 2010/ 2011 2011/2012E 2012/2013E 2013/2014E 2014/2015E 2015/2016E FRCC 39,699 42,001 36,229 41,449 42,493 45,993 46,093 45,042 51,703 45,954 44,196 44,750 45,350

  12. Tri-Laboratory Linux Capacity Cluster 2007 SOW

    SciTech Connect (OSTI)

    Seager, M

    2007-03-22

    The Advanced Simulation and Computing (ASC) Program (formerly know as Accelerated Strategic Computing Initiative, ASCI) has led the world in capability computing for the last ten years. Capability computing is defined as a world-class platform (in the Top10 of the Top500.org list) with scientific simulations running at scale on the platform. Example systems are ASCI Red, Blue-Pacific, Blue-Mountain, White, Q, RedStorm, and Purple. ASC applications have scaled to multiple thousands of CPUs and accomplished a long list of mission milestones on these ASC capability platforms. However, the computing demands of the ASC and Stockpile Stewardship programs also include a vast number of smaller scale runs for day-to-day simulations. Indeed, every 'hero' capability run requires many hundreds to thousands of much smaller runs in preparation and post processing activities. In addition, there are many aspects of the Stockpile Stewardship Program (SSP) that can be directly accomplished with these so-called 'capacity' calculations. The need for capacity is now so great within the program that it is increasingly difficult to allocate the computer resources required by the larger capability runs. To rectify the current 'capacity' computing resource shortfall, the ASC program has allocated a large portion of the overall ASC platforms budget to 'capacity' systems. In addition, within the next five to ten years the Life Extension Programs (LEPs) for major nuclear weapons systems must be accomplished. These LEPs and other SSP programmatic elements will further drive the need for capacity calculations and hence 'capacity' systems as well as future ASC capability calculations on 'capability' systems. To respond to this new workload analysis, the ASC program will be making a large sustained strategic investment in these capacity systems over the next ten years, starting with the United States Government Fiscal Year 2007 (GFY07). However, given the growing need for 'capability' systems as well, the budget demands are extreme and new, more cost effective ways of fielding these systems must be developed. This Tri-Laboratory Linux Capacity Cluster (TLCC) procurement represents the ASC first investment vehicle in these capacity systems. It also represents a new strategy for quickly building, fielding and integrating many Linux clusters of various sizes into classified and unclassified production service through a concept of Scalable Units (SU). The programmatic objective is to dramatically reduce the overall Total Cost of Ownership (TCO) of these 'capacity' systems relative to the best practices in Linux Cluster deployments today. This objective only makes sense in the context of these systems quickly becoming very robust and useful production clusters under the crushing load that will be inflicted on them by the ASC and SSP scientific simulation capacity workload.

  13. High capacity immobilized amine sorbents

    DOE Patents [OSTI]

    Gray, McMahan L.; Champagne, Kenneth J.; Soong, Yee; Filburn, Thomas

    2007-10-30

    A method is provided for making low-cost CO.sub.2 sorbents that can be used in large-scale gas-solid processes. The improved method entails treating an amine to increase the number of secondary amine groups and impregnating the amine in a porous solid support. The method increases the CO.sub.2 capture capacity and decreases the cost of utilizing an amine-enriched solid sorbent in CO.sub.2 capture systems.

  14. Pennsylvania Nuclear Profile - Limerick

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

    Limerick" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration date" 1,"1,130","9,047",91.4,"BWR","application/vnd.ms-excel","application/vnd.ms-excel"

  15. Michigan Nuclear Profile - Fermi

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

    Fermi" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration date" 2,"1,085","7,738",81.4,"BWR","application/vnd.ms-excel","application/vnd.ms-excel" ,"

  16. Michigan Nuclear Profile - Palisades

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

    Palisades" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration date" 1,793,"6,241",89.8,"PWR","application/vnd.ms-excel","application/vnd.ms-excel" ,793,"6,241&

  17. Georgia Nuclear Profile - Vogtle

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

    Vogtle" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration date" 1,"1,150","10,247",101.7,"PWR","application/vnd.ms-excel","application/vnd.ms-excel"

  18. EIA - State Nuclear Profiles

    Gasoline and Diesel Fuel Update (EIA)

    85.5 BWR 1211969 492029 615 4,601 85.5 Data for 2010 BWR Boiling Water Reactor. ... The nuclear generating unit is a General Electric Type 2 boiling water reactor. ...

  19. Absolute nuclear material assay

    DOE Patents [OSTI]

    Prasad, Manoj K.; Snyderman, Neal J.; Rowland, Mark S.

    2012-05-15

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

  20. Absolute nuclear material assay

    DOE Patents [OSTI]

    Prasad, Manoj K.; Snyderman, Neal J.; Rowland, Mark S.

    2010-07-13

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