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Sample records for nuclear generating station

  1. California Nuclear Profile - San Onofre Nuclear Generating Station

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

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

  2. 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"

  3. 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"

  4. 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"

  5. 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"

  6. 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

  7. 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"

  8. 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"

  9. 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

  10. 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.

  11. 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.

  12. 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.

  13. 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

  14. 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.

  15. Peoples Generating Station Biomass Facility | Open Energy Information

    Open Energy Info (EERE)

    Peoples Generating Station Biomass Facility Jump to: navigation, search Name Peoples Generating Station Biomass Facility Facility Peoples Generating Station Sector Biomass Facility...

  16. Brent Run Generating Station Biomass Facility | Open Energy Informatio...

    Open Energy Info (EERE)

    Brent Run Generating Station Biomass Facility Jump to: navigation, search Name Brent Run Generating Station Biomass Facility Facility Brent Run Generating Station Sector Biomass...

  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. Utilities respond to nuclear station blackout rule

    SciTech Connect (OSTI)

    Rubin, A.M.; Beasley, B.; Tenera, L.P

    1990-02-01

    The authors discuss how nuclear plants in the United States have taken actions to respond to the NRC Station Blackout Rule, 10CFR50.63. The rule requires that each light water cooled nuclear power plant licensed to operate must be able to withstand for a specified duration and recover from a station blackout. Station blackout is defined as the complete loss of a-c power to the essential and non-essential switch-gear buses in a nuclear power plant. A station blackout results from the loss of all off-site power as well as the on-site emergency a-c power system. There are two basic approaches to meeting the station blackout rule. One is to cope with a station blackout independent of a-c power. Coping, as it is called, means the ability of a plant to achieve and maintain a safe shutdown condition. The second approach is to provide an alternate a-c power source (AAC).

  19. NRC Fact-Finding Task Force report on the ATWS event at Salem Nuclear Generating Station, Unit 1, on February 25, 1983

    SciTech Connect (OSTI)

    Not Available

    1983-03-01

    An NRC Region I Task Force was established on March 1, 1983 to conduct fact finding and data collection with regard to the circumstances which led to an anticipated transient without scram (ATWS) event at the Public Service Electric and Gas Company's Salem Generating Station, Unit 1 on February 25, 1983. The charter of the Task Force was to determine the factual information pertinent to management and administrative controls which should have ensured proper operation of the reactor trip breakers in the solid state protection system. This report documents the findings of the Task Force along with its conclusions.

  20. Illinois Nuclear Profile - Clinton Power Station

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

    Clinton Power Station" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration date" 1,"1,065","8,612",92.3,"BWR","application/vnd.ms-excel","application/vnd.ms-

  1. WWTP Power Generation Station Biomass Facility | Open Energy...

    Open Energy Info (EERE)

    WWTP Power Generation Station Sector Biomass Facility Type Non-Fossil Waste Location Alameda County, California Coordinates 37.6016892, -121.7195459 Show Map Loading map......

  2. Re: Potomac River Generating Station Department of Energy, Case...

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

    Columbia. PDF icon Department of Energy Order No. 202-05-03 Revised Notice of Planned Outages During January 2006 More Documents & Publications Re: Potomac River Generating Station ...

  3. 1,"Elm Road Generating Station","Coal","Wisconsin Electric Power...

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

    summer capacity (MW)" 1,"Elm Road Generating Station","Coal","Wisconsin Electric Power ... Electric Power Co",1190 4,"Columbia (WI)","Coal","Wisconsin Power & Light ...

  4. License Amendment Request for Storing Exelon Sister Nuclear Stations Class

    Office of Scientific and Technical Information (OSTI)

    B/C LLRW in the LaSalle Station Interim Radwaste Storage Facility - 13620 (Conference) | SciTech Connect License Amendment Request for Storing Exelon Sister Nuclear Stations Class B/C LLRW in the LaSalle Station Interim Radwaste Storage Facility - 13620 Citation Details In-Document Search Title: License Amendment Request for Storing Exelon Sister Nuclear Stations Class B/C LLRW in the LaSalle Station Interim Radwaste Storage Facility - 13620 Exelon Nuclear (Exelon) designed and constructed

  5. Potential failure of steam generator tubes following a station blackout

    SciTech Connect (OSTI)

    Ward, L.W.; Palmrose, D.E.

    1994-12-31

    The U.S. Nuclear Regulatory Commission is considering changes to pressurized water reactor (PWR) requirements relating to steam generator tube plugging and repair criteria, including leakage monitoring. The proposed changes are known as the alternate tube plugging criteria (APC) and are intended to permit PWRs to operate with through-wall cracks in steam generator tubes subject to meeting a specified limit on predicted primary to secondary leakage under accident conditions. To assess the consequences of the alternate plugging criteria, analyses were performed for a station blackout sequence in which the reactor core melts while the reactor coolant system (RCS) remains at high pressure. Evaluations were conducted to investigate the potential for tube failure with and without secondary system depressurization. The excessive heat coupled with the high-pressure differentials across the steam generator tubes could result in creep rupture failure of the tubes during a severe accident, which could lead to a radiological release directly to the environment. In order to assess the safety significance of the APC, it is important to identify the level of steam generator tube leakage that can occur without challenging the previous study conclusions that steam generator creep failure will not occur prior to a surge line or hot-leg failure. To assess the effect of leakage on steam generator tube integrity during a core melt sequence with the RCS at high pressure and the secondary side of the steam generators pressurized and depressurized, an analysis was performed for a core melt event resulting from an unmitigated station blackout to identify the total steamenerator and tube leakage flow rates that could induce tube ruptures prior to other RCS boudary faliures that could depressurize the RCS.

  6. Re: Potomac River Generating Station Department of Energy Case...

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

    Potomac Electric Power Company (PEPCO) Concerning Planned Outages of the 230 kV circuits Re: Potomac River Generating Station Department of Energy, Case No. EO-05-01: Potomac...

  7. Re: Potomac River Generating Station Department of Energy, Case...

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

    of the two 230 kV circuits serving the downtown area of the District of Columbia. ... More Documents & Publications Re: Potomac River Generating Station Department of Energy, Case ...

  8. Re: Potomac River Generating Station Department of Energy, Case...

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

    Re: Potomac River Generating Station Department of Energy, Case No. EO-05-01: Potomac Electric ... Extension of Order No. 202-05-3 of the District of Columbia Public Service Commission

  9. Navajo Generating Station and Air Visibility Regulations: Alternatives...

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

    ... Table 5-8. Visibility CostBenefit Comparisons 91 Table 6-1. Poverty Rates on Navajo and ... Figure 6-1. Navajo generating station tribe map NRELTP-6A20-53024 95 Table 6-1. Poverty ...

  10. 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)

  11. Navajo Generating Station and Air Visibility Regulations: Alternatives and Impacts

    SciTech Connect (OSTI)

    Hurlbut, D. J.; Haase, S.; Brinkman, G.; Funk, K.; Gelman, R.; Lantz, E.; Larney, C.; Peterson, D.; Worley, C.; Liebsch, E.

    2012-01-01

    Pursuant to the Clean Air Act, the U.S. Environmental Protection Agency (EPA) announced in 2009 its intent to issue rules for controlling emissions from Navajo Generating Station that could affect visibility at the Grand Canyon and at several other national parks and wilderness areas. The final rule will conform to what EPA determines is the best available retrofit technology (BART) for the control of haze-causing air pollutants, especially nitrogen oxides. While EPA is ultimately responsible for setting Navajo Generating Station's BART standards in its final rule, it will be the U.S. Department of the Interior's responsibility to manage compliance and the related impacts. This study aims to assist both Interior and EPA by providing an objective assessment of issues relating to the power sector.

  12. Re: Potomac River Generating Station Department of Energy Case No.

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

    EO-05-01: PEPCO is providing you with information regarding the planned transmission maintenance outage | Department of Energy PEPCO is providing you with information regarding the planned transmission maintenance outage Re: Potomac River Generating Station Department of Energy Case No. EO-05-01: PEPCO is providing you with information regarding the planned transmission maintenance outage Docket No. EO-05-01. Order No. 202-07-02: Per your request, Potomac Electric Power Company

  13. Elimination of direct current distribution systems from new generating stations

    SciTech Connect (OSTI)

    Jancauskas, J.R.

    1996-12-31

    This paper advances the concept that it may be both possible and advantageous to eliminate the traditional direct current distribution system from a new generating station. The latest developments in uninterruptible power supply (UPS) technology are what have made this option technically feasible. A traditional dc distribution system will be compared to an ac distribution system supplied by a UPS to investigate the merits of the proposed approach.

  14. License Amendment Request for Storing Exelon Sister Nuclear Stations Class B/C LLRW in the LaSalle Station Interim Radwaste Storage Facility - 13620

    SciTech Connect (OSTI)

    Azar, Miguel; Gardner, Donald A.; Taylor, Edward R.

    2013-07-01

    Exelon Nuclear (Exelon) designed and constructed an Interim Radwaste Storage Facility (IRSF) in the mid-1980's at LaSalle County Nuclear Station (LaSalle). The facility was designed to store low-level radioactive waste (LLRW) on an interim basis, i.e., up to five years. The primary reason for the IRSF was to offset lack of disposal in case existing disposal facilities, such as the Southeast Compact's Barnwell Disposal Facility in Barnwell, South Carolina, ceased accepting radioactive waste from utilities not in the Southeast Compact. Approximately ninety percent of the Radwaste projected to be stored in the LaSalle IRSF in that period of time was Class A, with the balance being Class B/C waste. On July 1, 2008 the Barnwell Disposal Facility in the Southeast Compact closed its doors to out of- compact Radwaste, which precluded LaSalle from shipping Class B/C Radwaste to an outside disposal facility. Class A waste generated by LaSalle is still able to be disposed at the 'Envirocare of Utah LLRW Disposal Complex' in Clive, Utah. Thus the need for utilizing the LaSalle IRSF for storing Class B/C Radwaste for an extended period, perhaps life-of-plant or more became apparent. Additionally, other Exelon Midwest nuclear stations located in Illinois that did not build an IRSF heretofore also needed extended Radwaste storage. In early 2009, Exelon made a decision to forward Radwaste from the Byron Nuclear Station (Byron), Braidwood Nuclear Station (Braidwood), and Clinton Nuclear Station (Clinton) to LaSalle's IRSF. As only Class B/C Radwaste would need to be forwarded to LaSalle, the original volumetric capacity of the LaSalle IRSF was capable of handling the small number of additional expected shipments annually from the Exelon sister nuclear stations in Illinois. Forwarding Class B/C Radwaste from the Exelon sister nuclear stations in Illinois to LaSalle would require an amendment to the LaSalle Station operating license. Exelon submitted the License Amendment Request (LAR) to NRC on January 6, 2010; NRC approved the LAR on July 21, 2011. A similar decision was made by Exelon in early 2009 to forward Radwaste from Limerick Nuclear Station to its sister station, the Peach Bottom Atomic Power Station; both in Pennsylvania. A LAR submittal to the NRC was also provided and NRC approval was received in 2011. (authors)

  15. Tri-Generation Success Story: World's First Tri-Gen EnergyStation...

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

    Tri-Generation Success Story: World's First Tri-Gen Energy Station-Fountain Valley Tri-Generation Success Story: World's First Tri-Gen Energy Station-Fountain Valley This Fuel Cell ...

  16. Re: Potomac River Generating Station Department of Energy Case No.

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

    EO-05-01: Advanced Notice of Power Outages. | Department of Energy Advanced Notice of Power Outages. Re: Potomac River Generating Station Department of Energy Case No. EO-05-01: Advanced Notice of Power Outages. Docket No. EO-05-01. Order No. 202-05-03: Potomac Electric Power Company ("Pepco"), on behalf of itself and PJM Interconnection, L.L.C. ("PJM"), is providing you with information regarding the planned transmission outages that are scheduled for the upcoming

  17. Re: Potomac River Generating Station Department of Energy, Case No.

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

    EO-05-01: Potomac Electric Power Company (PEPCO) evised plan for transmission outages for the 230 kV circuits | Department of Energy evised plan for transmission outages for the 230 kV circuits Re: Potomac River Generating Station Department of Energy, Case No. EO-05-01: Potomac Electric Power Company (PEPCO) evised plan for transmission outages for the 230 kV circuits Docket No. EO-05-01. Order No. 202-07-02: Potomac Electric Power Company ("Pepco") is providing you with the

  18. Nuclear Rocket Development Station at the Nevada Test Site | Department of

    Office of Environmental Management (EM)

    Energy Nuclear Rocket Development Station at the Nevada Test Site Nuclear Rocket Development Station at the Nevada Test Site During the 1950s, the United States launched a nuclear rocket program called Project Rover. PDF icon Nuclear Rocket Development Station More Documents & Publications Recovery Act Workers Demolish Facility Tied to Project Pluto History Gap Analysis to Support Extended Storage of Used Nuclear Fuel Enforcement Letter, Bechtel Nevada - April 1, 2002

  19. Notification of Planned 230kV Outage at Potomac River Generating Station

    Energy Savers [EERE]

    Sent: Wednesday, May 16, 2007 4:49 PM To: #DOE_Notification@pepco.com Subject: Notification of Planned 230kV Outage at Potomac River Generating Station To Whom It May Concern: This morning Pepco and PJM observed that the generation at the Potomac River Generating Station was having difficulty matching the station generation requirement to the Potomac River area load. Mirant has also informed Pepco and PJM that several generating units were experiencing equipment problems which required them to

  20. Machinery monitoring system installed at nuclear power station

    SciTech Connect (OSTI)

    Piety, K.; Hamrick, L.; McCurdy, A.

    1981-10-01

    The Grand Gulf Nuclear Station under construction in Mississippi will have a computer-based system to monitor 300 process variables and 200 vibration signals in each of the two units. The system's functions include monitoring support, startup/shutdown, surveillance, and diagnostics. The tasks associated with machinery monitoring are broken down into the initial plant design, construction and startup testing, and power-operation phases. The value of this monitoring is discussed and summarized in a table showing the impact of component failure on plant availability. 4 figures, 3 tables. (DCK)

  1. World's First Tri-Generation Fuel Cell and Hydrogen Fueling Station |

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

    Department of Energy Tri-Generation Fuel Cell and Hydrogen Fueling Station World's First Tri-Generation Fuel Cell and Hydrogen Fueling Station April 18, 2013 - 12:00am Addthis EERE supported the development of the world's first tri-generation station-a combined heat and power system that produces hydrogen in addition to heat and electricity-in Fountain Valley. The system runs on natural gas and biogas generated by the Orange County Sanitation District's wastewater treatment facility.

  2. Enhancement of NRC station blackout requirements for nuclear power plants

    SciTech Connect (OSTI)

    McConnell, M. W.

    2012-07-01

    The U.S. Nuclear Regulatory Commission (NRC) established a Near-Term Task Force (NTTF) in response to Commission direction to conduct a systematic and methodical review of NRC processes and regulations to determine whether the agency should make additional improvements to its regulatory system and to make recommendations to the Commission for its policy direction, in light of the accident at the Fukushima Dai-ichi Nuclear Power Plant. The NTTF's review resulted in a set of recommendations that took a balanced approach to defense-in-depth as applied to low-likelihood, high-consequence events such as prolonged station blackout (SBO) resulting from severe natural phenomena. Part 50, Section 63, of Title 10 of the Code of Federal Regulations (CFR), 'Loss of All Alternating Current Power,' currently requires that each nuclear power plant must be able to cool the reactor core and maintain containment integrity for a specified duration of an SBO. The SBO duration and mitigation strategy for each nuclear power plant is site specific and is based on the robustness of the local transmission system and the transmission system operator's capability to restore offsite power to the nuclear power plant. With regard to SBO, the NTTF recommended that the NRC strengthen SBO mitigation capability at all operating and new reactors for design-basis and beyond-design-basis external events. The NTTF also recommended strengthening emergency preparedness for prolonged SBO and multi-unit events. These recommendations, taken together, are intended to clarify and strengthen US nuclear reactor safety regarding protection against and mitigation of the consequences of natural disasters and emergency preparedness during SBO. The focus of this paper is on the existing SBO requirements and NRC initiatives to strengthen SBO capability at all operating and new reactors to address prolonged SBO stemming from design-basis and beyond-design-basis external events. The NRC initiatives are intended to enhance core and spent fuel pool cooling, reactor coolant system integrity, and containment integrity. (authors)

  3. DESIGNING AN OPPORTUNITY FUEL WITH BIOMASS AND TIRE-DERIVED FUEL FOR COFIRING AT WILLOW ISLAND GENERATING STATION AND COFIRING SAWDUST WITH COAL AT ALBRIGHT GENERATING STATION

    SciTech Connect (OSTI)

    K. Payette; D. Tillman

    2003-07-01

    During the period April 1, 2003--June 30, 2003, Allegheny Energy Supply Co., LLC (Allegheny) proceeded with demonstration operations at the Willow Island Generating Station and improvements to the Albright Generating Station cofiring systems. The demonstration operations at Willow Island were designed to document integration of biomass cofiring into commercial operations. The Albright improvements were designed to increase the resource base for the projects, and to address issues that came up during the first year of operations. This report summarizes the activities associated with the Designer Opportunity Fuel program, and demonstrations at Willow Island and Albright Generating Stations.

  4. EIS-0435: Modification of the Groton Generation Station Interconnection Agreement, Brown County, South Dakota

    Broader source: Energy.gov [DOE]

    This EIS evaluates the environmental impacts of a proposal for DOE's Western Area Power Administration to modify its Large Generator Connection Agreement for the Groton Generation Station in Brown County, South Dakota. The modification would allow Basin Electric Power Cooperative, which operates the generation station, to produce power above the current operating limit of 50 average megawatts.

  5. 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.

  6. 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

  7. Radwaste assessment program for nuclear station modifications by design engineering

    SciTech Connect (OSTI)

    Eble, R.G.

    1988-01-01

    Radwaste burial for Duke Power Company's (DPC's) seven nuclear units has become a complicated and costly process. Burial costs are based on overall volume, surcharges for radioactivity content and weight of containers, truck and cask rental, driver fees, and state fees and taxes. Frequently, radwaste costs can be as high as $500 per drum. Additionally, DPC is limited on the total burial space allocated for each plant each year. The thrust of this program is to reduce radwaste volumes needing burial at either Barnwell, South Carolina, or Richland, Washington. A limited number of options are available at our sites: (a) minimization of radwaste volume production, (b) segregation of contamination and noncontaminated trash, (c) decontamination of small hardware, (d) volume reduction of compatible trash, (e) incineration of combustible trash (available at Oconee in near future), and (f) burial of below-regulatory-concern very low level waste on site. Frequently, costs can be reduced by contracting services outside the company, i.e., supercompaction, decontamination, etc. Information about radwaste volumes, activities, and weight, however, must be provided to the nuclear production department (NPD) radwaste group early in the nuclear station modification (NSM) process to determine the most cost-effective method of processing radwaste. In addition, NSM radwaste costs are needed for the NPD NSM project budget. Due to the advanced planning scope of this budget, NSM construction costs must be estimated during the design-phase proposal.

  8. Next Generation Hydrogen Station Composite Data Products: Data through Quarter 2 of 2013

    SciTech Connect (OSTI)

    Sprik, S.; Kurtz, J.; Ainscough, C.; Post, M.; Saur, G.; Peters, M.

    2013-11-01

    This report includes 18 composite data products (CDPs) produced for next generation hydrogen stations, with data through quarter 2 of 2013.

  9. Next Generation Hydrogen Station Composite Data Products: Data through Quarter 4 of 2013

    SciTech Connect (OSTI)

    Sprik, S.; Kurtz, J.; Peters, M.

    2014-05-01

    This report includes 25 composite data products (CDPs) produced for next generation hydrogen stations, with data through quarter 4 of 2013.

  10. Study of Fukushima Dai-ichi Nuclear Power Station Unit 4 Spent...

    Office of Scientific and Technical Information (OSTI)

    Journal Article: Study of Fukushima Dai-ichi Nuclear Power Station Unit 4 Spent Fuel Pool Citation Details In-Document Search Title: Study of Fukushima Dai-ichi Nuclear Power...

  11. Tri-Generation Success Story: World's First Tri-Gen Energy Station - Fountain Valley

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

    Tri-Generation Success Story World's First Tri-Gen Energy Station- Fountain Valley The Fountain Valley energy station, supported in part by a $2.2 million grant from the Energy Department, is the world's frst tri-generation hydrogen energy and electrical power station to provide transportation fuel to the public and electric power to an industrial facility. Located at the Orange County Sanitation District's wastewater treatment plant in Fountain Valley, California, the unit is a combined heat,

  12. U.S. Nuclear Generation of Electricity

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

    Year Capacity and Generation by State and Reactor 2015 P XLS ... data information in the Annual Energy Review, table 9.2. U. S. Nuclear power plants projected electricity ...

  13. Notification of Planned 230kV Outage at Potomac River Generating Station |

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

    Department of Energy In accordance with DOE Order No. 202-05-03 Pepco is required to provide notification of any and all 230kV planned outages at Potomac River Generating Station. On Tuesday February 20, 2007 Potomac Electric Power Company (Pepco) will be taking a planned outage on the 23106 high voltage circuit between the Palmer's Corner Substation and the Potomac River Generating Station. PDF icon Notification of Planned 230kV Outage at Potomac River Generating Station More Documents

  14. Notification of Planned 230kV Outage at Potomac River Generating Station |

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

    Department of Energy The next planned outage on xxxxx high voltage circuit between Palmers Corner Substation and the Potomac River Generating Station is scheduled for Sunday, June 3, 2007 and will begin at 4:00 AM with a scheduled return date of Saturday, June 9, 2007 at 2:00 PM. PDF icon Notification of Planned 230kV Outage at Potomac River Generating Station More Documents & Publications Notification of Planned 230kV Outage at Potomac River Generating Station Notification of Planned

  15. Re: Potomac River Generating Station Department of Energy, Case No.

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

    EO-05-01: Potomac Electric Power Company (PEPCO) Concerning Planned Outages of the 230 kV circuits | Department of Energy EO-05-01: Pursuant to the United States Department of Energy ("DOE") Order No. 202-05-3, issued December 20, 2005 ("DOE Potomac River Order") Pepco hereby files this revised notice of the planned outage of the 230 kV circuits serving the Potomac River Substation, and through that station, the District of Columbia. PDF icon Department of Energy Order

  16. 1,"Chuck Lenzie Generating Station","Natural gas","Nevada Power...

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

    Co",522 9,"Apex Generating Station","Natural gas","Los Angeles Department of Water & Power",494.4 10,"Desert Star Energy Center","Natural gas","Desert Star Energy Center SDG&E",45

  17. Recovery sequences for a station blackout accident at the Grand Gulf Nuclear Station

    SciTech Connect (OSTI)

    Carbajo, J.J. [Martin Marietta Energy Systems, Oak Ridge, TN (United States)

    1995-12-31

    Recovery sequences for a low-pressure, short term, station blackout severe accident at the Grand Gulf power plant have been investigated using the computer code MELCOR, version 1.8.3 PN. This paper investigates the effect of reflood timing and mass flow rate on accident recovery.

  18. Investigation of waste rag generation at Naval Station Mayport. Project report, May 1990-July 1993

    SciTech Connect (OSTI)

    1995-08-01

    The report presents the results of an investigation examining pollution prevention alternatives for reducing the volume of waste rags generated at Naval Station Mayport, located near Jacksonville Beach, Florida. The report recommends five specific pollution prevention alternatives: better operating practices, installation of equipment cleaning stations to remove contaminants normally removed with rags; replacement of SERVE MART rags with disposable wipers; use of recyclable rats for oil and great removal; and confirmation that used rags are fully contaminated prior to disposal.

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

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

    Fostering the Next Generation of Nuclear Energy Technology Peter W. Davidson Peter W. ... make available 12.6 billion in loan guarantees for advanced nuclear energy technologies. ...

  20. DESIGNING AND OPPORTUNITY FUEL WITH BIOMASS AND TIRE-DERIVED FUEL FOR COFIRING AT WILLOW ISLAND GENERATING STATION AND COFIRING SAWDUST WITH COAL AT ALBRIGHT GENERATING STATION

    SciTech Connect (OSTI)

    K. Payette; D. Tillman

    2004-06-01

    During the period July 1, 2000-March 31, 2004, Allegheny Energy Supply Co., LLC (Allegheny) conducted an extensive demonstration of woody biomass cofiring at its Willow Island and Albright Generating Stations. This demonstration, cofunded by USDOE and Allegheny, and supported by the Biomass Interest Group (BIG) of EPRI, evaluated the impacts of sawdust cofiring in both cyclone boilers and tangentially-fired pulverized coal boilers. The cofiring in the cyclone boiler--Willow Island Generating Station Unit No.2--evaluated the impacts of sawdust alone, and sawdust blended with tire-derived fuel. The biomass was blended with the coal on its way to the combustion system. The cofiring in the pulverized coal boiler--Albright Generating Station--evaluated the impact of cofiring on emissions of oxides of nitrogen (NO{sub x}) when the sawdust was injected separately into the furnace. The demonstration of woody biomass cofiring involved design, construction, and testing at each site. The results addressed impacts associated with operational issues--capacity, efficiency, and operability--as well as formation and control of airborne emissions such as NO{sub x}, sulfur dioxide (SO{sub 2}2), opacity, and mercury. The results of this extensive program are detailed in this report.

  1. 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.

  2. 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.

  3. Meeting the Next Generation of Nuclear Nonproliferation Specialists |

    National Nuclear Security Administration (NNSA)

    National Nuclear Security Administration Meeting the Next Generation of Nuclear Nonproliferation Specialists | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact

  4. Next Generation Hydrogen Station Composite Data Products: Data through Quarter 4 of 2014; NREL (National Renewable Energy Laboratory)

    SciTech Connect (OSTI)

    Sprik, S.; Kurtz, J.; Ainscough, C.; Peters, M.

    2015-05-14

    This publication includes 43 composite data products (CDPs) produced for next generation hydrogen stations, with data through the fourth quarter of 2014.

  5. The network architecture and site test of DCIS in Lungmen nuclear power station

    SciTech Connect (OSTI)

    Lee, C. K.

    2006-07-01

    The Lungmen Nuclear Power Station (LMNPS) is located in North-Eastern Seashore of Taiwan. LMNPP has two units. Each unit generates 1350 Megawatts. It is the first ABWR Plant in Taiwan and is under-construction now. Due to contractual arrangement, there are seven large I and C suppliers/designers, which are GE NUMAC, DRS, Invensys, GEIS, Hitachi, MHI, and Stone and Webster company. The Distributed Control and Information System (DCIS) in Lungmen are fully integrated with the state-of-the-art computer and network technology. General Electric is the leading designer for integration of DCIS. This paper presents Network Architecture and the Site Test of DCIS. The network architectures are follows. GE NUMAC System adopts the point to point architecture, DRS System adopts Ring type architecture with SCRAMNET protocol, Inevnsys system adopts IGiga Byte Backbone mesh network with Rapid Spanning Tree Protocol, GEIS adopts Ethernet network with EGD protocol, Hitachi adopts ring type network with proprietary protocol. MHI adopt Ethernet network with UDP. The data-links are used for connection between different suppliers. The DCIS architecture supports the plant automation, the alarm prioritization and alarm suppression, and uniform MMI screen for entire plant. The Test Program regarding the integration of different network architectures and Initial DCIS architecture Setup for 161KV Energization will be discussed. Test tool for improving site test schedule, and lessons learned from FAT will be discussed too. And conclusions are at the end of this paper. (authors)

  6. Steam Dryer Segmentation and Packaging at Grand Gulf Nuclear Station - 13577

    SciTech Connect (OSTI)

    Kreitman, Paul J.; Sirianni, Steve R.; Pillard, Mark M.

    2013-07-01

    Entergy recently performed an Extended Power Up-rate (EPU) on their Grand Gulf Nuclear Station, near Port Gibson, Mississippi. To support the EPU, a new Steam Dryer Assembly was installed during the last refueling outage. Due to limited access into the containment, the large Replacement Steam Dryer (RSD) had to be brought into the containment in pieces and then final assembly was completed on the refueling floor before installation into the reactor. Likewise, the highly contaminated Original Steam Dryer (OSD) had to be segmented into manageable sections, loaded into specially designed shielded containers, and rigged out of containment where they will be safely stored until final disposal is accomplished at an acceptable waste repository. Westinghouse Nuclear Services was contracted by Entergy to segment, package and remove the OSD from containment. This work was performed on critical path during the most recent refueling outage. The segmentation was performed underwater to minimize radiation exposure to the workers. Special hydraulic saws were developed for the cutting operations based on Westinghouse designs previously used in Sweden to segment ABB Reactor Internals. The mechanical cutting method was selected because of its proven reliability and the minimal cutting debris that is generated by the process. Maintaining stability of the large OSD sections during cutting was accomplished using a custom built support stand that was installed into the Moisture Separator Pool after the Moisture Separator was installed back in the reactor vessel. The OSD was then moved from the Steam Dryer Pool to the Moisture Separator Pool for segmentation. This scenario resolved the logistical challenge of having two steam dryers and a moisture separator in containment simultaneously. A water filtration/vacuum unit was supplied to maintain water clarity during the cutting and handling operations and to collect the cutting chips. (authors)

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

    Energy Savers [EERE]

    Department of Energy Industry Participation Sought for Design of Next Generation Nuclear Plant Industry Participation Sought for Design of Next Generation Nuclear Plant June 29, 2006 - 2:41pm Addthis Gen IV Reactor Capable of Producing Electricity and/or Hydrogen WASHINGTON, DC - The U.S. Department of Energy (DOE) is seeking expressions of interest from prospective industry teams interested in participating in the development and conceptual design for the Next Generation Nuclear Plant

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

    Energy Savers [EERE]

    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

  9. Reactor Vessel and Reactor Vessel Internals Segmentation at Zion Nuclear Power Station - 13230

    SciTech Connect (OSTI)

    Cooke, Conrad; Spann, Holger

    2013-07-01

    Zion Nuclear Power Station (ZNPS) is a dual-unit Pressurized Water Reactor (PWR) nuclear power plant located on the Lake Michigan shoreline, in the city of Zion, Illinois approximately 64 km (40 miles) north of Chicago, Illinois and 67 km (42 miles) south of Milwaukee, Wisconsin. Each PWR is of the Westinghouse design and had a generation capacity of 1040 MW. Exelon Corporation operated both reactors with the first unit starting production of power in 1973 and the second unit coming on line in 1974. The operation of both reactors ceased in 1996/1997. In 2010 the Nuclear Regulatory Commission approved the transfer of Exelon Corporation's license to ZionSolutions, the Long Term Stewardship subsidiary of EnergySolutions responsible for the decommissioning of ZNPS. In October 2010, ZionSolutions awarded Siempelkamp Nuclear Services, Inc. (SNS) the contract to plan, segment, remove, and package both reactor vessels and their respective internals. This presentation discusses the tools employed by SNS to remove and segment the Reactor Vessel Internals (RVI) and Reactor Vessels (RV) and conveys the recent progress. SNS's mechanical segmentation tooling includes the C-HORCE (Circumferential Hydraulically Operated Cutting Equipment), BMT (Bolt Milling Tool), FaST (Former Attachment Severing Tool) and the VRS (Volume Reduction Station). Thermal segmentation of the reactor vessels will be accomplished using an Oxygen- Propane cutting system. The tools for internals segmentation were designed by SNS using their experience from other successful reactor and large component decommissioning and demolition (D and D) projects in the US. All of the designs allow for the mechanical segmentation of the internals remotely in the water-filled reactor cavities. The C-HORCE is designed to saw seven circumferential cuts through the Core Barrel and Thermal Shield walls with individual thicknesses up to 100 mm (4 inches). The BMT is designed to remove the bolts that fasten the Baffle Plates to the Baffle Former Plates. The FaST is designed to remove the Baffle Former Plates from the Core Barrel. The VRS further volume reduces segmented components using multiple configurations of the 38i and horizontal reciprocating saws. After the successful removal and volume reduction of the Internals, the RV will be segmented using a 'First in the US' thermal cutting process through a co-operative effort with Siempelkamp NIS Ingenieurgesellschaft mbH using their experience at the Stade NPP and Karlsruhe in Germany. SNS mobilized in the fall of 2011 to commence execution of the project in order to complete the RVI segmentation, removal and packaging activities for the first unit (Unit 2) by end of the 2012/beginning 2013 and then mobilize to the second unit, Unit 1. Parallel to the completion of the segmentation of the reactor vessel internals at Unit 1, SNS will segment the Unit 2 pressure vessel and at completion move to Unit 1. (authors)

  10. 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.

  11. NNSA Next Generation Safeguards Initiative | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration Next Generation Safeguards Initiative | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo Gallery Jobs Apply

  12. LLNL to deliver next-generation supercomputer | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration LLNL to deliver next-generation supercomputer | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo Gallery

  13. Thermal Modeling of NUHOMS HSM-15 and HSM-1 Storage Modules at Calvert Cliffs Nuclear Power Station ISFSI

    SciTech Connect (OSTI)

    Suffield, Sarah R.; Fort, James A.; Adkins, Harold E.; Cuta, Judith M.; Collins, Brian A.; Siciliano, Edward R.

    2012-10-01

    As part of the Used Fuel Disposition Campaign of the Department of Energy (DOE), visual inspections and temperature measurements were performed on two storage modules in the Calvert Cliffs Nuclear Power Stations Independent Spent Fuel Storage Installation (ISFSI). Detailed thermal models models were developed to obtain realistic temperature predictions for actual storage systems, in contrast to conservative and bounding design basis calculations.

  14. Table 8.2. Cost and performance characteristics of new central station electricity generating technologies

    Gasoline and Diesel Fuel Update (EIA)

    Table 8.2. Cost and performance characteristics of new central station electricity generating technologies Contingency Factors Technology Online Year 1 Size (MW) Lead time (years) Base Overnight Cost in 2014 (2013 $/kW) Project Contin- gency Factor 2 Techno- logical Optimism Factor 3 Total Overnight Cost in 2014 4 (2013 $/kW) Variable O&M 5 (2013 $/mWh) Fixed O&M (2013 $/ kW/yr.) Heatrate 6 in 2014 (Btu/ kWh) nth-of-a- kind Heatrate (Btu/kWh Scrubbed Coal New 2018 1300 4 2,726 1.07 1.00

  15. Potomac River Generating Station Dept. of Energy Case No. EO-05-01; September 8, 2005

    Energy Savers [EERE]

    Craig A. Glazer Vice President - Federal Government Policy PJM Washington Office (202) 393-7756 .FAX (202) 393-7741 e-mail: glazec@pjm.com CRITICAL ENERGY INFRASTRUCTURE INFORMATION HAS BEEN REMOVED FROM THIS SUBMITTAL FOR PRIVILEGED TREATMENT September 8, 2005 Lawrence Mansueti Office of Electricity Delivery and Energy Reliability U.S. Department of Energy Rm. 8H-033 1000 Independence Avenue Washington, D.C. 20585 Re: Potomac River Generating Station Dept. of Energy Case No. EO-05-01 Dear Mr.

  16. The AP1000{sup R} nuclear power plant innovative features for extended station blackout mitigation

    SciTech Connect (OSTI)

    Vereb, F.; Winters, J.; Schulz, T.; Cummins, E.; Oriani, L. [Westinghouse Electric Company LLC, 1000 Westinghouse Drive, Cranberry Township, PA 16066 (United States)

    2012-07-01

    Station Blackout (SBO) is defined as 'a condition wherein a nuclear power plant sustains a loss of all offsite electric power system concurrent with turbine trip and unavailability of all onsite emergency alternating current (AC) power system. Station blackout does not include the loss of available AC power to buses fed by station batteries through inverters or by alternate AC sources as defined in this section, nor does it assume a concurrent single failure or design basis accident...' in accordance with Reference 1. In this paper, the innovative features of the AP1000 plant design are described with their operation in the scenario of an extended station blackout event. General operation of the passive safety systems are described as well as the unique features which allow the AP1000 plant to cope for at least 7 days during station blackout. Points of emphasis will include: - Passive safety system operation during SBO - 'Fail-safe' nature of key passive safety system valves; automatically places the valve in a conservatively safe alignment even in case of multiple failures in all power supply systems, including normal AC and battery backup - Passive Spent Fuel Pool cooling and makeup water supply during SBO - Robustness of AP1000 plant due to the location of key systems, structures and components required for Safe Shutdown - Diverse means of supplying makeup water to the Passive Containment Cooling System (PCS) and the Spent Fuel Pool (SFP) through use of an engineered, safety-related piping interface and portable equipment, as well as with permanently installed onsite ancillary equipment. (authors)

  17. Next Generation Nuclear Plant: A Report to Congress

    Broader source: Energy.gov [DOE]

    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...

  18. 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"

  19. Method and apparatus for generating low energy nuclear particles

    DOE Patents [OSTI]

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

    1999-02-09

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

  20. 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.

  1. 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.

  2. MELCOR Analysis of Steam Generator Tube Creep Rupture in Station Blackout Severe Accident

    SciTech Connect (OSTI)

    Liao, Y.; Vierow, K. [Purdue University (United States)

    2005-12-15

    A pressurized water reactor steam generator tube rupture (SGTR) is of concern because it represents a bypass of the containment for radioactive materials to the environment. In a station blackout accident, tube integrity could be threatened by creep rupture, particularly if cracks are present in the tube walls. Methods are developed herein to improve assessment capabilities for SGTR by using the severe-accident code MELCOR. Best-estimate assumptions based on recent research and computational fluid dynamics calculations are applied in the MELCOR analysis to simulate two-dimensional natural circulation and to determine the relative creep-rupture timing in the reactor coolant pressure boundary components. A new method is developed to estimate the steam generator (SG) hottest tube wall temperature and the tube critical crack size for the SG tubes to fail first. The critical crack size for SG tubes to fail first is estimated to be 20% of the wall thickness larger than by a previous analysis. Sensitivity studies show that the failure sequence would change if some assumptions are modified. In particular, the uncertainty in the countercurrent flow limit model could reverse the failure sequence of the SG tubes and surge line.

  3. Table 2. Ten Largest Plants by Generation Capacity, 2013

    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 Station","Nuclear","Exelon Nuclear",2300 3,"LaSalle Generating Station","Nuclear","Exelon Nuclear",2277 4,"Quad Cities Generating Station","Nuclear","Exelon

  4. 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.

  5. Underground nuclear power station using self-regulating heat-pipe controlled reactors

    DOE Patents [OSTI]

    Hampel, Viktor E.

    1989-01-01

    A nuclear reactor for generating electricity is disposed underground at the bottom of a vertical hole that can be drilled using conventional drilling technology. The primary coolant of the reactor core is the working fluid in a plurality of thermodynamically coupled heat pipes emplaced in the hole between the heat source at the bottom of the hole and heat exchange means near the surface of the earth. Additionally, the primary coolant (consisting of the working flud in the heat pipes in the reactor core) moderates neutrons and regulates their reactivity, thus keeping the power of the reactor substantially constant. At the end of its useful life, the reactor core may be abandoned in place. Isolation from the atmosphere in case of accident or for abandonment is provided by the operation of explosive closures and mechanical valves emplaced along the hole. This invention combines technology developed and tested for small, highly efficient, space-based nuclear electric power plants with the technology of fast-acting closure mechanisms developed and used for underground testing of nuclear weapons. This invention provides a nuclear power installation which is safe from the worst conceivable reactor accident, namely, the explosion of a nuclear weapon near the ground surface of a nuclear power reactor.

  6. An underground nuclear power station using self-regulating heat-pipe controlled reactors

    DOE Patents [OSTI]

    Hampel, V.E.

    1988-05-17

    A nuclear reactor for generating electricity is disposed underground at the bottom of a vertical hole that can be drilled using conventional drilling technology. The primary coolant of the reactor core is the working fluid in a plurality of thermodynamically coupled heat pipes emplaced in the hole between the heat source at the bottom of the hole and heat exchange means near the surface of the earth. Additionally, the primary coolant (consisting of the working fluid in the heat pipes in the reactor core) moderates neutrons and regulates their reactivity, thus keeping the power of the reactor substantially constant. At the end of its useful life, the reactor core may be abandoned in place. Isolation from the atmosphere in case of accident or for abandonment is provided by the operation of explosive closures and mechanical valves emplaced along the hole. This invention combines technology developed and tested for small, highly efficient, space-based nuclear electric power plants with the technology of fast- acting closure mechanisms developed and used for underground testing of nuclear weapons. This invention provides a nuclear power installation which is safe from the worst conceivable reactor accident, namely, the explosion of a nuclear weapon near the ground surface of a nuclear power reactor. 5 figs.

  7. EIS-0092: Conversion to Coal, Holyoke Water Power Company, Mt. Tom Generating Station Unit 1 Holyoke, Hampden County, Massachusetts

    Broader source: Energy.gov [DOE]

    The Economic Regulatory Administration prepared this statement to assess the environmental impacts of prohibiting Unit 1 of the Mt. Tom Generation Station Unit 1 from using either natural gas or petroleum products as a primary energy source, which would result in the utility burning low-sulfur coal.

  8. Navajo Generating Station and Clean-Energy Alternatives: Options for Renewables

    SciTech Connect (OSTI)

    Hurlbut, D. J.; Haase, S.; Turchi, C. S.; Burman, K.

    2012-06-01

    In January 2012, the National Renewable Energy Laboratory delivered to the Department of the Interior the first part of a study on Navajo Generating Station (Navajo GS) and the likely impacts of BART compliance options. That document establishes a comprehensive baseline for the analysis of clean energy alternatives, and their ability to achieve benefits similar to those that Navajo GS currently provides. This analysis is a supplement to NREL's January 2012 study. It provides a high level examination of several clean energy alternatives, based on the previous analysis. Each has particular characteristics affecting its relevance as an alternative to Navajo GS. It is assumed that the development of any alternative resource (or portfolio of resources) to replace all or a portion of Navajo GS would occur at the end of a staged transition plan designed to reduce economic disruption. We assume that replacing the federal government's 24.3% share of Navajo GS would be a cooperative responsibility of both the U.S. Bureau of Reclamation (USBR) and the Central Arizona Water Conservation District (CAWCD).

  9. 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

  10. 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.

  11. 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.

  12. Direction on characterization of fuel debris for defueling process in Fukushima Daiichi Nuclear Power Station

    SciTech Connect (OSTI)

    Yano, Kimihiko; Kitagaki, Toru; Ikeuchi, Hirotomo; Wakui, Ryohei; Higuchi, Hidetoshi; Kaji, Naoya; Koizumi, Kenji; Washiya, Tadahiro

    2013-07-01

    For the decommissioning of Fukushima Daiichi Nuclear Power Station (1F), defueling of the fuel debris in the reactor core of Units 1-3 is planned to start within 10 years. Preferential items in the characterization of the fuel debris were identified for this work, in which the procedure and handling tools were assumed on the basis of information on 1F and experience after the Three Mile Island Unit 2 (TMI-2) accident. The candidates for defueling tools for 1F were selected from among the TMI- 2 defueling tools. It was found that they could be categorized into six groups according to their operating principles. The important properties of the fuel debris for defueling were selected considering the effect of the target materials on the tool performance. The selected properties are shape, size, density, thermal conductivity, heat capacity, melting point, hardness, elastic modulus, and fracture toughness. Of these properties, the mechanical properties (hardness, elastic modulus, fracture toughness) were identified as preferential items, because too few data on these characteristics of fuel debris are available in past severe accident studies. (authors)

  13. 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.

  14. Evaluation of station blackout accidents at nuclear power plants: Technical findings related to unresolved safety issue A-44: Final report

    SciTech Connect (OSTI)

    Not Available

    1988-06-01

    ''Station Blackout,'' which is the complete loss of alternating current (AC) electrical power in a nuclear power plant, has been designated as Unresolved Safety Issue A-44. Because many safety systems required for reactor core decay heat removal and containment heat removal depend on AC power, the consequences of a station blackout could be severe. This report documents the findings of technical studies performed as part of the program to resolve this issue. The important factors analyzed include: the fequency of loss of offsite power; the probability that emergency or onsite AC power supplies would be unavailable; the capability and reliability of decay heat removal systems independent of AC power; and the likelihood that offsite power would be restored before systems that cannot operate for extended periods without AC power fail, thus resulting in core damage. This report also addresses effects of different designs, locations, and operational features on the estimated frequency of core damage resulting from station blackout events.

  15. World's First Tri-Generation Fuel Cell and Hydrogen Fueling Station...

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

    The system runs on natural gas and biogas generated by the Orange County Sanitation ... out the tri-generation facility that uses biogas from Orange County Sanitation District's ...

  16. 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.

  17. Sorption (Kd) measurements in support of dose assessments for Zion Nuclear Station Decommissioning

    SciTech Connect (OSTI)

    Yim S. P.; Sullivan T.; Milian, L.

    2012-12-12

    The Zion Nuclear Power Station is being decommissioned. ZionSolutions proposes to leave much of the below grade structures in place and to fill them with clean concrete demolition debris from the above grade parts of the facility. This study, commissioned by ZionSolutions and conducted by the Brookhaven National Laboratory (BNL) was performed to provide site-specific data for performance assessment calculations to support the request to terminate the NRC license and allow unrestricted use of the facility. Specifically, this study measured the distribution coefficient for five radionuclides of concern using site-specific soils and groundwater. The distributions coefficient is a measure of the amount of the radionuclide that will remain sorbed to the soil or concrete that is present relative to the amount that will remain in solution. A high distribution coefficient indicates most of the radionuclide will remain on the solid material and will not be available for transport by the groundwater. The radionuclides of concern are Fe-55, Co-60, Ni-63, Sr-90, and Cs-137. Tests were performed following ASTM C1733-10, Standard Test Methods for Distribution Coefficients of Inorganic Species by the Batch Method. Sr-85 was used in the testing as an analogue for Sr-90 because it behaves similarly with respect to sorption and has a gamma emission that is easier to detect than the beta emission from Sr-90. Site-specific soils included disturbed sand (sand removed during construction and used as backfill), native sand, silt/clay and silt. In addition, concrete cores from the Unit-1 Containment Building and the Crib House were broken into particles less than 2 mm in size and tested to obtain distribution coefficients for the five nuclides.

  18. 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 –

  19. Hydrogen Mitigation Strategy of the APR1400 Nuclear Power Plant for a Hypothetical Station Blackout Accident

    SciTech Connect (OSTI)

    Kim, Jongtae; Hong, Seong-Wan; Kim, Sang-Baik; Kim, Hee-Dong [Korea Atomic Energy Research Institute (Korea, Republic of)

    2005-06-15

    In order to analyze the hydrogen distribution during a hypothetical station blackout accident in the Korean next-generation Advanced Power Reactor 1400 (APR1400) containment, the three-dimensional computational fluid dynamics code GASFLOW was used. The source of the hydrogen and steam for the GASFLOW analysis was obtained from a MAAP calculation. The discharged water, steam, and hydrogen from the pressurizer are released into the water of the in-containment refueling water storage tank (IRWST). Most of the discharged steam is condensed in the IRWST water because of its subcooling, and dry hydrogen is released into the free volume of the IRWST; finally, it goes out to the annular compartment above the IRWST through the vent holes. From the GASFLOW analysis, it was found that the gas mixture in the IRWST becomes quickly nonflammable by oxygen starvation but the hydrogen is accumulated in the annular compartment because of the narrow ventilation gap between the operating deck and containment wall when the igniters installed in the IRWST are not operated. When the igniters installed in the APR1400 were turned on, a short period of burning occurred in the IRWST, and then the flame was extinguished by the oxygen starvation in the IRWST. The unburned hydrogen was released into the annular compartment and went up to the dome because no igniters are installed around the annular compartment in the base design of the APR1400. From this result, it could be concluded that the control of the hydrogen concentration is difficult for the base design. In this study design modifications are proposed and evaluated with GASFLOW in view of the hydrogen mitigation strategy.

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

    SciTech Connect (OSTI)

    Brown, L.C.

    2002-11-01

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

  1. Washington DC Reliability Requirements and the Need to Operate Mirant’s Potomac River Generation Station to Support Local Area Reliability (Oak Ridge National Laboratory 2005)

    Broader source: Energy.gov [DOE]

    Pursuant to Docket No. EO-05-01: Oak Ridge National Laboratory provided an analysis of the Mirant Potomac River Generation Station in 2005 and discussed the reliability requirements of the local...

  2. 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.

  3. 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

  4. 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 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.

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

    Energy Savers [EERE]

    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

  6. 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.

  7. 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.

  8. 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.

  9. 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.

  10. 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.

  11. 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.

  12. 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.

  13. Analysis of data from sensitive U.S. monitoring stations for the Fukushima Dai-ichi nuclear reactor accident

    SciTech Connect (OSTI)

    Biegalski, Steven R.; Bowyer, Ted W.; Eslinger, Paul W.; Friese, Judah I.; Greenwood, Lawrence R.; Haas, Derek A.; Hayes, James C.; Hoffman, Ian; Keillor, Martin E.; Miley, Harry S.; Morin, Marc P.

    2012-12-01

    The March 11, 2011 9.0 magnitude undersea megathrust earthquake off the coast of Japan and subsequent tsunami waves triggered a major nuclear event at the Fukushima Dai-ichi nuclear power station. At the time of the event, units 1, 2, and 3 were operating and units 4, 5, and 6 were in a shutdown condition for maintenance. Loss of cooling capacity to the plants along with structural damage caused by the earthquake and tsunami resulted in a breach of the nuclear fuel integrity and release of radioactive fission products to the environment. Fission products started to arrive in the United States via atmospheric transport on March 15, 2011 and peaked by March 23, 2011. Atmospheric activity concentrations of 131I reached levels of 3.0 * 10*2 Bqm*3 in Melbourne, FL. The noble gas 133Xe reached atmospheric activity concentrations in Ashland, KS of 17 Bqm*3. While these levels are not health concerns, they were well above the detection capability of the radionuclide monitoring systems within the International Monitoring System of the Comprehensive Nuclear-Test-Ban Treaty.

  14. Nuclear and in-source laser spectroscopy with the ISAC yield station

    SciTech Connect (OSTI)

    Kunz, Peter Bricault, Pierre; Dombsky, Marik; Lassen, Jens; Teigelhfer, Andrea; Heggen, Henning; Andreoiu, Corina; Wong, Fiona

    2014-05-15

    A new decay station has been built for the ISAC facility at TRIUMF for the rapid and reliable characterization of radioactive ion beam (RIB) compositions and intensities with the capability of simultaneously collecting ?, ?, and ? decay data from RIB with intensities between a few and ?10{sup 11} ions per second. It features user-friendly control, data acquisition, and analysis software. The analysis of individual decay time structures allows the unambiguous assignment of ? and ? lines even with substantial isobaric contamination present. The capability for accurate half-life measurements is demonstrated with the example of {sup 46}K. The coupling of the yield station to the laser ion source, TRILIS, allows the correlation of radiometric data with automated laser frequency scans. First results of in-source laser spectroscopy measurements on astatine are discussed.

  15. 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

  16. Safer nuclear power

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

    Safer nuclear power 1663 Los Alamos science and technology magazine Latest Issue:October 2015 past issues All Issues » submit Safer nuclear power Experiments at Los Alamos reveal that alternative fuel rod cladding materials can make nuclear power plants dramatically less likely to suffer a Fukushima-type explosion in the event of a nuclear accident March 25, 2013 Safer nuclear power Nuclear generating station Los Alamos scientists, in collaboration with scientists from the Idaho and Oak Ridge

  17. 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.

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

    Energy Savers [EERE]

    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

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

    Office of Environmental Management (EM)

    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

  20. 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.

  1. Reactor engineering support of operations at Three Mile Island nuclear station

    SciTech Connect (OSTI)

    Tropasso, R.T.

    1995-12-31

    The purpose of this paper is to detail the activities in which plant nuclear engineering personnel provide direct support to plant operations. The specific activities include steady-state, transient, and shutdown/refueling operation support as well as special project involvement. The paper is intended to describe the experiences at Three Mile Island (TMI) in which significant benefit to the success of the activity is achieved through the support of the nuclear engineers.

  2. 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.

  3. 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.

  4. 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.

  5. Preliminary Thermal Modeling of Hi-Storm 100S-218 Version B Storage Modules at Hope Creek Nuclear Power Station ISFSI

    SciTech Connect (OSTI)

    Cuta, Judith M.; Adkins, Harold E.

    2013-08-30

    This report fulfills the M3 milestone M3FT-13PN0810022, Report on Inspection 1, under Work Package FT-13PN081002. Thermal analysis is being undertaken at Pacific Northwest National Laboratory (PNNL) in support of inspections of selected storage modules at various locations around the United States, as part of the Used Fuel Disposition Campaign of the U.S. Department of Energy, Office of Nuclear Energy (DOE-NE) Fuel Cycle Research and Development. This report documents pre-inspection predictions of temperatures for four modules at the Hope Creek Nuclear Generating Station ISFSI that have been identified as candidates for inspection in late summer or early fall/winter of 2013. These are HI-STORM 100S-218 Version B modules storing BWR 8x8 fuel in MPC-68 canisters. The temperature predictions reported in this document were obtained with detailed COBRA-SFS models of these four storage systems, with the following boundary conditions and assumptions.

  6. 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.

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

    Office of Environmental Management (EM)

    the Next Generation of U.S. Nuclear Energy Leaders Investing in the Next Generation of U.S. ... power continues to be part of our clean energy mix while leveraging the strong ...

  8. 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.

  9. 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.

  10. 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...

  11. 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.

  12. EIS-0105: Conversion to Coal, Baltimore Gas & Electric Company, Brandon Shores Generating Station Units 1 and 2, Anne Arundel County, Maryland

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy’s Economic Regulatory Administration Office of Fuels Program, Coal and Electricity Division prepared this statement to assess the potential environmental and socioeconomic impacts associated with prohibiting the use of petroleum products as a primary energy source for Units 1 and 2 of the Brandon Shores Generating Station, located in Anne Arundel County, Maryland.

  13. EIS-0036: Coal Conversion Program, New England Power Company, Brayton Point Generating Station Plants 1, 2 and 3, Sommerset, Bristol County, Massachusetts

    Broader source: Energy.gov [DOE]

    The Economic Regulatory Administration developed this EIS to evaluate the site-specific environmental impacts of issuing a Notice of Effectiveness to New England Power Company's Brayton Point Generating Station, Units 1, 2 and 3 to prohibit burning of gas or oil as the primary source of fuel.

  14. EIS-0086: Conversion to Coal, New England Power Company, Salem Harbor Generating Station Units 1, 2, and 3, Salem, Essex County, Massachusetts

    Broader source: Energy.gov [DOE]

    The Economic Regulatory Administration prepared this statement to assess the environmental impacts of prohibiting Units I, 2, and 3 of the Salem Harbor Generating Station from using either natural gas or petroleum products as a primary energy source, which would result in the utility burning low-sulfur coal.

  15. Leach studies on cement-solidified ion exchange resins from decontamination processes at operating nuclear power stations

    SciTech Connect (OSTI)

    McIsaac, C.V.; Akers, D.W.; McConnell, J.W.; Morcos, N.

    1992-08-01

    The effects of varying pH and leachant compositions on the physical stability and leachability of radionuclides and chelating agents were determined for cement-solidified decontamination ion-exchange resin wastes collected from two operating commercial light water reactors. Small scale waste-form specimens were collected during waste solidifications performed at the Brunswick Steam Electric Plant Unit 1 and at the James A. FitzPatrick Nuclear Power Station. The collected specimens were leach tested, and their compressive strength was measured in accordance with the Nuclear Regulatory Commission`s ``Technical Position on Waste Form`` (Revision 1), from the Low-Level Waste Management Branch. Leachates from these studies were analyzed for radionuclides, selected transition metals, and chelating agents to assess the leachability of these waste form constituents. Leachants used for the study were deionized water, simulated seawater, and groundwater compositions similar to those found at Barnwell, South Carolina and Hanford, Washington. Results of this study indicate that initial leachant pH does not affect leachate pH or releases from cement-solidified decontamination ion-exchange resin waste forms. However, differences in leachant composition and the presence of chelating agents may affect the releases of radionuclides and chelating agents. In addition, results from this study indicate that the cumulative releases of radionuclides and chelating agents observed for forms that disintegrated were similar to those for forms that maintained their general physical integrity.

  16. Leach studies on cement-solidified ion exchange resins from decontamination processes at operating nuclear power stations

    SciTech Connect (OSTI)

    McIsaac, C.V.; Akers, D.W.; McConnell, J.W.; Morcos, N.

    1992-01-01

    The effects of varying pH and leachant compositions on the physical stability and leachability of radionuclides and chelating agents were determined for cement-solidified decontamination ion-exchange resin wastes collected from two operating commercial light water reactors. Small scale waste-form specimens were collected during waste solidifications performed at the Brunswick Steam Electric Plant Unit 1 and at the James A. FitzPatrick Nuclear Power Station. The collected specimens were leach tested, and their compressive strength was measured in accordance with the Nuclear Regulatory Commission's Technical Position on Waste Form'' (Revision 1), from the Low-Level Waste Management Branch. Leachates from these studies were analyzed for radionuclides, selected transition metals, and chelating agents to assess the leachability of these waste form constituents. Leachants used for the study were deionized water, simulated seawater, and groundwater compositions similar to those found at Barnwell, South Carolina and Hanford, Washington. Results of this study indicate that initial leachant pH does not affect leachate pH or releases from cement-solidified decontamination ion-exchange resin waste forms. However, differences in leachant composition and the presence of chelating agents may affect the releases of radionuclides and chelating agents. In addition, results from this study indicate that the cumulative releases of radionuclides and chelating agents observed for forms that disintegrated were similar to those for forms that maintained their general physical integrity.

  17. 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.

  18. Training the Next Generation of Nuclear Energy Leaders

    Broader source: Energy.gov [DOE]

    To train and educate the future leaders of the nuclear energy field, the Energy Department is offering $47.2 million in competitive scholarships, fellowships, research projects and university research reactor upgrades.

  19. 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

  20. 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

  1. SEP operating history of the Dresden Nuclear Power Station Unit 2

    SciTech Connect (OSTI)

    Mays, G.T.; Harrington, K.H.

    1983-01-01

    206 forced shutdowns and power reductions were reviewed, along with 631 reportable events and other miscellaneous documentation concerning the operation of Dresden-2, in order to indicate those areas of plant operation that compromised plant safety. The most serious plant challenge to plant safety occurred on June 5, 1970; while undergoing power testing at 75% power, a spurious signal in the reactor pressure control system caused a turbine trip followed by a reactor scram. Subsequent erratic water level and pressure control in the reactor vessel, compounded by a stuck indicator pen on a water level monitor-recorder and inability of the isolation condenser to function, led to discharge of steam and water through safety valves into the reactor drywell. No significant contamination was discharged. There was no pressure damage or the reactor vessel of the drywell containment walls. Six areas of operation that should be of continued concern are diesel generator failures, control rod and rod drive malfunctions, radioactive waste management/health physics program problems, operator errors, turbine control valve and EHC problems, and HPCI failures. All six event types have continued to recur.

  2. 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.

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

    Energy Savers [EERE]

    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

  4. 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:

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

    Energy Savers [EERE]

    | Department of Energy Reactors - Key to Future Nuclear Power Generation in the U.S. Small Modular Reactors - Key to Future Nuclear Power Generation in the U.S. This report presents the results of an extensive analysis of the economics of both gigawatt-scale and small modular reactors. Topics covered include the safety case, economics, the business case, and a business plan, government incentives, licensing, design and engineering, and future research. PDF icon Small Modular Reactors - Key

  6. 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)

  7. Sorption (Kd) measurements on cinder block and grout in support of dose assessments for Zion Nuclear Station decommissioning

    SciTech Connect (OSTI)

    Milian L.; Sullivan T.

    2014-06-24

    The Zion Nuclear Power Station is being decommissioned. ZionSolutions proposes to leave much of the below grade structures in place and to fill them with a backfill to provide structural support. Backfills under consideration include clean concrete demolition debris from the above grade parts of the facility, a flowable grout, cinder block construction debris and sand. A previous study (Yim, 2012) examined the sorption behavior of five nuclides (Fe-55, Co-60, Ni-63, Sr-85, and Cs-137) on concrete and local soils. This study, commissioned by ZionSolutions and conducted by the Brookhaven National Laboratory (BNL) examines the sorption behavior on cinder block and grout materials. Specifically, this study measured the distribution coefficient for four radionuclides of concern using site-groundwater and cinder block from the Zion site and a flowable grout. The distributions coefficient is a measure of the amount of the radionuclide that will remain sorbed to the solid material that is present relative to the amount that will remain in solution. A high distribution coefficient indicates most of the radionuclide will remain on the solid material and will not be available for transport by the groundwater. The radionuclides examined in this set of tests were Co-60, Ni-63, Sr-85, and Cs-137. Tests were performed following ASTM C1733-10, Standard Test Methods for Distribution Coefficients of Inorganic Species by the Batch Method. Sr-85 was used in the testing as an analogue for Sr-90 because it behaves similarly with respect to sorption and has a gamma emission that is easier to detect than the beta emission from Sr-90.

  8. 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.

  9. Determination of station blackout frequency-duration relationships

    SciTech Connect (OSTI)

    Griggs, D.P.; Riggs, B.K.; Balakrishna, S.

    1986-01-01

    Station blackout is the loss of all alternating current (ac) power to the essential and nonessential electrical buses in a nuclear power plant. This generally involves the loss of redundant off-site power sources and the failure of two or more emergency diesel generators (EDGs). The US Nuclear Regulatory Commission (NRC) has proposed requiring all commercial reactors to have the capability of coping with a station blackout of a specified duration. The NRC has also proposed 4 or 8 h as acceptable durations, depending on plant susceptibility to the occurrence of station blackout events. Analyses were performed to determine expected station blackout frequencies representative of a majority of domestic nuclear power plants. A methodology based on that developed by the NRC was used. Representative industry data for loss of off-site power (LOOP) events and EDG reliability were used in the analyses.

  10. Emery Station Operations Center

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

    Emery Station Operations Center

  11. 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.

  12. 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.

  13. Table 2. Ten Largest Plants by Generation Capacity, 2013

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

    Jersey" ,"Plant","Primary energy source","Operating company","Net summer capacity (MW)" 1,"PSEG Salem Generating Station","Nuclear","PSEG Nuclear LLC",2370.4 2,"PSEG Linden Generating Station","Natural gas","PSEG Fossil LLC",1572 3,"Bergen Generating Station","Natural gas","PSEG Fossil LLC",1208 4,"PSEG Hope Creek Generating

  14. 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.

  15. 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.

  16. Next Generation Fast RF Interlock Module and ATCA Adapter for ILC High Availability RF Test Station Demonstration

    SciTech Connect (OSTI)

    Larsen, R

    2009-10-17

    High availability interlocks and controls are required for the ILC (International Linear Collider) L-Band high power RF stations. A new F3 (Fast Fault Finder) VME module has been developed to process both fast and slow interlocks using FPGA logic to detect the interlock trip excursions. This combination eliminates the need for separate PLC (Programmable Logic Controller) control of slow interlocks. Modules are chained together to accommodate as many inputs as needed. In the next phase of development the F3's will be ported to the new industry standard ATCA (Advanced Telecom Computing Architecture) crate (shelf) via a specially designed VME adapter module with IPMI (Intelligent Platform Management Interface). The goal is to demonstrate auto-failover and hot-swap for future partially redundant systems.

  17. An Adaptive, Consent-Based Path to Nuclear Waste Storage and Disposal

    Energy Savers [EERE]

    Solutions | Department of Energy An Adaptive, Consent-Based Path to Nuclear Waste Storage and Disposal Solutions An Adaptive, Consent-Based Path to Nuclear Waste Storage and Disposal Solutions February 12, 2014 - 1:15pm Addthis The Tennessee Valley Authority's Sequoyah Nuclear Generating Station. | Photo courtesy of the Energy Department. The Tennessee Valley Authority's Sequoyah Nuclear Generating Station. | Photo courtesy of the Energy Department. Dr. Ernest Moniz Dr. Ernest Moniz

  18. 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

  19. 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.

  20. 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

  1. Topics in nuclear power (Journal Article) | SciTech Connect

    Office of Scientific and Technical Information (OSTI)

    NUCLEAR POWER STATION; GAIN; JAPAN; NATURAL DISASTERS; NUCLEAR INDUSTRY; NUCLEAR POWER; NUCLEAR POWER PLANTS; PROBABILISTIC ESTIMATION; REACTOR ACCIDENTS; REACTOR MAINTENANCE;...

  2. 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.

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

    DOE Patents [OSTI]

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

    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.

  4. 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

  5. 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

  6. Screening evaluation of radionuclide groundwater concentrations for the end state basement fill model Zion Nuclear Power Station decommissioning project

    SciTech Connect (OSTI)

    Sullivan T.

    2014-06-09

    ZionSolutions is in the process of decommissioning the Zion Nuclear Power Plant. The site contains two reactor Containment Buildings, a Fuel Building, an Auxiliary Building, and a Turbine Building that may be contaminated. The current decommissioning plan involves removing all above grade structures to a depth of 3 feet below grade. The remaining underground structures will be backfilled with clean material. The final selection of fill material has not been made.

  7. 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)

  8. 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.

  9. Effect of pH on the release of radionuclides and chelating agents from cement-solidified decontamination ion-exchange resins collected from operating nuclear power stations

    SciTech Connect (OSTI)

    McIsaac, C.V.; Akers, D.W.; McConnell, J.W. )

    1991-06-01

    Data are presented on the physical stability and leachability of radionuclides and chelating agents from cement-solidified decontamination ion-exchange resin wastes collected from two operating commercial light water reactors. Small-scale waste--form specimens collected during solidifications performed at the Brunswick Steam Electric Plant Unit 1 and at the James A. FitzPatrick Nuclear Power Station were leach-tested and subjected to compressive strength testing in accordance with the Nuclear Regulatory Commission's Technical Position on Waste Form'' (Revision 1). Samples of untreated resin waste collected from each solidification vessel before the solidification process were analyzed for concentrations of radionuclides, selected transition metals, and chelating agents to determine the quantities of these chemicals in the waste-form specimens. The chelating agents included oxalic, citric, and picolinic acids. In order to determine the effect of leachant chemical composition and pH on the stability and leachability of the waste forms, waste-form specimens were leached in various leachants. Results of this study indicate that differences in pH do not affect releases from cement-solidified decontamination ion-exchange resin waste forms, but that differences in leachant chemistry and the presence of chelating agents may affect the releases of radionuclides and chelating agents. Also, this study indicates that the cumulative releases of radionuclides and chelating agents are similar for waste- form specimens that decomposed and those that retained their general physical form. 36 refs., 60 figs., 28 tabs.

  10. 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.

  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. 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).

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

    DOE Patents [OSTI]

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

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

    DOE Patents [OSTI]

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

    1995-01-01

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

  15. 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. 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.

  17. 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.

  18. 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.

  19. 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.

  20. Suggestion of typical phases of in-vessel fuel-debris by thermodynamic calculation for decommissioning technology of Fukushima-Daiichi nuclear power station

    SciTech Connect (OSTI)

    Ikeuchi, Hirotomo; Yano, Kimihiko; Kaji, Naoya; Washiya, Tadahiro; Kondo, Yoshikazu; Noguchi, Yoshikazu

    2013-07-01

    For the decommissioning of the Fukushima-Daiichi Nuclear Power Station (1F), the characterization of fuel-debris in cores of Units 1-3 is necessary. In this study, typical phases of the in-vessel fuel-debris were estimated using a thermodynamic equilibrium (TDE) calculation. The FactSage program and NUCLEA database were applied to estimate the phase equilibria of debris. It was confirmed that the TDE calculation using the database can reproduce the phase separation behavior of debris observed in the Three Mile Island accident. In the TDE calculation of 1F, the oxygen potential [G(O{sub 2})] was assumed to be a variable. At low G(O{sub 2}) where metallic zirconium remains, (U,Zr)O{sub 2}, UO{sub 2}, and ZrO{sub 2} were found as oxides, and oxygen-dispersed Zr, Fe{sub 2}(Zr,U), and Fe{sub 3}UZr{sub 2} were found as metals. With an increase in zirconium oxidation, the mass of those metals, especially Fe{sub 3}UZr{sub 2}, decreased, but the other phases of metals hardly changed qualitatively. Consequently, (U,Zr)O{sub 2} is suggested as a typical phase of oxide, and Fe{sub 2}(Zr,U) is suggested as that of metal. However, a more detailed estimation is necessary to consider the distribution of Fe in the reactor pressure vessel through core-melt progression. (authors)

  1. 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.

  2. 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

  3. Nuclear reactor characteristics and operational history

    Gasoline and Diesel Fuel Update (EIA)

    2. Ownership Data, Table 3. Characteristics and Operational History Table 1. Nuclear Reactor, State, Type, Net Capacity, Generation, and Capacity Factor PDF XLS Plant/Reactor Name Generator ID State Type 2009 Summer Capacity Net MW(e)1 2010 Annual Generation Net MWh2 Capacity Factor Percent3 Arkansas Nuclear One 1 AR PWR 842 6,607,090 90 Arkansas Nuclear One 2 AR PWR 993 8,415,588 97 Beaver Valley 1 PA PWR 892 7,119,413 91 Beaver Valley 2 PA PWR 885 7,874,151 102 Braidwood Generation Station 1

  4. 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.

  5. 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.

  6. 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.

  7. 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.

  8. 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...

  9. 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.

  10. 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.

  11. Alternative Fueling Station Locator

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    19,710 alternative fuel stations in the United States Excluding private stations Location details are subject to change. We recommend calling the stations to verify location, hours...

  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. 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.

  15. 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.

  16. 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.

  17. 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.

  18. 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.

  19. 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...

  20. 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.

  1. 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.

  2. 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.

  3. 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.

  4. 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.

  5. 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.

  6. 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.

  7. 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.

  8. 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

  9. Refueling Stations | Open Energy Information

    Open Energy Info (EERE)

    Refueling Stations Jump to: navigation, search TODO: Add description List of Refueling Stations Incentives Retrieved from "http:en.openei.orgwindex.php?titleRefuelingStations...

  10. Pilgrim Station | Open Energy Information

    Open Energy Info (EERE)

    Station Jump to: navigation, search Name Pilgrim Station Facility Pilgrim Stage Station Sector Wind energy Facility Type Commercial Scale Wind Facility Status In Service Owner...

  11. Nuclear Workforce Initiative - SRSCRO

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

    nuclear Nuclear Workforce Initiative The SRSCRO region of Georgia and South Carolina has the most unique nuclear industry capabilities in the nation. This region is at the forefront of new nuclear power production, environmental stewardship, innovative technology and national security. Long-term nuclear workforce demand is growing in the region as new nuclear reactors are under construction at the V.C Summer Nuclear Station in Fairfield County, SC and at Plant Vogtle in Waynesboro, GA. New

  12. 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)

  13. Compression and immersion tests and leaching of radionuclides, stable metals, and chelating agents from cement-solidified decontamination waste collected from nuclear power stations

    SciTech Connect (OSTI)

    Akers, D.W.; Kraft, N.C.; Mandler, J.W.

    1994-06-01

    A study was performed for the Nuclear Regulatory Commission (NRC) to evaluate structural stability and leachability of radionuclides, stable metals, and chelating agents from cement-solidified decontamination ion-exchange resin wastes collected from seven commercial boiling water reactors and one pressurized water reactor. The decontamination methods used at the reactors were the Can-Decon, AP/Citrox, Dow NS-1, and LOMI processes. Samples of untreated resin waste and solidified waste forms were subjected to immersion and compressive strength testing. Some waste-form samples were leach-tested using simulated groundwaters and simulated seawater for comparison with the deionized water tests that are normally performed to assess waste-form leachability. This report presents the results of these tests and assesses the effects of the various decontamination methods, waste form formulations, leachant chemical compositions, and pH of the leachant on the structural stability and leachability of the waste forms. Results indicate that releases from intact and degraded waste forms are similar and that the behavior of some radionuclides such as {sup 55}Fe, {sup 60}Co, and {sup 99}Tc were similar. In addition, the leachability indexes are greater than 6.0, which meets the requirement in the NRC`s ``Technical Position on Waste Form,`` Revision 1.

  14. Independent technical support for the frozen soil barrier installation and operation at the Fukushima Daiichi Nuclear Power Station (F1 Site)

    SciTech Connect (OSTI)

    Looney, Brian B.; Jackson, Dennis G.; Truex, Michael J.; Johnson, Christian D.

    2015-02-23

    TEPCO is implementing a number of water countermeasures to limit the releases and impacts of contaminated water to the surrounding environment. The diverse countermeasures work together in an integrated manner to provide different types, and several levels, of protection. In general, the strategy represents a comprehensive example of a “defense in depth” concept that is used for nuclear facilities around the world. One of the key countermeasures is a frozen soil barrier encircling the damaged reactor facilities. The frozen barrier is intended to limit the flow of water into the area and provide TEPCO the ability to reduce the amount of contaminated water that requires treatment and storage. The National Laboratory team supports the selection of artificial ground freezing and the incorporation of the frozen soil barrier in the contaminated water countermeasures -- the technical characteristics of a frozen barrier are relatively well suited to the Fukushima-specific conditions and the need for inflow reduction. Further, our independent review generally supports the TEPCO/Kajima design, installation strategy and operation plan.

  15. 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.

  16. Monthly/Annual Energy Review - nuclear section

    Reports and Publications (EIA)

    2016-01-01

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

  17. 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.

  18. 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).

  19. Timber Mountain Precipitation Monitoring Station

    SciTech Connect (OSTI)

    Lyles, Brad; McCurdy, Greg; Chapman, Jenny; Miller, Julianne

    2012-01-01

    A precipitation monitoring station was placed on the west flank of Timber Mountain during the year 2010. It is located in an isolated highland area near the western border of the Nevada National Security Site (NNSS), south of Pahute Mesa. The cost of the equipment, permitting, and installation was provided by the Environmental Monitoring Systems Initiative (EMSI) project. Data collection, analysis, and maintenance of the station during fiscal year 2011 was funded by the U.S. Department of Energy, National Nuclear Security Administration, Nevada Site Office Environmental Restoration, Soils Activity. The station is located near the western headwaters of Forty Mile Wash on the Nevada Test and Training Range (NTTR). Overland flows from precipitation events that occur in the Timber Mountain high elevation area cross several of the contaminated Soils project CAU (Corrective Action Unit) sites located in the Forty Mile Wash watershed. Rain-on-snow events in the early winter and spring around Timber Mountain have contributed to several significant flow events in Forty Mile Wash. The data from the new precipitation gauge at Timber Mountain will provide important information for determining runoff response to precipitation events in this area of the NNSS. Timber Mountain is also a groundwater recharge area, and estimation of recharge from precipitation was important for the EMSI project in determining groundwater flowpaths and designing effective groundwater monitoring for Yucca Mountain. Recharge estimation additionally provides benefit to the Underground Test Area Sub-project analysis of groundwater flow direction and velocity from nuclear test areas on Pahute Mesa. Additionally, this site provides data that has been used during wild fire events and provided a singular monitoring location of the extreme precipitation events during December 2010 (see data section for more details). This letter report provides a summary of the site location, equipment, and data collected in fiscal year 2011.

  20. Hot Plate Station

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

    Hot Plate Station The hot plate station is comprised of four Prazitherm precision hot plates manufactured for resist processing. Each hot plate is sized 350mm x 350mm. They are flat and level, with temperature uniformity of +/- 0.5º. The maximum operating temperature is limited to 200ºC in order to maintain temperature inside the cleanroom. A hood located over the hot plate station ensures evaporated fumes are not released into the cleanroom environment. Each hot plate is controlled through

  1. Greening Gas Stations

    Office of Environmental Management (EM)

    eere.energy.gov Public Service of Colorado Ponnequin Wind Farm Greening Gas Stations Prestene S. Garnenez Intern, Sandia National Laboratories Graduate Student, University of California, Los Angeles Department of Urban Planning eere.energy.gov It's Not Easy Being GREEN * What does it mean to be Green? * Can a Gas Station be Green? * How can a Gas Station be "Green"? * Image: inconvenientyouth.org eere.energy.gov What does it mean to be Green? * There are no "rules" for being

  2. The materials test station: a fast spectrum irradiation facility

    SciTech Connect (OSTI)

    Pitcher, Eric J.

    2007-07-01

    The Materials Test Station is a fast-neutron spectrum irradiation facility under design at the Los Alamos National Laboratory in support of the United States Department of Energy's Global Nuclear Energy Partnership. The facility will be capable of rodlets-scale irradiations of candidate fuel forms being developed to power the next generation of fast reactors. Driven by a powerful proton beam, the fuel irradiation region exhibits a neutron spectrum similar to that seen in a fast reactor, with a peak neutron flux of 1.6 x 10{sup 15} n.cm{sup -2}.s{sup -1}. Site preparation and construction are estimated to take four years, with a cost range of $60 M to $90 M. (author)

  3. Electrolysis at Forecourt Stations

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

    CLEAN FUEL ITM Electrolysis at Forecourt Stations NREL Workshop Feb 27 & 28, 2014 Contents: * Introduction ITM Power Inc. * Target Costs * Challenges and Technology Developments - Continuous Improvements * Renewable Energy - Power pricing is the Key * HFuel PEM Electrolysis Module Spec * 100 % Renewable Hydrogen Refuelling Project ITM POWER INC. CLEAN FUEL ITM Electrolysis at Forecourt Stations INTRODUCTION - ITM POWER INC. ITM POWER INC. ENERGY STORAGE | CLEAN FUEL Established to enter the

  4. Biosciences: Emery Station Operations Center (ESOC)

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

    Biosciences: Emery Station Operations Center (ESOC

  5. Department of Energy Commends the Nuclear Regulatory Commission...

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

    today applauded the Nuclear Regulatory Commission's (NRC) decision to approve an Early Site Permit (ESP) for the Entergy Corporation's Grand Gulf Nuclear Station in Mississippi. ...

  6. Regulatory/backfit analysis for the resolution of Unresolved Safety Issue A-44, Station Blackout

    SciTech Connect (OSTI)

    Rubin, A.M.

    1988-06-01

    Station blackout is the complete loss of alternating current (ac) electric power to the essential and nonessential buses in a nuclear power plant; it results when both offsite power and the onsite emergency ac power systems are unavailable. Because many safety systems required for reactor core decay heat removal and containment heat removal depend on ac power, the consequences of a station blackout could be severe. Because of the concern about the frequency of loss of offsite power, the number of failures of emergency diesel generators, and the potentially severe consequences of a loss of all ac power, ''Station Blackout'' was designated as Unresolved Safety Issue (USI) A-44. This report presents the regulatory/backfit analysis for USI A-44. It includes (1) a summary of the issue, (2) the recommended technical resolution, (3) alternative resolutions considered by the Nuclear Regulatory Commission (NRC) staff, (4) an assessment of the benefits and costs of the recommended resolution, (5) the decision rationale, (6) the relationship between USI A-44 and other NRC programs and requirements, and (7) a backfit analysis demonstrating that the resolution of USI A-44 complies with the backfit rule (10 CFR 50.109).

  7. Regulatory analysis for the resolution of Unresolved Safety Issue A-44, Station Blackout. Draft report

    SciTech Connect (OSTI)

    Rubin, A.M.

    1986-01-01

    ''Station Blackout'' is the complete loss of alternating current (ac) electric power to the essential and nonessential buses in a nuclear power plant; it results when both offsite power and the onsite emergency ac power systems are unavailable. Because many safety systems required for reactor core decay heat removal and containment heat removal depend on ac power, the consequences of a station blackout could be severe. Because of the concern about the frequency of loss of offsite power, the number of failures of emergency diesel generators, and the potentially severe consequences of a loss of all ac power, ''Station Blackout'' was designated as Unresolved Safety Issue (USI) A-44. This report presents the regulatory analysis for USI A-44. It includes: (1) a summary of the issue, (2) the proposed technical resolution, (3) alternative resolutions considered by the Nuclear Regulatory Commission (NRC) staff, (4) an assessment of the benefits and costs of the recommended resolution, (5) the decision rationale, and (6) the relationship between USI A-44 and other NRC programs and requirements.

  8. Station blackout transients in the semiscale facility

    SciTech Connect (OSTI)

    Chapman, J.C.

    1985-12-01

    The test results of station blackout transients conducted in the Semiscale MOD-2B facility are discussed in this report. The Semiscale MOD-2B facility simulates a pressurized water reactor (PWR) power plant. The experiments were initiated from conditions typical of PWR plant operating conditions (primary pressure of 15.2 MPa (2205 psi) and cold leg fluid temperature of 550 K (530F)). Five station blackout experiments were conducted, Three tests in the Power Loss (PL) Test Series and the two Primary Boil-off (PBO) Tests. The responses of these tests were analyzed and compared. However, only one test response (S-PL-2) is presented and discussed in detail. The S-PL-2 experiment is characterized by examining the responses of the primary and secondary pressures and fluid temperatures, the pressurizer liquid level, the primary fluid distribution, and the core thermal behavior. The mechanisms driving the S-PL-2 responses, the main elements of the station blackout transient, the influences of initial and boundary conditions and other transient that may appear similar to a station blackout are also discussed. Information pertinent to station blackout nuclear safety issues is presented in the report. 13 refs., 44 figs.

  9. Table 2. Ten largest plants by generation capacity, 2013

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

    Kansas" ,"Plant","Primary energy source","Operating company","Net summer capacity (MW)" 1,"Jeffrey Energy Center","Coal","Westar Energy Inc",2155 2,"La Cygne","Coal","Kansas City Power & Light Co",1415.3 3,"Wolf Creek Generating Station","Nuclear","Wolf Creek Nuclear Optg Corp",1175 4,"Gordon Evans Energy Center","Natural gas","Kansas

  10. 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.

  11. 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

  12. Online Monitoring Technical Basis and Analysis Framework for Emergency Diesel Generators - Interim Report for FY 2013

    SciTech Connect (OSTI)

    Binh T. Pham; Nancy J. Lybeck; Vivek Agarwal

    2012-12-01

    The Light Water Reactor Sustainability program at Idaho National Laboratory is actively conducting research to develop and demonstrate online monitoring capabilities for active components in existing nuclear power plants. Idaho National Laboratory and the Electric Power Research Institute are working jointly to implement a pilot project to apply these capabilities to emergency diesel generators and generator step-up transformers. The Electric Power Research Institute Fleet-Wide Prognostic and Health Management Software Suite will be used to implement monitoring in conjunction with utility partners: Braidwood Generating Station (owned by Exelon Corporation) for emergency diesel generators, and Shearon Harris Nuclear Generating Station (owned by Duke Energy Progress) for generator step-up transformers. This report presents monitoring techniques, fault signatures, and diagnostic and prognostic models for emergency diesel generators. Emergency diesel generators provide backup power to the nuclear power plant, allowing operation of essential equipment such as pumps in the emergency core coolant system during catastrophic events, including loss of offsite power. Technical experts from Braidwood are assisting Idaho National Laboratory and Electric Power Research Institute in identifying critical faults and defining fault signatures associated with each fault. The resulting diagnostic models will be implemented in the Fleet-Wide Prognostic and Health Management Software Suite and tested using data from Braidwood. Parallel research on generator step-up transformers was summarized in an interim report during the fourth quarter of fiscal year 2012.

  13. Mobile Alternative Fueling Station Locator

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Alternative Fueling Station Locator Fuel Type Biodiesel (B20 and above) Compressed Natural Gas Electric Ethanol (E85) Hydrogen Liquefied Natural Gas (LNG) Liquefied Petroleum Gas (Propane) Location Enter a city, postal code, or address Include private stations Not all stations are open to the public. Choose this option to also search private fueling stations. Search Caution: The AFDC recommends that users verify that stations are open, available to the public, and have the fuel prior to making a

  14. Microsoft PowerPoint - Station Service for SWPA_June _17_2015 - HDC.pptx [Read-Only]

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

    Station Service Generators Southwestern Federal Hydropower Council Dewey Short Visitor Center June 17, 2015 by Scott Cotner, P.E. Senior Electrical Engineer Hydroelectric Design Center BUILDING STRONG ® PORTLAND DISTRICT 2 Outline  Station Service System Definition  Components of a Station Service System  System Design Criteria  Typical Station Service Configurations  Station Service Generators ► Benefits ► Potential Rehab Items  Alternative Sources  Summary BUILDING

  15. 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.

  16. MHK Technologies/Ocean Powered Compressed Air Stations | Open...

    Open Energy Info (EERE)

    Description The Ocean Powered Compressed Air Station is a point absorber that uses an air pump to force air to a landbased generator The device only needs 4m water depth and...

  17. 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 Administrations Mars Science Laboratory, which launched in November of 2011.

  18. 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

  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. Hydrogen Filling Station

    SciTech Connect (OSTI)

    Boehm, Robert F; Sabacky, Bruce; Anderson II, Everett B; Haberman, David; Al-Hassin, Mowafak; He, Xiaoming; Morriseau, Brian

    2010-02-24

    Hydrogen is an environmentally attractive transportation fuel that has the potential to displace fossil fuels. The Freedom CAR and Freedom FUEL initiatives emphasize the importance of hydrogen as a future transportation fuel. Presently, Las Vegas has one hydrogen fueling station powered by natural gas. However, the use of traditional sources of energy to produce hydrogen does not maximize the benefit. The hydrogen fueling station developed under this grant used electrolysis units and solar energy to produce hydrogen fuel. Water and electricity are furnished to the unit and the output is hydrogen and oxygen. Three vehicles were converted to utilize the hydrogen produced at the station. The vehicles were all equipped with different types of technologies. The vehicles were used in the day-to-day operation of the Las Vegas Valley Water District and monitoring was performed on efficiency, reliability and maintenance requirements. The research and demonstration utilized for the reconfiguration of these vehicles could lead to new technologies in vehicle development that could make hydrogen-fueled vehicles more cost effective, economical, efficient and more widely used. In order to advance the development of a hydrogen future in Southern Nevada, project partners recognized a need to bring various entities involved in hydrogen development and deployment together as a means of sharing knowledge and eliminating duplication of efforts. A road-mapping session was held in Las Vegas in June 2006. The Nevada State Energy Office, representatives from DOE, DOE contractors and LANL, NETL, NREL were present. Leadership from the National hydrogen Association Board of Directors also attended. As a result of this session, a roadmap for hydrogen development was created. This roadmap has the ability to become a tool for use by other road-mapping efforts in the hydrogen community. It could also become a standard template for other states or even countries to approach planning for a hydrogen future. Project partners also conducted a workshop on hydrogen safety and permitting. This provided an opportunity for the various permitting agencies and end users to gather to share experiences and knowledge. As a result of this workshop, the permitting process for the hydrogen filling station on the Las Vegas Valley Water Districts land was done more efficiently and those who would be responsible for the operation were better educated on the safety and reliability of hydrogen production and storage. The lessons learned in permitting the filling station and conducting this workshop provided a basis for future hydrogen projects in the region. Continuing efforts to increase the working pressure of electrolysis and efficiency have been pursued. Research was also performed on improving the cost, efficiency and durability of Proton Exchange Membrane (PEM) hydrogen technology. Research elements focused upon PEM membranes, electrodes/catalysts, membrane-electrode assemblies, seals, bipolar plates, utilization of renewable power, reliability issues, scale, and advanced conversion topics. Additionally, direct solar-to-hydrogen conversion research to demonstrate stable and efficient photoelectrochemistry (PEC) hydrogen production systems based on a number of optional concepts was performed. Candidate PEC concepts included technical obstacles such as inefficient photocatalysis, inadequate photocurrent due to non-optimal material band gap energies, rapid electron-hole recombination, reduced hole mobility and diminished operational lifetimes of surface materials exposed to electrolytes. Project Objective 1: Design, build, operate hydrogen filling station Project Objective 2: Perform research and development for utilizing solar technologies on the hydrogen filling station and convert two utility vehicles for use by the station operators Project Objective 3: Increase capacity of hydrogen filling station; add additional vehicle; conduct safety workshop; develop a roadmap for hydrogen development; accelerate the development of photovoltaic components Project Objective 4:

  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. Operational experience and maintenance programs of Transamerica Delaval, Inc., diesel generators

    SciTech Connect (OSTI)

    Rajan, J.R.

    1994-05-01

    Concerns regarding the reliability of large-bore, medium-speed diesel generators manufactured by Transamerica Delaval, Inc. (TDI) for application at domestic nuclear plants were first prompted by a crankshaft failure at Shoreham Nuclear Power Station in August 1983. A number of diesel generator components were identified which had potential deficiencies from a manufacturing and operational standpoint. In response to these problems, 11 (now 8) U.S. nuclear utility owners formed a TDI Diesel Generator Owners Group (Owners Group) to address operational and regulatory issues relative to diesel generator sets used for standby emergency power. The Owners` Group performed extensive design reviews of all key engine components and developed recommendations to be implemented by the individual owners concerning needed component replacements and modifications, component inspections to validate the {open_quotes}as-manufactured{close_quotes} and {open_quotes}as-assembled{close_quotes} quality of key engine components, engine testing, and an enhanced maintenance and surveillance program.

  3. Quadrennial Technology Review's Alternative Generation Workshop...

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

    Technology Review's Alternative Generation Workshop Slides Preliminary Slides for Alternative Generation Workshop including Carbon Capture and Sequestration, Nuclear Power,...

  4. 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.

  5. HYDROGEN IGNITION MECHANISM FOR EXPLOSIONS IN NUCLEAR FACILITY PIPE SYSTEMS

    SciTech Connect (OSTI)

    Leishear, R

    2010-05-02

    Hydrogen and oxygen generation due to the radiolysis of water is a recognized hazard in pipe systems used in the nuclear industry, where the accumulation of hydrogen and oxygen at high points in the pipe system is expected, and explosive conditions exist. Pipe ruptures at nuclear facilities were attributed to hydrogen explosions inside pipelines, in nuclear facilities, i.e., Hamaoka, Nuclear Power Station in Japan, and Brunsbuettel in Germany. Prior to these accidents an ignition source for hydrogen was questionable, but these accidents, demonstrated that a mechanism was, in fact, available to initiate combustion and explosion. Hydrogen explosions may occur simultaneously with water hammer accidents in nuclear facilities, and a theoretical mechanism to relate water hammer to hydrogen deflagrations and explosions is presented herein.

  6. Carbon tax or carbon permits: The impact on generators' risks

    SciTech Connect (OSTI)

    Green, R.

    2008-07-01

    Volatile fuel prices affect both the cost and price of electricity in a liberalized market. Generators with the price-setting technology will face less risk to their profit margins than those with costs that are not correlated with price, even if those costs are not volatile. Emissions permit prices may respond to relative fuel prices, further increasing volatility. This paper simulates the impact of this on generators' profits, comparing an emissions trading scheme and a carbon tax against predictions for the UK in 2020. The carbon tax reduces the volatility faced by nuclear generators, but raises that faced by fossil fuel stations. Optimal portfolios would contain a higher proportion of nuclear plant if a carbon tax was adopted.

  7. Xcel Energy Comanche Station: Pueblo, Colorado (Data)

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Stoffel, T.; Andreas, A.

    A partnership with industry and U.S. Department of Energy's National Renewable Energy Laboratory (NREL) to collect solar data to support future solar power generation in the United States. The measurement station monitors global horizontal, direct normal, and diffuse horizontal irradiance to define the amount of solar energy that hits this particular location. The solar measurement instrumentation is also accompanied by meteorological monitoring equipment to provide scientists with a complete picture of the solar power possibilities.

  8. Xcel Energy Comanche Station: Pueblo, Colorado (Data)

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Stoffel, T.; Andreas, A.

    2007-06-20

    A partnership with industry and U.S. Department of Energy's National Renewable Energy Laboratory (NREL) to collect solar data to support future solar power generation in the United States. The measurement station monitors global horizontal, direct normal, and diffuse horizontal irradiance to define the amount of solar energy that hits this particular location. The solar measurement instrumentation is also accompanied by meteorological monitoring equipment to provide scientists with a complete picture of the solar power possibilities.

  9. Nuclear Security for Floating Nuclear Power Plants

    SciTech Connect (OSTI)

    Skiba, James M.; Scherer, Carolynn P.

    2015-10-13

    Recently there has been a lot of interest in small modular reactors. A specific type of these small modular reactors (SMR,) are marine based power plants called floating nuclear power plants (FNPP). These FNPPs are typically built by countries with extensive knowledge of nuclear energy, such as Russia, France, China and the US. These FNPPs are built in one country and then sent to countries in need of power and/or seawater desalination. Fifteen countries have expressed interest in acquiring such power stations. Some designs for such power stations are briefly summarized. Several different avenues for cooperation in FNPP technology are proposed, including IAEA nuclear security (i.e. safeguards), multilateral or bilateral agreements, and working with Russian design that incorporates nuclear safeguards for IAEA inspections in non-nuclear weapons states

  10. High speed imager test station

    DOE Patents [OSTI]

    Yates, George J.; Albright, Kevin L.; Turko, Bojan T.

    1995-01-01

    A test station enables the performance of a solid state imager (herein called a focal plane array or FPA) to be determined at high image frame rates. A programmable waveform generator is adapted to generate clock pulses at determinable rates for clock light-induced charges from a FPA. The FPA is mounted on an imager header board for placing the imager in operable proximity to level shifters for receiving the clock pulses and outputting pulses effective to clock charge from the pixels forming the FPA. Each of the clock level shifters is driven by leading and trailing edge portions of the clock pulses to reduce power dissipation in the FPA. Analog circuits receive output charge pulses clocked from the FPA pixels. The analog circuits condition the charge pulses to cancel noise in the pulses and to determine and hold a peak value of the charge for digitizing. A high speed digitizer receives the peak signal value and outputs a digital representation of each one of the charge pulses. A video system then displays an image associated with the digital representation of the output charge pulses clocked from the FPA. In one embodiment, the FPA image is formatted to a standard video format for display on conventional video equipment.

  11. High speed imager test station

    DOE Patents [OSTI]

    Yates, G.J.; Albright, K.L.; Turko, B.T.

    1995-11-14

    A test station enables the performance of a solid state imager (herein called a focal plane array or FPA) to be determined at high image frame rates. A programmable waveform generator is adapted to generate clock pulses at determinable rates for clock light-induced charges from a FPA. The FPA is mounted on an imager header board for placing the imager in operable proximity to level shifters for receiving the clock pulses and outputting pulses effective to clock charge from the pixels forming the FPA. Each of the clock level shifters is driven by leading and trailing edge portions of the clock pulses to reduce power dissipation in the FPA. Analog circuits receive output charge pulses clocked from the FPA pixels. The analog circuits condition the charge pulses to cancel noise in the pulses and to determine and hold a peak value of the charge for digitizing. A high speed digitizer receives the peak signal value and outputs a digital representation of each one of the charge pulses. A video system then displays an image associated with the digital representation of the output charge pulses clocked from the FPA. In one embodiment, the FPA image is formatted to a standard video format for display on conventional video equipment. 12 figs.

  12. 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)

  13. 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.

  14. Alternative Fueling Station Locator | Department of Energy

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

    Alternative Fueling Station Locator Alternative Fueling Station Locator Find alternative fueling stations near an address or ZIP code or along a route in the United States. Enter a state to see a station count

  15. Rancia Geothermal Power Station | Open Energy Information

    Open Energy Info (EERE)

    Station General Information Name Rancia Geothermal Power Station Sector Geothermal energy Location Information Location Tuscany, Italy Geothermal Resource Area...

  16. Sesta Geothermal Power Station | Open Energy Information

    Open Energy Info (EERE)

    Station General Information Name Sesta Geothermal Power Station Sector Geothermal energy Location Information Location Tuscany, Italy Geothermal Resource Area Larderello...

  17. Farinello Geothermal Power Station | Open Energy Information

    Open Energy Info (EERE)

    Station General Information Name Farinello Geothermal Power Station Sector Geothermal energy Location Information Location Tuscany, Italy Geothermal Resource Area Larderello...

  18. Pianacce Geothermal Power Station | Open Energy Information

    Open Energy Info (EERE)

    Station General Information Name Pianacce Geothermal Power Station Sector Geothermal energy Location Information Location Tuscany, Italy Geothermal Resource Area...

  19. 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.

  20. 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)

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

    SciTech Connect (OSTI)

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

    2009-07-02

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

  2. Hanford Meteorological Station - Hanford Site

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

    Meteorological Station Hanford Meteorological Station Real Time Met Data from Around the Site Current and Past 48 Hours HMS Observations Daily HMS Extremes in Met Data Met and Climate Data Summary Products Contacts / Hours Current NWS Forecast for the Tri-Cities NWS Windchill Chart Hanford Meteorological Station Email Email Page | Print Print Page |Text Increase Font Size Decrease Font Size The HMS is operated by Mission Support Alliance for the U.S. Department of Energy. The HMS provides a

  3. Antenna unit and radio base station therewith

    DOE Patents [OSTI]

    Kuwahara, Mikio; Doi, Nobukazu; Suzuki, Toshiro; Ishida, Yuji; Inoue, Takashi; Niida, Sumaru

    2007-04-10

    Phase and amplitude deviations, which are generated, for example, by cables connecting an array antenna of a CDMA base station and the base station, are calibrated in the baseband. The base station comprises: an antenna apparatus 1; couplers 2; an RF unit 3 that converts a receive signal to a baseband signal, converts a transmit signal to a radio frequency, and performs power control; an A/D converter 4 for converting a receive signal to a digital signal; a receive beam form unit 6 that multiplies the receive signal by semi-fixed weight; a despreader 7 for this signal input; a time-space demodulator 8 for demodulating user data; a despreader 9 for probe signal; a space modulator 14 for user data; a spreader 13 for user signal; a channel combiner 12; a Tx calibrater 11 for controlling calibration of a signal; a D/A converter 10; a unit 16 for calculation of correlation matrix for generating a probe signal used for controlling an Rx calibration system and a TX calibration system; a spreader 17 for probe signal; a power control unit 18; a D/A converter 19; an RF unit 20 for probe signal; an A/D converter 21 for signal from the couplers 2; and a despreader 22.

  4. Wachs Cutter Tooling Station (4495)

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

    purchase, build and install Wachs cutter tooling. The Wachs Cutter Tooling Station is similar to previously operated facility tooling and will utilize an existing hydraulic unit....

  5. BIOMASS COGASIFICATION AT POLK POWER STATION

    SciTech Connect (OSTI)

    John McDaniel

    2002-05-01

    Part of a closed loop biomass crop was recently harvested to produce electricity in Tampa Electric's Polk Power Station Unit No.1. No technical impediments to incorporating a small percentage of biomass into Polk Power Station's fuel mix were identified. Appropriate dedicated storage and handling equipment would be required for routine biomass use. Polk Unit No.1 is an integrated gasification combined cycle (IGCC) power plant. IGCC is a new approach to generating electricity cleanly from solid fuels such as coal, petroleum coke, The purpose of this experiment was to demonstrate the Polk Unit No.1 could process biomass as a fraction of its fuel without an adverse impact on availability and plant performance. The biomass chosen for the test was part of a crop of closed loop Eucalyptus trees.

  6. Nuclear Energy Programs

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

    Nuclear Energy Programs Solving Nuclear Energy Technical Challenges Our science and technology are making way for new nuclear fuels and reactor materials. Get Expertise David Teter Email Generating breakthroughs in nuclear energy materials Safe and sustainable nuclear energy is a focus of the Laboratory's energy security mission, and our expertise in materials science plays an important role. With collaborators worldwide, Los Alamos is developing technologies for future nuclear reactor designs

  7. Alternative Fuels Data Center: Ethanol Fueling Stations

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Fueling Stations to someone by E-mail Share Alternative Fuels Data Center: Ethanol Fueling Stations on Facebook Tweet about Alternative Fuels Data Center: Ethanol Fueling Stations on Twitter Bookmark Alternative Fuels Data Center: Ethanol Fueling Stations on Google Bookmark Alternative Fuels Data Center: Ethanol Fueling Stations on Delicious Rank Alternative Fuels Data Center: Ethanol Fueling Stations on Digg Find More places to share Alternative Fuels Data Center: Ethanol Fueling Stations on

  8. Alternative Fuels Data Center: Hydrogen Fueling Stations

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Fueling Stations to someone by E-mail Share Alternative Fuels Data Center: Hydrogen Fueling Stations on Facebook Tweet about Alternative Fuels Data Center: Hydrogen Fueling Stations on Twitter Bookmark Alternative Fuels Data Center: Hydrogen Fueling Stations on Google Bookmark Alternative Fuels Data Center: Hydrogen Fueling Stations on Delicious Rank Alternative Fuels Data Center: Hydrogen Fueling Stations on Digg Find More places to share Alternative Fuels Data Center: Hydrogen Fueling Stations

  9. Alternative Fuels Data Center: Propane Fueling Stations

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Fueling Stations to someone by E-mail Share Alternative Fuels Data Center: Propane Fueling Stations on Facebook Tweet about Alternative Fuels Data Center: Propane Fueling Stations on Twitter Bookmark Alternative Fuels Data Center: Propane Fueling Stations on Google Bookmark Alternative Fuels Data Center: Propane Fueling Stations on Delicious Rank Alternative Fuels Data Center: Propane Fueling Stations on Digg Find More places to share Alternative Fuels Data Center: Propane Fueling Stations on

  10. Analysis of core uncovery time in Kuosheng station blackout transient with MELCOR

    SciTech Connect (OSTI)

    Wang, S.J.; Chien, C.S. [Inst. of Nuclear Energy Research, Lungtan (Taiwan, Province of China)

    1996-02-01

    The MELCOR code, developed by the Sandia National Laboratories, is capable of simulating severe accident phenomena of nuclear power plants. Core uncovery time is an important parameter in the probabilistic risk assessment. However, many MELCOR users do not generate the initial conditions in a station blackout (SBO) transient analysis. Thus, achieving reliable core uncovery time is difficult. The core uncovery time for the Kuosheng nuclear power plant during an SBO transient is analyzed. First, full-power steady-state conditions are generated with the application of a developed self-initialization algorithm. Then the response of the SBO transient up to core uncovery is simulated. The effects of key parameters including the initialization process and the reactor feed pump (RFP) coastdown time on the core uncovery time are analyzed. The initialization process is the most important parameter that affects the core uncovery time. Because SBO transient analysis, the correct initial conditions must be generated to achieve a reliable core uncovery time. The core uncovery time is also sensitive to the RFP coastdown time. A correct time constant is required.

  11. Loss of pressurizer water level during station blackout

    SciTech Connect (OSTI)

    Griggs, D.P.; Riggs, B.K.

    1986-01-01

    Station blackout is the loss of all alternating current (ac) power to both the essential and nonessential electrical buses in a nuclear power plant. The US Nuclear Regulatory Commission (NRC) has proposed a requirement that all plants be capable of maintaining adequate core cooling during station blackout events lasting a specified duration. The NRC has also suggested acceptable specified durations of four or eight hours, depending on individual plant susceptibility to blackout events. In a pressurized water reactor (PWR), the occurrence of a station blackout event results in the functional loss of many plant components, including main feedwater, reactor coolant pumps, the emergency core cooling system, and pressurizer heaters and spray. Nevertheless, PWRs have the capability of removing decay heat for some period of time using steam-driven auxiliary feedwater pumps and the natural-circulation capability of the primary system. The purpose of this investigation is to determine the early response of a PWR to station blackout conditions. In particular, the effect of primary coolant shrinkage and inventory loss on pressurizer level is examined to gain insight into the operational and analytical issues associated with the proposed station blackout coping requirement.

  12. 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

  13. Nuclear Propulsion in Space (1968)

    ScienceCinema (OSTI)

    None

    2014-06-17

    Project NERVA was an acronym for Nuclear Engine for Rocket Vehicle Application, a joint program of the U.S. Atomic Energy Commission and NASA managed by the Space Nuclear Propulsion Office (SNPO) at the Nuclear Rocket Development Station in Jackass Flats, Nevada U.S.A. Between 1959 and 1972, the Space Nuclear Propulsion Office oversaw 23 reactor tests, both the program and the office ended at the end of 1972.

  14. Nuclear Propulsion in Space (1968)

    SciTech Connect (OSTI)

    2012-06-23

    Project NERVA was an acronym for Nuclear Engine for Rocket Vehicle Application, a joint program of the U.S. Atomic Energy Commission and NASA managed by the Space Nuclear Propulsion Office (SNPO) at the Nuclear Rocket Development Station in Jackass Flats, Nevada U.S.A. Between 1959 and 1972, the Space Nuclear Propulsion Office oversaw 23 reactor tests, both the program and the office ended at the end of 1972.

  15. Study of a Station Blackout Event in the PWR Plant

    SciTech Connect (OSTI)

    Ching-Hui Wu; Tsu-Jen Lin; Tsu-Mu Kao [Institute of Nuclear Energy Research P.O. Box 3-3, Longtan, 32500, Taiwan (China)

    2002-07-01

    On March 18, 2001, a PWR nuclear power plant located in the Southern Taiwan occurred a Station Blackout (SBO) event. Monsoon seawater mist caused the instability of offsite power grids. High salt-contained mist caused offsite power supply to the nuclear power plant very unstable, and forced the plant to be shutdown. Around 24 hours later, when both units in the plant were shutdown, several inadequate high cycles of bus transfer between 345 kV and 161 kV startup transformers degraded the emergency 4.16 kV switchgears. Then, in the Train-A switchgear room of Unit 1 occurred a fire explosion, when the degraded switchgear was hot shorted at the in-coming 345 kV breaker. Inadequate configuration arrangement of the offsite power supply to the emergency 4.16 kV switchgears led to loss of offsite power (LOOP) events to both units in the plant. Both emergency diesel generators (EDG) of Unit 1 could not be in service in time, but those of Unit 2 were running well. The SBO event of Unit 1 lasted for about two hours till the fifth EDG (DG-5) was lined-up to the Train-B switchgear. This study investigated the scenario of the SBO event and evaluated a risk profile for the SBO period. Guidelines in the SBO event, suggested by probabilistic risk assessment (PRA) procedures were also reviewed. Many related topics such as the re-configuration of offsite power supply, the addition of isolation breakers of the emergency 4.16 kV switchgears, the betterment of DG-5 lineup design, and enhancement of the reliability of offsite power supply to the PWR plant, etc., will be in further studies. (authors)

  16. Polk power station syngas cooling system

    SciTech Connect (OSTI)

    Jenkins, S.D.

    1995-01-01

    Tampa Electric Company (TEC) is in the site development and construction phase of the new Polk Power Station Unit No. 1. This will be the first unit at a new site and will use Integrated Gasification Combined Cycle (IGCC) Technology. The unit will utilize Texaco`s oxygen-blown, entrained-flow coal gasification, along with combined cycle power generation, to produce nominal 260MW. Integral to the gasification process is the syngas cooling system. The design, integration, fabrication, transportation, and erection of this equipment have provided and continue to provide major challenges for this project.

  17. EIA - State Nuclear Profiles

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

    FirstEnergy Nuclear Operating Company Perry Unit 1 1,240 10,620 67.2 FirstEnergy ... Perry Nuclear Power Plant Unit Summer capacity (mw) Net generation (thousand mwh) Summer ...

  18. Alternative Fuels Data Center: Biodiesel Fueling Stations

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Fueling Stations to someone by E-mail Share Alternative Fuels Data Center: Biodiesel Fueling Stations on Facebook Tweet about Alternative Fuels Data Center: Biodiesel Fueling Stations on Twitter Bookmark Alternative Fuels Data Center: Biodiesel Fueling Stations on Google Bookmark Alternative Fuels Data Center: Biodiesel Fueling Stations on Delicious Rank Alternative Fuels Data Center: Biodiesel Fueling Stations on Digg Find More places to share Alternative Fuels Data Center: Biodiesel Fueling

  19. WVU Hydrogen Fuel Dispensing Station

    SciTech Connect (OSTI)

    Davis, William

    2015-09-01

    The scope of this project was changed during the course of the project. Phase I of the project was to construct a site similar to the site at Central West Virginia Regional Airport in Charleston, WV to show that duplication of the site was a feasible method of conducting hydrogen stations. Phase II of the project was necessitated due to a lack of funding that was planned for the development of the station in Morgantown. The US Department of Energy determined that the station in Charleston would be dismantled and moved to Morgantown and reassembled at the Morgantown site. This necessitated storage of the components of the station for almost a year at the NAFTC Headquarters which caused a number of issues with the equipment that will be discussed in later portions of this report. This report will consist of PHASE I and PHASE II with discussions on each of the tasks scheduled for each phase of the project.

  20. Energy Department Launches Alternative Fueling Station Locator...

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

    stations across the country. Users can search for stations that offer electricity, biodiesel (B20), natural gas (compressed and liquefied), ethanol (E85), hydrogen, and propane....

  1. Hydrogen Fueling Infrastructure Research and Station Technology...

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

    Infrastructure Research and Station Technology Webinar Slides Hydrogen Fueling Infrastructure Research and Station Technology Webinar Slides Download presentation slides from the...

  2. Shimian Dagoutou Hydropower Station | Open Energy Information

    Open Energy Info (EERE)

    Dagoutou Hydropower Station Jump to: navigation, search Name: Shimian Dagoutou Hydropower Station Place: Ya'an, Sichuan Province, China Zip: 625400 Sector: Hydro Product:...

  3. Liuyang Hedong Hydropower Station | Open Energy Information

    Open Energy Info (EERE)

    Liuyang Hedong Hydropower Station Jump to: navigation, search Name: Liuyang Hedong Hydropower Station Place: Liuyang, Hunan Province, China Zip: 410305 Sector: Hydro Product:...

  4. Eryuan Huian Hydropower Station | Open Energy Information

    Open Energy Info (EERE)

    Eryuan Huian Hydropower Station Jump to: navigation, search Name: Eryuan Huian Hydropower Station Place: Dali Bai Autonomous Prefecture, Yunnan Province, China Zip: 671200 Sector:...

  5. Tianlin Baxin Hydropower Station | Open Energy Information

    Open Energy Info (EERE)

    Baxin Hydropower Station Jump to: navigation, search Name: Tianlin Baxin Hydropower Station Place: Baise, Guangxi Autonomous Region, China Zip: 533000 Sector: Hydro Product:...

  6. Shimian Danihe Hydropower Station | Open Energy Information

    Open Energy Info (EERE)

    Danihe Hydropower Station Jump to: navigation, search Name: Shimian Danihe Hydropower Station Place: Ya'an, Sichuan Province, China Zip: 625400 Sector: Hydro Product: China-based...

  7. Reference Designs for Hydrogen Fueling Stations

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

    ... greenfield and gasoline station co-location. 35 Summary * The Reference Station Design Task has produced results that include: - Vehicle roll-out scenarios - Detailed ...

  8. Franklin Heating Station | Open Energy Information

    Open Energy Info (EERE)

    search Name: Franklin Heating Station Place: Minnesota Phone Number: 5072893534 Facebook: https:www.facebook.compagesFranklin-Heating-Station116610418398578 References:...

  9. Ohaaki Geothermal Power Station | Open Energy Information

    Open Energy Info (EERE)

    Station General Information Name Ohaaki Geothermal Power Station Sector Geothermal energy Location Information Location 20km NE of Taupo, Waikato, New Zealand Coordinates...

  10. Fang Geothermal Power Station | Open Energy Information

    Open Energy Info (EERE)

    Power Station General Information Name Fang Geothermal Power Station Sector Geothermal energy Location Information Coordinates 19.961842432467, 99.107366035005 Loading map......

  11. Mokai Geothermal Power Station | Open Energy Information

    Open Energy Info (EERE)

    Station General Information Name Mokai Geothermal Power Station Sector Geothermal energy Location Information Location Waikato, New Zealand Coordinates -38.530556,...

  12. Poihipi Power Station | Open Energy Information

    Open Energy Info (EERE)

    Poihipi Power Station General Information Name Poihipi Power Station Sector Geothermal energy Location Information Location Poihipi Road, Near Taupo, Waikato, New Zealand...

  13. Larderello Geothermal Power Station | Open Energy Information

    Open Energy Info (EERE)

    Station General Information Name Larderello Geothermal Power Station Sector Geothermal energy Location Information Location Larderello, Pisa, Italy Coordinates 43.236, 10.8672...

  14. Krafla Geothermal Power Station | Open Energy Information

    Open Energy Info (EERE)

    Station General Information Name Krafla Geothermal Power Station Sector Geothermal energy Location Information Location Krafla Volcanoe, Iceland Coordinates 65.703861,...

  15. Reykjanes Geothermal Power Station | Open Energy Information

    Open Energy Info (EERE)

    Station General Information Name Reykjanes Geothermal Power Station Sector Geothermal energy Location Information Location Reykjanes, Iceland Coordinates 63.826389, -22.681944...

  16. Svartsengi Geothermal Power Station | Open Energy Information

    Open Energy Info (EERE)

    Station General Information Name Svartsengi Geothermal Power Station Sector Geothermal energy Location Information Location Reykjanes Peninsula, Iceland Coordinates 63.878611,...

  17. Kawerau Geothermal Power Station | Open Energy Information

    Open Energy Info (EERE)

    Station General Information Name Kawerau Geothermal Power Station Sector Geothermal energy Location Information Location Bay of Plenty Region, New Zealand Coordinates...

  18. Technical Analysis of the Hydrogen Energy Station Concept, Phase I and Phase II

    SciTech Connect (OSTI)

    TIAX, LLC

    2005-05-04

    Phase I Due to the growing interest in establishing a domestic hydrogen infrastructure, several hydrogen fueling stations already have been established around the country as demonstration units. While these stations help build familiarity with hydrogen fuel in their respective communities, hydrogen vehicles are still several years from mass production. This limited number of hydrogen vehicles translates to a limited demand for hydrogen fuel, a significant hurdle for the near-term establishment of commercially viable hydrogen fueling stations. By incorporating a fuel cell and cogeneration system with a hydrogen fueling station, the resulting energy station can compensate for low hydrogen demand by providing both hydrogen dispensing and combined heat and power (CHP) generation. The electrical power generated by the energy station can be fed back into the power grid or a nearby facility, which in turn helps offset station costs. Hydrogen production capacity not used by vehicles can be used to support building heat and power loads. In this way, an energy station can experience greater station utility while more rapidly recovering capital costs, providing an increased market potential relative to a hydrogen fueling station. At an energy station, hydrogen is generated on-site. Part of the hydrogen is used for vehicle refueling and part of the hydrogen is consumed by a fuel cell. As the fuel cell generates electricity and sends it to the power grid, excess heat is reclaimed through a cogeneration system for use in a nearby facility. Both the electrical generation and heat reclamation serve to offset the cost of purchasing the equivalent amount of energy for nearby facilities and the energy station itself. This two-phase project assessed the costs and feasibility of developing a hydrogen vehicle fueling station in conjunction with electricity and cogenerative heat generation for nearby Federal buildings. In order to determine which system configurations and operational patterns would be most viable for an energy station, TIAX developed several criteria for selecting a representative set of technology configurations. TIAX applied these criteria to all possible technology configurations to determine an optimized set for further analysis, as shown in Table ES-1. This analysis also considered potential energy station operational scenarios and their impact upon hydrogen and power production. For example, an energy station with a 50-kWe reformer could generate enough hydrogen to serve up to 12 vehicles/day (at 5 kg/fill) or generate up to 1,200 kWh/day, as shown in Figure ES-1. Buildings that would be well suited for an energy station would utilize both the thermal and electrical output of the station. Optimizing the generation and utilization of thermal energy, hydrogen, and electricity requires a detailed look at the energy transfer within the energy station and the transfer between the station and nearby facilities. TIAX selected the Baseline configuration given in Table ES-1 for an initial analysis of the energy and mass transfer expected from an operating energy station. Phase II The purpose of this technical analysis was to analyze the development of a hydrogen-dispensing infrastructure for transportation applications through the installation of a 50-75 kW stationary fuel cell-based energy station at federal building sites. The various scenarios, costs, designs and impacts of such a station were quantified for a hypothetical cost-shared program that utilizes a natural gas reformer to provide hydrogen fuel for both the stack(s) and a limited number of fuel cell powered vehicles, with the possibility of using cogeneration to support the building heat load.

  19. Civilian Nuclear Programs

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

    The Civilian Nuclear Programs Office is the focal point for nuclear energy research and development and next-generation repository science at Los Alamos National Laboratory. Civilian Nuclear Programs Los Alamos is committed to using its advanced nuclear expertise and unique facilities to meet the civilian nuclear national security demands of the future. CONTACT US Program Director Venkateswara Rao Dasari (Rao) (505) 667-5098 Email Los Alamos partners extensively with other laboratories,

  20. EIS-0415: Deer Creek Station Energy Facility Project, South Dakota

    Broader source: Energy.gov [DOE]

    This EIS analyzes WAPA's decision to approve the interconnection request made by Basin Electric Power Cooperative (Basin Electric) with the USDA Rural Utilities Service (RUS) proposing to provide financial assistance, for the Deer Creek Station Project, a proposed 300-megawatt (MW) natural gas-fired generation facility.

  1. Development of a Turnkey Hydrogen Fueling Station Final Report

    SciTech Connect (OSTI)

    David E. Guro; Edward Kiczek; Kendral Gill; Othniel Brown

    2010-07-29

    The transition to hydrogen as a fuel source presents several challenges. One of the major hurdles is the cost-effective production of hydrogen in small quantities (less than 1MMscf/month). In the early demonstration phase, hydrogen can be provided by bulk distribution of liquid or compressed gas from central production plants; however, the next phase to fostering the hydrogen economy will likely include onsite generation and extensive pipeline networks to help effect a pervasive infrastructure. Providing inexpensive hydrogen at a fleet operators garage or local fueling station is a key enabling technology for direct hydrogen Fuel Cell Vehicles (FCVs). The objective of this project was to develop a comprehensive, turnkey, stand-alone, commercial hydrogen fueling station for FCVs with state-of-the-art technology that is cost-competitive with current hydrocarbon fuels. Such a station would promote the advent of the hydrogen fuel economy for buses, fleet vehicles, and ultimately personal vehicles. Air Products, partnering with the U.S. Department of Energy (DOE), The Pennsylvania State University, Harvest Energy Technology, and QuestAir, developed a turnkey hydrogen fueling station on the Penn State campus. Air Products aimed at designing a station that would have 65% overall station efficiency, 82% PSA (pressure swing adsorption) efficiency, and the capability of producing hydrogen at $3.00/kg (gge) H2 at mass production rates. Air Products designed a fueling station at Penn State from the ground up. This project was implemented in three phases. The first phase evaluated the various technologies available in hydrogen generation, compression, storage, and gas dispensing. In the second phase, Air Products designed the components chosen from the technologies examined. Finally, phase three entailed a several-month period of data collection, full-scale operation, maintenance of the station, and optimization of system reliability and performance. Based on field data analysis, it was determined by a proprietary hydrogen-analysis model that hydrogen produced from the station at a rate of 1500 kg/day and when produced at 1000 stations per year would be able to deliver hydrogen at a price of $3.03/kg (gge) H2. The stations efficiency was measured to be 65.1%, and the PSA was tested and ran at an efficiency of 82.1%, thus meeting the project targets. From the study, it was determined that more research was needed in the area of hydrogen fueling. The overall cost of the hydrogen energy station, when combined with the required plot size for scaled-up hydrogen demands, demonstrated that a station using steam methane reforming technology as a means to produce onsite hydrogen would have limited utility in the marketplace. Alternative hydrogen supplies, such as liquid or pipeline delivery to a refueling station, need to be included in the exploration of alternative energy site layouts. These avenues need to be explored before a definitive refueling station configuration and commercialization pathway can be determined.

  2. More California Gas Stations Can Provide Hydrogen than Previously Thought,

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

    Sandia Study Says California Gas Stations Can Provide Hydrogen than Previously Thought, Sandia Study Says - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid

  3. Springerville Generating Station Solar System Solar Power Plant...

    Open Energy Info (EERE)

    This article is a stub. You can help OpenEI by expanding it. References http:www.tep.comGreenGreenWattssolaroutput.asp Retrieved from "http:en.openei.orgw...

  4. Grand Blanc Generating Station Biomass Facility | Open Energy...

    Open Energy Info (EERE)

    (MW) 4.04 MW 4,000 kW 4,000,000 W 4,000,000,000 mW 0.004 GW Commercial Online Date 1994 Heat Rate (BTUkWh) 11079.9 References EPA Web Site1 Loading map......

  5. Ottawa Generating Station Biomass Facility | Open Energy Information

    Open Energy Info (EERE)

    4.84.8 MW 4,800 kW 4,800,000 W 4,800,000,000 mW 0.0048 GW Commercial Online Date 1994 Heat Rate (BTUkWh) 11797.1 References EPA Web Site1 Loading map......

  6. Distributed Generation Study/Dakota Station (Minnegasco) | Open...

    Open Energy Info (EERE)

    Study Technology Microturbine Prime Mover Capstone C30 Heat Recovery Systems Unifin Fuel Natural Gas System Installer Capstone Turbine Corp System Enclosure Outdoor System...

  7. Re: Potomac River Generating Station Department of Energy, Case No.

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

    EO-05-01: Potomac Electric Power Company (PEPCO) Concerning Planned Outages of the 230 kV circuits | Department of Energy No. EO-05-01. Order No. 202-07-02: Pursuant to the Department of Energy's Order No. 202-05-3 issued December 20, 2005 ("DOE Potomac River Order"), Pepco has filed notice of the planned outages, in sequence during January 2006, of each of the two 230 kV circuits serving the downtown area of the District of Columbia. Earlier scheduled maintenance on these lines

  8. Re: Potomac River Generating Station Department of Energy Case...

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

    PEPCO is providing you with information regarding the planned transmission maintenance ... you with information regarding the planned transmission maintenance outage Docket No. ...

  9. Microsoft Word - Columbia Generating Station Electric Rev Bonds...

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

    Tax Reform Act of 1986, as amended (the "1986 Act") and Section 103 of the Internal Revenue Code of 1986, as amended (the "1986 Code"). In the further opinion of Special Tax...

  10. Workplace Charging Station Basics | Department of Energy

    Energy Savers [EERE]

    Station Basics Workplace Charging Station Basics As your organization moves forward with workplace charging, it is important to understand the fundamental differences and similarities between the types of charging stations, commonly referred to as electric vehicle supply equipment (EVSE) units. Charging stations deliver electrical energy from an electricity source to a plug-in electric vehicle (PEV) battery. There are three primary types of charging stations: AC Level 1, AC Level 2 and DC fast

  11. Pala Fire Station Solar Project

    Energy Savers [EERE]

    Pala Fire Station Solar Project Pala Band of Mission Indians Pala Environmental Department Pala Fire Departme nt The Pala Reservation  Located in San Diego County, California  Approximately 13,000 acres  Over 1,000 tribal members  Home to approximately 1,350 people The Pala Reservation  Over 800 houses and buildings  New houses all have PV solar  Main energy users:  Pala Casino Resort & Spa  Pala Fire Station  Pala Administration complex Long-term goal:

  12. Irradiation Environment of the Materials Test Station

    SciTech Connect (OSTI)

    Pitcher, Eric John

    2012-06-21

    Conceptual design of the proposed Materials Test Station (MTS) at the Los Alamos Neutron Science Center (LANSCE) is now complete. The principal mission is the irradiation testing of advanced fuels and materials for fast-spectrum nuclear reactor applications. The neutron spectrum in the fuel irradiation region of MTS is sufficiently close to that of fast reactor that MTS can match the fast reactor fuel centerline temperature and temperature profile across a fuel pellet. This is an important characteristic since temperature and temperature gradients drive many phenomena related to fuel performance, such as phase stability, stoichiometry, and fission product transport. The MTS irradiation environment is also suitable in many respects for fusion materials testing. In particular, the rate of helium production relative to atomic displacements at the peak flux position in MTS matches well that of fusion reactor first wall. Nuclear transmutation of the elemental composition of the fusion alloy EUROFER97 in MTS is similar to that expected in the first wall of a fusion reactor.

  13. Nuclear reactor characteristics and operational history

    Gasoline and Diesel Fuel Update (EIA)

    1. Capacity and Generation, Table 3. Characteristics and Operational History Table 2. U.S. Nuclear Reactor Ownership Data PDF XLS Plant/Reactor Name Generator ID Utility Name - Operator Owner Name % Owned Arkansas Nuclear One 1 Entergy Arkansas Inc Entergy Arkansas Inc 100 Arkansas Nuclear One 2 Entergy Arkansas Inc Entergy Arkansas Inc 100 Beaver Valley 1 FirstEnergy Nuclear Operating Company FirstEnergy Nuclear Generation Corp 100 Beaver Valley 2 FirstEnergy Nuclear Operating Company

  14. NOAA PMEL Station Chemistry Data

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Quinn, Patricia

    2008-04-04

    Submicron and supermicron samples are analyzed by ion chromatography for Cl-, NO3-, SO4-2, Na+, NH4+, K+, Mg2+, and Ca+2. The analysis of MSA-, Br-, and oxalate has been added to some stations. Samples also are analyzed for total mass by gravimetric analysis at 55 +/- 5% RH.

  15. Mobile Alternative Fueling Station Locator

    SciTech Connect (OSTI)

    Not Available

    2009-04-01

    The Department of Energy's Alternative Fueling Station Locator is available on-the-go via cell phones, BlackBerrys, or other personal handheld devices. The mobile locator allows users to find the five closest biodiesel, electricity, E85, hydrogen, natural gas, and propane fueling sites using Google technology.

  16. A HYDROGEN IGNITION MECHANISM FOR EXPLOSIONS IN NUCLEAR FACILITY PIPING SYSTEMS

    SciTech Connect (OSTI)

    Leishear, R.

    2013-03-28

    Hydrogen explosions may occur simultaneously with water hammer accidents in nuclear facilities, and a theoretical mechanism to relate water hammer to hydrogen deflagrations and explosions is presented herein. Hydrogen and oxygen generation due to the radiolysis of water is a recognized hazard in pipe systems used in the nuclear industry, where the accumulation of hydrogen and oxygen at high points in the pipe system is expected, and explosive conditions may occur. Pipe ruptures in nuclear reactor cooling systems were attributed to hydrogen explosions inside pipelines, i.e., Hamaoka, Nuclear Power Station in Japan, and Brunsbuettel in Germany. Prior to these accidents, an ignition source for hydrogen was not clearly demonstrated, but these accidents demonstrated that a mechanism was, in fact, available to initiate combustion and explosion. A new theory to identify an ignition source and explosion cause is presented here, and further research is recommended to fully understand this explosion mechanism.

  17. Building upon Historical Competencies: Next-generation Clean-up Technologies for World-Wide Application - 13368

    SciTech Connect (OSTI)

    Guevara, K.C.; Fellinger, A.P.; Aylward, R.S.; Griffin, J.C.; Hyatt, J.E.; Bush, S.R.

    2013-07-01

    The Department of Energy's Savannah River Site has a 60-year history of successfully operating nuclear facilities and cleaning up the nuclear legacy of the Cold War era through the processing of radioactive and otherwise hazardous wastes, remediation of contaminated soil and groundwater, management of nuclear materials, and deactivation and decommissioning of excess facilities. SRS recently unveiled its Enterprise.SRS (E.SRS) strategic vision to identify and facilitate application of the historical competencies of the site to current and future national and global challenges. E.SRS initiatives such as the initiative to Develop and Demonstrate Next generation Clean-up Technologies seek timely and mutually beneficial engagements with entities around the country and the world. One such ongoing engagement is with government and industry in Japan in the recovery from the devastation of the Fukushima Daiichi Nuclear Power Station. (authors)

  18. 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.

  19. Analysis of a Nuclear Accident: Fission and Activation Product Releases from the Fukushima Daiichi Nuclear Facility as Remote Indicators of Source Identification, Extent of Release, and State of Damaged Spent Nuclear Fuel

    SciTech Connect (OSTI)

    Schwantes, Jon M.; Orton, Christopher R.; Clark, Richard A.

    2011-12-05

    Evidence of the release Pu from the Fukushima Daiichi nuclear power station to the local environment and surrounding communities and estimates on fraction of total fuel inventory released

  20. The status and prospective of environmental radiation monitoring stations in Saudi Arabia

    SciTech Connect (OSTI)

    Al-Kheliewi, Abdullah S.; Holzheimer, Clous

    2014-09-30

    The use of nuclear technology requires an environmental monitoring program to ensure the safety of the environment, and to protect people from the hazards of radioactive materials, and nuclear accidents. Nuclear accidents are unique, for they incur effects that surpass international frontiers, and can even have a long lasting impact on Earth. Such was the case of the Chernobyl accident in the Ukraine on April 6, 1986. For that purpose, international and national efforts come together to observe for any nuclear or radioactive accident. Many states, including Saudi Arabia which oversees the operation of the National Radiation, Environmental and Early Monitoring Stations, The Radiation Monitoring Stations(RMSs) are currently scattered across 35 cities in the country,. These locations are evaluated based on various technological criteria such as border cities, cities of high population density, wind direction, etc. For new nuclear power plants hovering around, it is strongly recommended to increase the number of radiation monitoring stations to warn against any threat that may arise from a nuclear leak or accident and to improve the performance of the existing RMSs. SARA (Spectroscopic Monitoring Station for air) should be implemented due to the high sensitivity to artificial radiation, automatic isotope identification, free of maintenance, and fully independent due to solar power supply (incl. battery backup) and wireless communication (GPRS)

  1. Biodiesel Filling Stations UK | Open Energy Information

    Open Energy Info (EERE)

    Filling Stations UK Jump to: navigation, search Name: Biodiesel Filling Stations UK Place: United Kingdom Product: A website providing a list of places in the UK where people can...

  2. Energy Department Launches Alternative Fueling Station Locator...

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

    on more than 15,000 stations across the country. Users can search for stations that offer electricity, biodiesel (B20), natural gas (compressed and liquefied), ethanol (E85),...

  3. Nesjavellir Geothermal Power Station | Open Energy Information

    Open Energy Info (EERE)

    General Information Name Nesjavellir Geothermal Power Station Sector Geothermal energy Location Information Location Thingvellir, Iceland Coordinates 64.108164743246,...

  4. International training course on implementation of state systems of accounting for and control of nuclear materials: proceedings

    SciTech Connect (OSTI)

    Not Available

    1986-06-01

    This report incorporates all lectures and presentations at the International Training Course on Implementation of State Systems of Accounting for and Control of Nuclear Materials held June 3 through June 21, 1985, at Santa Fe and Los Alamos, New Mexico, and San Clemente, California. Authorized by the US Nuclear Non-Proliferation Act and sponsored by the US Department of Energy in cooperation with the International Atomic Energy Agency, the Course was developed to provide practical training in the design, implementation, and operation of a state system of nuclear materials accountability and control that satisfies both national and international safeguards requirements. Major emphasis for the 1985 course was placed on safeguards methods used at item-control facilities, particularly nuclear power generating stations and test reactors. An introduction to safeguards methods used at bulk handling facilities, particularly low-enriched uranium conversion and fuel fabrication plants, was also included. The course was conducted by the University of California's Los Alamos National Laboratory and the Southern California Edison Company. Tours and demonstrations were arranged at the Los Alamos National Laboratory, Los Alamos, New Mexico, and the San Onofre Nuclear Generating Station, San Clemente, California.

  5. Archbald Power Station Biomass Facility | Open Energy Information

    Open Energy Info (EERE)

    Archbald Power Station Biomass Facility Jump to: navigation, search Name Archbald Power Station Biomass Facility Facility Archbald Power Station Sector Biomass Facility Type...

  6. Elk City Station Biomass Facility | Open Energy Information

    Open Energy Info (EERE)

    Station Biomass Facility Jump to: navigation, search Name Elk City Station Biomass Facility Facility Elk City Station Sector Biomass Facility Type Landfill Gas Location Douglas...

  7. Lowry Range Solar Station: Arapahoe County, Colorado (Data)

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Yoder, M.; Andreas, A.

    A partnership with industry and U.S. Department of Energy's National Renewable Energy Laboratory (NREL) to collect solar data to support future solar power generation in the United States. The measurement station monitors global horizontal, direct normal, and diffuse horizontal irradiance to define the amount of solar energy that hits this particular location. The solar measurement instrumentation is also accompanied by meteorological monitoring equipment to provide scientists with a complete picture of the solar power possibilities.

  8. Nevada Power: Clark Station; Las Vegas, Nevada (Data)

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Stoffel, T.; Andreas, A.

    A partnership with the University of Nevada and U.S. Department of Energy's National Renewable Energy Laboratory (NREL) to collect solar data to support future solar power generation in the United States. The measurement station monitors global horizontal, direct normal, and diffuse horizontal irradiance to define the amount of solar energy that hits this particular location. The solar measurement instrumentation is also accompanied by meteorological monitoring equipment to provide scientists with a complete picture of the solar power possibilities.

  9. Nevada Power: Clark Station; Las Vegas, Nevada (Data)

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Stoffel, T.; Andreas, A.

    2006-03-27

    A partnership with the University of Nevada and U.S. Department of Energy's National Renewable Energy Laboratory (NREL) to collect solar data to support future solar power generation in the United States. The measurement station monitors global horizontal, direct normal, and diffuse horizontal irradiance to define the amount of solar energy that hits this particular location. The solar measurement instrumentation is also accompanied by meteorological monitoring equipment to provide scientists with a complete picture of the solar power possibilities.

  10. Lowry Range Solar Station: Arapahoe County, Colorado (Data)

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Yoder, M.; Andreas, A.

    2008-05-30

    A partnership with industry and U.S. Department of Energy's National Renewable Energy Laboratory (NREL) to collect solar data to support future solar power generation in the United States. The measurement station monitors global horizontal, direct normal, and diffuse horizontal irradiance to define the amount of solar energy that hits this particular location. The solar measurement instrumentation is also accompanied by meteorological monitoring equipment to provide scientists with a complete picture of the solar power possibilities.

  11. Experimental Stations by Number | Stanford Synchrotron Radiation

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

    Lightsource Experimental Stations by Number Beam Line by Techniques Photon Source Parameters Station Type Techniques Energy Range Contact Person Experimental Station 1-5 X-ray Materials Small-angle X-ray Scattering (SAXS) focused 4600-16000 eV Christopher J. Tassone Tim J. Dunn Experimental Station 2-1 X-ray Powder diffraction Thin film diffraction Focused 5000 - 14500 eV Apurva Mehta Charles Troxel Jr Experimental Station 2-2 X-ray X-ray Absorption Spectroscopy 1000-40000 eV Ryan Davis

  12. 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.

  13. License Amendment Request for Storing Exelon Sister Nuclear Stations...

    Office of Scientific and Technical Information (OSTI)

    The facility was designed to store low-level radioactive waste (LLRW) on an interim basis, i.e., up to five years. The primary reason for the IRSF was to offset lack of disposal in ...

  14. Conceptual design of a submerged power station

    SciTech Connect (OSTI)

    Herring, J.S. )

    1992-01-01

    Providing safe and sustainable energy to the world's increasing population will be one of the major challenges of the 21st century. Idaho National Engineering Laboratory is developing the concept of a submerged power stations (SPS). The reactor is located in the forward part of the vessel, while the turbine and generator are in the midsection, and the control and crew quarters are located at the opposite end of the vessel. The current design of the SPS has a 22.5-m o.d., is 146 m long, and has a total mass, including seawater in the annular region between the hulls, of 47,000 t. The SPS would be operated in 20 to 100 m of water at a distance of 10 to 30 km from the shore and would generate 300 to 600 MW(electric) transmitted to shore by undersea cables. The SPS has the advantages of centralized fabrication and maintenance. The author believes that the SPS has significant safety and environmental advantages.

  15. conventional diesel generator

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

    conventional diesel generator - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel Cycle Defense Waste Management Programs

  16. next-generation biofuels

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

    next-generation biofuels - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel Cycle Defense Waste Management Programs Advanced

  17. Advanced Nuclear Energy Projects | Department of Energy

    Energy Savers [EERE]

    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

  18. Rancia 2 Geothermal Power Station | Open Energy Information

    Open Energy Info (EERE)

    Station General Information Name Rancia 2 Geothermal Power Station Sector Geothermal energy Location Information Location Tuscany, Italy Geothermal Resource Area...

  19. Travale 4 Geothermal Power Station | Open Energy Information

    Open Energy Info (EERE)

    Station General Information Name Travale 4 Geothermal Power Station Sector Geothermal energy Location Information Location Tuscany, Italy Geothermal Resource Area...

  20. Light Water Reactor Sustainability Program: Analysis of Pressurized Water Reactor Station Blackout caused by external flooding using the RISMC toolkit

    SciTech Connect (OSTI)

    Mandelli, Diego; Smith, Curtis; Prescott, Steven; Alfonsi, Andrea; Rabiti, Cristian; Cogliati, Joshua; Kinoshita, Robert

    2014-08-01

    The existing fleet of nuclear power plants is in the process of extending its lifetime and increasing the power generated from these plants via power uprates. In order to evaluate the impacts of these two factors on the safety of the plant, the Risk Informed Safety Margin Characterization project aims to provide insights to decision makers through a series of simulations of the plant dynamics for different initial conditions (e.g., probabilistic analysis and uncertainty quantification). This paper focuses on the impacts of power uprate on the safety margin of a boiling water reactor for a flooding induced station black-out event. Analysis is performed by using a combination of thermal-hydraulic codes and a stochastic analysis tool currently under development at the Idaho National Laboratory, i.e. RAVEN. We employed both classical statistical tools, i.e. Monte-Carlo, and more advanced machine learning based algorithms to perform uncertainty quantification in order to quantify changes in system performance and limitations as a consequence of power uprate. Results obtained give a detailed investigation of the issues associated with a plant power uprate including the effects of station black-out accident scenarios. We were able to quantify how the timing of specific events was impacted by a higher nominal reactor core power. Such safety insights can provide useful information to the decision makers to perform risk informed margins management.

  1. 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.

  2. 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.

  3. 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.

  4. Demonstration of fully coupled simplified extended station black-out accident simulation with RELAP-7

    SciTech Connect (OSTI)

    Zhao, Haihua; Zhang, Hongbin; Zou, Ling; Anders, David; Martineau, Richard

    2014-10-01

    The RELAP-7 code is the next generation nuclear reactor system safety analysis code being developed at the Idaho National Laboratory (INL). The RELAP-7 code develop-ment effort started in October of 2011 and by the end of the second development year, a number of physical components with simplified two phase flow capability have been de-veloped to support the simplified boiling water reactor (BWR) extended station blackout (SBO) analyses. The demonstration case includes the major components for the primary system of a BWR, as well as the safety system components for the safety relief valve (SRV), the reactor core isolation cooling (RCIC) system, and the wet well. Three scenar-ios for the SBO simulations have been considered. Since RELAP-7 is not a severe acci-dent analysis code, the simulation stops when fuel clad temperature reaches damage point. Scenario I represents an extreme station blackout accident without any external cooling and cooling water injection. The system pressure is controlled by automatically releasing steam through SRVs. Scenario II includes the RCIC system but without SRV. The RCIC system is fully coupled with the reactor primary system and all the major components are dynamically simulated. The third scenario includes both the RCIC system and the SRV to provide a more realistic simulation. This paper will describe the major models and dis-cuss the results for the three scenarios. The RELAP-7 simulations for the three simplified SBO scenarios show the importance of dynamically simulating the SRVs, the RCIC sys-tem, and the wet well system to the reactor safety during extended SBO accidents.

  5. Utility perspective on station blackout rule implementation with NUMARC 87-00

    SciTech Connect (OSTI)

    Maracek, J.

    1990-01-01

    The development of the station blackout rule involved an unusually high level of cooperation between the industry and the Nuclear Regulatory Commission (NRC). The industry developed an approach to implementation of the rule in the form of the Nuclear Management and Resources Council's (NUMARC's) Guidelines and Technical Bases for NUMARC Initiatives Addressing Station Blackout at Light Water Reactors (NUMARC 87-00). This document was reviewed and accepted by the NRC staff as a means for meeting the requirements of the station blackout rule. Yet difficulties still arose when individual utilities used the NUMARC 87-00 approach to respond to the rule. This presentation examines the development process and subsequent difficulties and identifies potential improvements for development and implementation of new rules in the future.

  6. MRDIS Standalone Central Alarm Station

    Energy Science and Technology Software Center (OSTI)

    2012-09-12

    The MRDIS Standalone Central Alarm Station(MRDIS-CAS} is a software system for receiving, storing, and reviewing radiation data collected by the Mobile Radiation Detection and Identification System (MRDIS}, a mobile radiation scanning system developed for use in foreign ports for the DOE Megaports Initiative. It is designed to run on one of the on board computers in the MRDIS cab. It will collect, store, and display data from the MRDIS without the need for wireless communicationsmore » or centralized server technology. It is intended to be a lightweight replacement for a distributed Megaports communication system in ports where the necessary communications infrastructure does not exist for a full Megaports communications system.« less

  7. GC GUIDANCE ON ELECTRIC VEHICLE RECHARGING STATIONS

    Office of Environmental Management (EM)

    ELECTRIC VEHICLE RECHARGING STATIONS Several National Laboratory contractors have asked us whether Department of Energy ("Department" or "DOE") appropriated funds may be used to reimburse the lab contractors for the cost of installing electric vehicle recharging stations and to pay (whether by reimbursement or by DOE directly) electricity bill costs resulting from the use of such stations. As more fully discussed below, the labs have several options for installing electric

  8. 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.

  9. 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.

  10. Locating PHEV exchange stations in V2G

    SciTech Connect (OSTI)

    Pan, Feng; Bent, Russell; Berscheid, Alan; Izraelevitz, David

    2010-01-01

    Plug-in hybrid electric vehicle (PREV) is an environment friendly modem transportation method and has been rapidly penetrate the transportation system. Renewable energy is another contributor to clean power but the associated intermittence increases the uncertainty in power generation. As a foreseen benefit of a vchicle-to-grid (V2G) system, PREV supporting infrastructures like battery exchange stations can provide battery service to PREV customers as well as being plugged into a power grid as energy sources and stabilizer. The locations of exchange stations are important for these two objectives under constraints from both ,transportation system and power grid. To model this location problem and to understand and analyze the benefit of a V2G system, we develop a two-stage stochastic program to optimally locate the stations prior to the realizations of battery demands, loads, and generation capacity of renewable power sources. Based on this model, we use two data sets to construct the V2G systems and test the benefit and the performance of these systems.

  11. Schiller Station Biomass Facility | Open Energy Information

    Open Energy Info (EERE)

    National Map Retrieved from "http:en.openei.orgwindex.php?titleSchillerStationBiomassFacility&oldid398074" Feedback Contact needs updating Image needs updating...

  12. Boyd Station LLC | Open Energy Information

    Open Energy Info (EERE)

    navigation, search Name: Boyd Station LLC Place: Danville, Pennsylvania Product: A biodiesel technology testing facility in Danville, Pennsylvania. Coordinates: 38.081585,...

  13. GC GUIDANCE ON ELECTRIC VEHICLE RECHARGING STATIONS

    Broader source: Energy.gov [DOE]

    Several National Laboratory contractors have asked whether appropriated funds may be used to reimburse cost of installing electric vehicle recharging stations and to pay electricity bill costs...

  14. NREL Dedicates Advanced Hydrogen Fueling Station | Community...

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

    NREL Dedicates Advanced Hydrogen Fueling Station Ceremony Coincides With National Hydrogen and Fuel Cell Day October 8, 2015 The Energy Department's National Renewable Energy...

  15. Reference Designs for Hydrogen Fueling Stations Webinar

    Broader source: Energy.gov [DOE]

    Access the recording and download the presentation slides from the Fuel Cell Technologies Office webinar "Reference Designs for Hydrogen Fueling Stations" held on October 13, 2015.

  16. Station Footprint: Separation Distances, Storage Options, and...

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

    More Documents & Publications Light Duty Fuel Cell Electric Vehicle Hydrogen Fueling Protocol H2FIRST Reference Station Design Task: Project Deliverable 2-2 On-Board Storage ...

  17. Hellisheidi Geothermal Power Station | Open Energy Information

    Open Energy Info (EERE)

    General Information Name Hellisheidi Geothermal Power Station Sector Geothermal energy Location Information Location Hengill, Iceland Coordinates 64.037222, -21.400833...

  18. Summary of monitoring station component evaluation project 2009-2011.

    SciTech Connect (OSTI)

    Hart, Darren M.

    2012-02-01

    Sandia National Laboratories (SNL) is regarded as a center for unbiased expertise in testing and evaluation of geophysical sensors and instrumentation for ground-based nuclear explosion monitoring (GNEM) systems. This project will sustain and enhance our component evaluation capabilities. In addition, new sensor technologies that could greatly improve national monitoring system performance will be sought and characterized. This work directly impacts the Ground-based Nuclear Explosion Monitoring mission by verifying that the performance of monitoring station sensors and instrumentation is characterized and suitable to the mission. It enables the operational monitoring agency to deploy instruments of known capability and to have confidence in operational success. This effort will ensure that our evaluation capabilities are maintained for future use.

  19. Steam generator support system

    DOE Patents [OSTI]

    Moldenhauer, James E. (Simi Valley, CA)

    1987-01-01

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

  20. Steam generator support system

    DOE Patents [OSTI]

    Moldenhauer, J.E.

    1987-08-25

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

  1. Severe Accident Test Station Activity Report

    SciTech Connect (OSTI)

    Pint, Bruce A.; Terrani, Kurt A.

    2015-06-01

    Enhancing safety margins in light water reactor (LWR) severe accidents is currently the focus of a number of international R&D programs. The current UO2/Zr-based alloy fuel system is particularly susceptible since the Zr-based cladding experiences rapid oxidation kinetics in steam at elevated temperatures. Therefore, alternative cladding materials that offer slower oxidation kinetics and a smaller enthalpy of oxidation can significantly reduce the rate of heat and hydrogen generation in the core during a coolant-limited severe accident. In the U.S. program, the high temperature steam oxidation performance of accident tolerant fuel (ATF) cladding solutions has been evaluated in the Severe Accident Test Station (SATS) at Oak Ridge National Laboratory (ORNL) since 2012. This report summarizes the capabilities of the SATS and provides an overview of the oxidation kinetics of several candidate cladding materials. A suggested baseline for evaluating ATF candidates is a two order of magnitude reduction in the steam oxidation resistance above 1000C compared to Zr-based alloys. The ATF candidates are categorized based on the protective external oxide or scale that forms during exposure to steam at high temperature: chromia, alumina, and silica. Comparisons are made to literature and SATS data for Zr-based alloys and other less-protective materials.

  2. Nuclear Science

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

    Nuclear Science Nuclear Science Experimental and theoretical nuclear research carried out at NERSC is driven by the quest for improving our understanding of the building blocks of...

  3. ESBWR response to an extended station blackout/loss of all AC power

    SciTech Connect (OSTI)

    Barrett, A. J.; Marquino, W.

    2012-07-01

    U.S. federal regulations require light water cooled nuclear power plants to cope with Station Blackouts for a predetermined amount of time based on design factors for the plant. U.S. regulations define Station Blackout (SBO) as a loss of the offsite electric power system concurrent with turbine trip and unavailability of the onsite emergency AC power system. According to U.S. regulations, typically the coping period for an SBO is 4 hours and can be as long as 16 hours for currently operating BWR plants. Being able to cope with an SBO and loss of all AC power is required by international regulators as well. The U.S. licensing basis for the ESBWR is a coping period of 72 hours for an SBO based on U.S. NRC requirements for passive safety plants. In the event of an extended SBO (viz., greater than 72 hours), the ESBWR response shows that the design is able to cope with the event for at least 7 days without AC electrical power or operator action. ESBWR is a Generation III+ reactor design with an array of passive safety systems. The ESBWR primary success path for mitigation of an SBO event is the Isolation Condenser System (ICS). The ICS is a passive, closed loop, safety system that initiates automatically on a loss of power. Upon Station Blackout or loss of all AC power, the ICS begins removing decay heat from the Reactor Pressure Vessel (RPV) by (i) condensing the steam into water in heat exchangers located in pools of water above the containment, and (ii) transferring the decay heat to the atmosphere. The condensed water is then returned by gravity to cool the reactor again. The ICS alone is capable of maintaining the ESBWR in a safe shutdown condition after an SBO for an extended period. The fuel remains covered throughout the SBO event. The ICS is able to remove decay heat from the RPV for at least 7 days and maintains the reactor in a safe shutdown condition. The water level in the RPV remains well above the top of active fuel for the duration of the SBO event. Beyond 7 days, only a few simple actions are needed to cope with the SBO for an indefinite amount of time. The operation of the ICS as the primary success path for mitigation of an SBO, allows for near immediate plant restart once power is restored. (authors)

  4. Background noise spectra of global seismic stations

    SciTech Connect (OSTI)

    Wada, M.M.; Claassen, J.P.

    1996-08-01

    Over an extended period of time station noise spectra were collected from various sources for use in estimating the detection and location performance of global networks of seismic stations. As the database of noise spectra enlarged and duplicate entries became available, an effort was mounted to more carefully select station noise spectra while discarding others. This report discusses the methodology and criteria by which the noise spectra were selected. It also identifies and illustrates the station noise spectra which survived the selection process and which currently contribute to the modeling efforts. The resulting catalog of noise statistics not only benefits those who model network performance but also those who wish to select stations on the basis of their noise level as may occur in designing networks or in selecting seismological data for analysis on the basis of station noise level. In view of the various ways by which station noise were estimated by the different contributors, it is advisable that future efforts which predict network performance have available station noise data and spectral estimation methods which are compatible with the statistics underlying seismic noise. This appropriately requires (1) averaging noise over seasonal and/or diurnal cycles, (2) averaging noise over time intervals comparable to those employed by actual detectors, and (3) using logarithmic measures of the noise.

  5. LNG to CNG refueling stations

    SciTech Connect (OSTI)

    Branson, J.D.

    1995-12-31

    While the fleet operator is concerned about the environment, he or she is going to make the choice based primarily on economics. Which fuel provides the lowest total operating cost? The calculation of this costing must include the price-per-gallon of the fuel delivered, as well as the tangible and intangible components of fuel delivery, such as downtime for vehicles during the refueling process, idle time for drivers during refueling, emissions costings resulting from compressor oil blow-by, inclusion of non-combustible constituents in the CNG, and energy consumption during the refueling process. Also, the upfront capital requirement of similar delivery capabilities must be compared. The use of LNG as the base resource for the delivered CNG, in conjunction with the utilization of a fully temperature-compressed LNG/CNG refueling system, eliminates many of the perceived shortfalls of CNG. An LNG/CNG refueling center designed to match the capabilities of the compressor-based station will have approximately the same initial capital requirement. However, because it derives its CNG sales product from the {minus}260 F LNG base product, thus availing itself of the natural physical properties of the cryogenic product, all other economic elements of the system favor the LNG/CNG product.

  6. Burner balancing Salem Harbor Station

    SciTech Connect (OSTI)

    Sload, A.W.; Dube, R.J.

    1995-12-31

    The traditional method of burner balancing is first to determine the fuel distribution, then to measure the economizer outlet excess oxygen distribution and to adjust the burners accordingly. Fuel distribution is typically measured by clean and dirty air probing. Coal pipe flow can then be adjusted, if necessary, through the use of coal pipe orificing or by other means. Primary air flow must be adjusted to meet the design criteria of the burner. Once coal pipe flow is balanced to within the desired criteria, secondary air flow to individual burners can be changed by adjusting windbox dampers, burner registers, shrouds or other devices in the secondary air stream. This paper discusses problems encountered in measuring excess O{sub 2} at the economizer outlet. It is important to recognize that O{sub 2} measurements at the economizer outlet, by themselves, can be very misleading. If measurement problems are suspected or encountered, an alternate approach similar to that described should be considered. The alternate method is not only useful for burner balancing but also can be used to help in calibrating the plant excess O{sub 2} instruments and provide an on line means of cross-checking excess air measurements. Balanced burners operate closer to their design stoichiometry, providing better NO{sub x} reduction. For Salem Harbor Station, this means a significant saving in urea consumption.

  7. Analysis of Kuosheng Station Blackout Accident Using MELCOR 1.8.4

    SciTech Connect (OSTI)

    Wang, S.-J.; Chien, C.-S.; Wang, T.-C.; Chiang, K.-S

    2000-11-15

    The MELCOR code, developed by Sandia National Laboratories, is a fully integrated, relatively fast-running code that models the progression of severe accidents in commercial light water nuclear power plants (NPPs).A specific station blackout (SBO) accident for Kuosheng (BWR-6) NPP is simulated using the MELCOR 1.8.4 code. The MELCOR input deck for Kuosheng NPP is established based on Kuosheng NPP design data and the MELCOR users' guides. The initial steady-state conditions are generated with a developed self-initialization algorithm. The main severe accident phenomena and the fission product release fractions associated with the SBO accident were simulated. The predicted results are plausible and as expected in light of current understanding of severe accident phenomena. The uncertainty of this analysis is briefly discussed. The important features of the MELCOR 1.8.4 are described. The estimated results provide useful information for the probabilistic risk assessment (PRA) of Kuosheng NPP. This tool will be applied to the PRA, the severe accident analysis, and the severe accident management study of Kuosheng NPP in the near future.

  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. Validation of an Integrated Hydrogen Energy Station

    SciTech Connect (OSTI)

    Edward C. Heydorn

    2012-10-26

    This report presents the results of a 10-year project conducted by Air Products and Chemicals, Inc. (Air Products) to determine the feasibility of coproducing hydrogen with electricity. The primary objective was to demonstrate the technical and economic viability of a hydrogen energy station using a high-temperature fuel cell designed to produce power and hydrogen. This four-phase project had intermediate go/no-go decisions and the following specific goals: • Complete a technical assessment and economic analysis of the use of high-temperature fuel cells, including solid oxide and molten carbonate, for the co-production of power and hydrogen (energy park concept). • Build on the experience gained at the Las Vegas H2 Energy Station and compare/contrast the two approaches for co-production. • Determine the applicability of co-production from a high-temperature fuel cell for the existing merchant hydrogen market and for the emerging hydrogen economy. • Demonstrate the concept on natural gas for six months at a suitable site with demand for both hydrogen and electricity. • Maintain safety as the top priority in the system design and operation. • Obtain adequate operational data to provide the basis for future commercial activities, including hydrogen fueling stations. Work began with the execution of the cooperative agreement with DOE on 30 September 2001. During Phase 1, Air Products identified high-temperature fuel cells as having the potential to meet the coproduction targets, and the molten carbonate fuel cell system from FuelCell Energy, Inc. (FuelCell Energy) was selected by Air Products and DOE following the feasibility assessment performed during Phase 2. Detailed design, construction and shop validation testing of a system to produce 250 kW of electricity and 100 kilograms per day of hydrogen, along with site selection to include a renewable feedstock for the fuel cell, were completed in Phase 3. The system also completed six months of demonstration operation at the wastewater treatment facility operated by Orange County Sanitation District (OCSD, Fountain Valley, CA). As part of achieving the objective of operating on a renewable feedstock, Air Products secured additional funding via an award from the California Air Resources Board. The South Coast Air Quality Management District also provided cost share which supported the objectives of this project. System operation at OCSD confirmed the results from shop validation testing performed during Phase 3. Hydrogen was produced at rates and purity that met the targets from the system design basis, and coproduction efficiency exceeded the 50% target set in conjunction with input from the DOE. Hydrogen production economics, updated from the Phase 2 analysis, showed pricing of $5 to $6 per kilogram of hydrogen using current gas purification systems. Hydrogen costs under $3 per kilogram are achievable if next-generation electrochemical separation technologies become available.

  10. Applications of the RELAP5 code to the station blackout transients at the Browns Ferry Unit One Plant

    SciTech Connect (OSTI)

    Schultz, R.R.; Wagoner, S.R.

    1983-01-01

    As a part of the charter of the Severe Accident Sequence Analysis (SASA) Program, station blackout transients have been analyzed using a RELAP5 model of the Browns Ferry Unit 1 Plant. The task was conducted as a partial fulfillment of the needs of the US Nuclear Regulatory Commission in examining the Unresolved Safety Issue A-44: Station Blackout (1) the station blackout transients were examined (a) to define the equipment needed to maintain a well cooled core, (b) to determine when core uncovery would occur given equipment failure, and (c) to characterize the behavior of the vessel thermal-hydraulics during the station blackout transients (in part as the plant operator would see it). These items are discussed in the paper. Conclusions and observations specific to the station blackout are presented.

  11. Nuclear Physics

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

    Science Programs Office of Science Nuclear Physics science-innovationassetsimagesicon-science.jpg Nuclear Physics Enabling remarkable discoveries and tools that ...

  12. EERE Success Story-World's First Tri-Generation Fuel Cell and Hydrogen

    Office of Environmental Management (EM)

    Fueling Station | Department of Energy Tri-Generation Fuel Cell and Hydrogen Fueling Station EERE Success Story-World's First Tri-Generation Fuel Cell and Hydrogen Fueling Station April 18, 2013 - 12:00am Addthis EERE supported the development of the world's first tri-generation station-a combined heat and power system that produces hydrogen in addition to heat and electricity-in Fountain Valley. The system runs on natural gas and biogas generated by the Orange County Sanitation District's

  13. Tri-Generation Success Story: World's First Tri-Gen Energy Station—Fountain Valley

    Broader source: Energy.gov [DOE]

    This Fuel Cell Technologies Office fact sheet describes the Fountain Valley energy station. Supported in part by a $2.2 million grant from the Energy Department, the Fountain Valley energy station is the world’s first tri-generation hydrogen energy and electrical power station to provide transportation fuel to the public and electric power to an industrial facility.

  14. Overview of New Tools to Perform Safety Analysis: BWR Station Black Out Test Case

    SciTech Connect (OSTI)

    D. Mandelli; C. Smith; T. Riley; J. Nielsen; J. Schroeder; C. Rabiti; A. Alfonsi; Cogliati; R. Kinoshita; V. Pasucci; B. Wang; D. Maljovec

    2014-06-01

    Dynamic Probabilistic Risk Assessment (DPRA) methodologies couple system simulator codes (e.g., RELAP, MELCOR) with simulation controller codes (e.g., RAVEN, ADAPT). While system simulator codes accurately model system dynamics deterministically, simulation controller codes introduce both deterministic (e.g., system control logic, operating procedures) and stochastic (e.g., component failures, parameter uncertainties) elements into the simulation. Typically, a DPRA is performed by: 1) sampling values of a set of parameters from the uncertainty space of interest (using the simulation controller codes), and 2) simulating the system behavior for that specific set of parameter values (using the system simulator codes). For complex systems, one of the major challenges in using DPRA methodologies is to analyze the large amount of information (i.e., large number of scenarios ) generated, where clustering techniques are typically employed to allow users to better organize and interpret the data. In this paper, we focus on the analysis of a nuclear simulation dataset that is part of the Risk Informed Safety Margin Characterization (RISMC) Boiling Water Reactor (BWR) station blackout (SBO) case study. We apply a software tool that provides the domain experts with an interactive analysis and visualization environment for understanding the structures of such high-dimensional nuclear simulation datasets. Our tool encodes traditional and topology-based clustering techniques, where the latter partitions the data points into clusters based on their uniform gradient flow behavior. We demonstrate through our case study that both types of clustering techniques complement each other in bringing enhanced structural understanding of the data.

  15. Texas 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" "Comanche Peak Unit 1, Unit 2","2,406","20,208",48.9,"Luminant Generation Company LLC" "South Texas Project Unit 1, Unit 2","2,560","21,127",51.1,"STP Nuclear

  16. National Nuclear Security Administration United States Department of Energy

    National Nuclear Security Administration (NNSA)

    America Treaty Organization NCT Nuclear Counterterrorism NCTIR Nuclear Counterterrorism and Incident Response Program NDAA National Defense Authorization Act NELA Nuclear Explosive Like-Assembly NEST Nuclear Emergency Support Team NGSI Next Generation Safeguards Initiative NIS Nonproliferation and International Security Program NMF National Mission Force NNSA National Nuclear Security Administration NNSS Nevada Nuclear Security Site NPAC Nonproliferation Policy and Arms Control Program NPT

  17. Alternative Fuels Data Center: Alternative Fueling Station Locator

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    20,236 alternative fuel stations in the United States Excluding private stations Location details are subject to change. We recommend calling the stations to verify location, hours of operation, and access. About the data

  18. Nuclear Forensics

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

    Nuclear Forensics AMS is a Powerful Tool for Nuclear Forensics Nuclear forensics, which can be applied to both interdicted materials and debris from a nuclear explosion, is the application of laboratory analysis and interpretation to provide technical conclusions (provenance, design, etc.) about a nuclear device or interdicted nuclear material. Nuclear forensic analysts can build confidence in their conclusions by employing multiple signatures that collectively minimize the subset of possible

  19. Alternative Fueling Station Locator App Provides Info at Your Fingertips |

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

    Department of Energy Alternative Fueling Station Locator App Provides Info at Your Fingertips Alternative Fueling Station Locator App Provides Info at Your Fingertips November 15, 2013 - 10:12am Addthis The Alternative Fueling Station Locator iPhone app helps you find fueling stations that offer electricity, natural gas, biodiesel, E85, propane, or hydrogen. | Energy Department The Alternative Fueling Station Locator iPhone app helps you find fueling stations that offer electricity, natural

  20. Energy Jobs: Electric Vehicle Charging Station Installer | Department of

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

    Energy Electric Vehicle Charging Station Installer Energy Jobs: Electric Vehicle Charging Station Installer October 28, 2014 - 3:23pm Addthis As the demand for electric vehicles goes up, charging stations become more prevalent -- here an electric vehicle owner uses a local charging station. | Photo Courtesy of the Energy Department. As the demand for electric vehicles goes up, charging stations become more prevalent -- here an electric vehicle owner uses a local charging station. | Photo

  1. Alternative Fuels Data Center: Electric Vehicle Charging Station Locations

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Station Locations to someone by E-mail Share Alternative Fuels Data Center: Electric Vehicle Charging Station Locations on Facebook Tweet about Alternative Fuels Data Center: Electric Vehicle Charging Station Locations on Twitter Bookmark Alternative Fuels Data Center: Electric Vehicle Charging Station Locations on Google Bookmark Alternative Fuels Data Center: Electric Vehicle Charging Station Locations on Delicious Rank Alternative Fuels Data Center: Electric Vehicle Charging Station Locations

  2. Alternative Fuels Data Center: Electric Vehicle Charging Stations

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Stations to someone by E-mail Share Alternative Fuels Data Center: Electric Vehicle Charging Stations on Facebook Tweet about Alternative Fuels Data Center: Electric Vehicle Charging Stations on Twitter Bookmark Alternative Fuels Data Center: Electric Vehicle Charging Stations on Google Bookmark Alternative Fuels Data Center: Electric Vehicle Charging Stations on Delicious Rank Alternative Fuels Data Center: Electric Vehicle Charging Stations on Digg Find More places to share Alternative Fuels

  3. Alternative Fuels Data Center: Natural Gas Fueling Stations

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Natural Gas Fueling Stations to someone by E-mail Share Alternative Fuels Data Center: Natural Gas Fueling Stations on Facebook Tweet about Alternative Fuels Data Center: Natural Gas Fueling Stations on Twitter Bookmark Alternative Fuels Data Center: Natural Gas Fueling Stations on Google Bookmark Alternative Fuels Data Center: Natural Gas Fueling Stations on Delicious Rank Alternative Fuels Data Center: Natural Gas Fueling Stations on Digg Find More places to share Alternative Fuels Data

  4. Alternative Fuels Data Center: Biodiesel Fueling Station Locations

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Station Locations to someone by E-mail Share Alternative Fuels Data Center: Biodiesel Fueling Station Locations on Facebook Tweet about Alternative Fuels Data Center: Biodiesel Fueling Station Locations on Twitter Bookmark Alternative Fuels Data Center: Biodiesel Fueling Station Locations on Google Bookmark Alternative Fuels Data Center: Biodiesel Fueling Station Locations on Delicious Rank Alternative Fuels Data Center: Biodiesel Fueling Station Locations on Digg Find More places to share

  5. Alternative Fuels Data Center: EV Charging Stations Spread Through Philly

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    EV Charging Stations Spread Through Philly to someone by E-mail Share Alternative Fuels Data Center: EV Charging Stations Spread Through Philly on Facebook Tweet about Alternative Fuels Data Center: EV Charging Stations Spread Through Philly on Twitter Bookmark Alternative Fuels Data Center: EV Charging Stations Spread Through Philly on Google Bookmark Alternative Fuels Data Center: EV Charging Stations Spread Through Philly on Delicious Rank Alternative Fuels Data Center: EV Charging Stations

  6. Alternative Fuels Data Center: Ethanol Fueling Station Locations

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Station Locations to someone by E-mail Share Alternative Fuels Data Center: Ethanol Fueling Station Locations on Facebook Tweet about Alternative Fuels Data Center: Ethanol Fueling Station Locations on Twitter Bookmark Alternative Fuels Data Center: Ethanol Fueling Station Locations on Google Bookmark Alternative Fuels Data Center: Ethanol Fueling Station Locations on Delicious Rank Alternative Fuels Data Center: Ethanol Fueling Station Locations on Digg Find More places to share Alternative

  7. Alternative Fuels Data Center: Natural Gas Fueling Station Locations

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Station Locations to someone by E-mail Share Alternative Fuels Data Center: Natural Gas Fueling Station Locations on Facebook Tweet about Alternative Fuels Data Center: Natural Gas Fueling Station Locations on Twitter Bookmark Alternative Fuels Data Center: Natural Gas Fueling Station Locations on Google Bookmark Alternative Fuels Data Center: Natural Gas Fueling Station Locations on Delicious Rank Alternative Fuels Data Center: Natural Gas Fueling Station Locations on Digg Find More places to

  8. Alternative Fuels Data Center: Propane Fueling Station Locations

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Station Locations to someone by E-mail Share Alternative Fuels Data Center: Propane Fueling Station Locations on Facebook Tweet about Alternative Fuels Data Center: Propane Fueling Station Locations on Twitter Bookmark Alternative Fuels Data Center: Propane Fueling Station Locations on Google Bookmark Alternative Fuels Data Center: Propane Fueling Station Locations on Delicious Rank Alternative Fuels Data Center: Propane Fueling Station Locations on Digg Find More places to share Alternative

  9. Webinar: Reference Designs for Hydrogen Fueling Stations

    Broader source: Energy.gov [DOE]

    The Fuel Cell Technologies Office will present a live webinar titled "Reference Designs for Hydrogen Fueling Stations" on Tuesday, October 13, from 12 to 1 p.m. Eastern Daylight Time (EDT).

  10. Bendersville Station-Aspers, Pennsylvania: Energy Resources ...

    Open Energy Info (EERE)

    OpenEI by expanding it. Bendersville Station-Aspers is a census-designated place in Adams County, Pennsylvania.1 References US Census Bureau 2005 Place to 2006 CBSA...

  11. POST 10/Truck Inspection Station (Map 3

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

    POST 10/Truck Inspection Station (Map 3) Changes Effective January 11, 2010 Pajarito Corridor Deliveries: Drivers of commercial delivery trucks headed to the Pajarito Corridor (Pajarito Road bounded by NM Highway 4 and Diamond Drive) must stop at Post 10 for truck inspections. Drivers will then need to present time-stamped inspection passes from Post 10 to protective force offcers stationed at the Pajarito Corridor. (Drivers exiting Post 10 should (1) turn right and proceed west on the Truck

  12. Hydrogen Fueling Infrastructure Research and Station Technology

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

    Infrastructure Research and Station Technology Erika Sutherland U.S. Department of Energy Fuel Cell Technologies Office 2 Question and Answer * Please type your question into the question box hydrogenandfuelcells.energy.gov Hydrogen Fueling Infrastructure Research and Station Technology Chris Ainscough, Joe Pratt, Jennifer Kurtz, Brian Somerday, Danny Terlip, Terry Johnson November 18, 2014 Objective: Ensure that FCEV customers have a positive fueling experience relative to conventional

  13. Solar and Infrared Radiation Station (SIRS) Handbook

    SciTech Connect (OSTI)

    Stoffel, T

    2005-07-01

    The Solar Infrared Radiation Station (SIRS) provides continuous measurements of broadband shortwave (solar) and longwave (atmospheric or infrared) irradiances for downwelling and upwelling components. The following six irradiance measurements are collected from a network of stations to help determine the total radiative flux exchange within the Atmospheric Radiation Measurement (ARM) Southern Great Plains (SGP) Climate Research Facility: Direct normal shortwave (solar beam) Diffuse horizontal shortwave (sky) Global horizontal shortwave (total hemispheric) Upwelling shortwave (reflected) Downwelling longwave (atmospheric infrared) Upwelling longwave (surface infrared)

  14. Check Out the New Alternative Fuel Station Locator

    Broader source: Energy.gov [DOE]

    With more than 10,000 publicly accessible alternative fueling stations, the new Alternative Fuel Station Locator map makes fueling your alternative fuel vehicle easier than ever.

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

    Open Energy Info (EERE)

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

  16. Genesee Power Station Biomass Facility | Open Energy Information

    Open Energy Info (EERE)

    Biomass Facility Jump to: navigation, search Name Genesee Power Station Biomass Facility Facility Genesee Power Station Sector Biomass Owner CMSFortistar Location Flint, Michigan...

  17. Pdc - The Worldwide Leader in Hydrogen Refueling Station Compression...

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

    Pdc - The Worldwide Leader in Hydrogen Refueling Station Compression Pdc - The Worldwide Leader in Hydrogen Refueling Station Compression This presentation by Matther Weaver of Pdc...

  18. Experiences from Ethanol Buses and Fuel Station Report - La Spezia...

    Open Energy Info (EERE)

    Experiences from Ethanol Buses and Fuel Station Report - La Spezia Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Experiences from Ethanol Buses and Fuel Station Report...

  19. Fact #717: March 5, 2012 Availability of Electric Charging Stations...

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

    of Electric Charging Stations Has Increased Dramatically in Recent Years At the end of September 2009, there were just 465 electric vehicle charging stations nationwide....

  20. Fuel Station of the Future- Innovative Approach to Fuel Cell...

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

    Fuel Station of the Future- Innovative Approach to Fuel Cell Technology Unveiled in California Fuel Station of the Future- Innovative Approach to Fuel Cell Technology Unveiled in ...

  1. Puge County Gongdefang Hydropower Station Investment and Development...

    Open Energy Info (EERE)

    Puge County Gongdefang Hydropower Station Investment and Development Co Ltd Jump to: navigation, search Name: Puge County Gongdefang Hydropower Station Investment and Development...

  2. Jingning County Baihe II Station Hydropower Co Ltd | Open Energy...

    Open Energy Info (EERE)

    Baihe II Station Hydropower Co Ltd Jump to: navigation, search Name: Jingning County Baihe II Station Hydropower Co. Ltd. Place: Hangzhou, Zhejiang Province, China Zip: 310002...

  3. The Status of Renewable Hydrogen and Energy Station Technologies...

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

    The Status of Renewable Hydrogen and Energy Station Technologies and Policy Recommendations The Status of Renewable Hydrogen and Energy Station Technologies and Policy...

  4. Development Wells At Fallon Naval Air Station Area (Sabin, Et...

    Open Energy Info (EERE)

    Fallon Naval Air Station Area (Sabin, Et Al., 2010) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Development Wells At Fallon Naval Air Station...

  5. EUHYFIS Hydrogen Filling Station Consortium | Open Energy Information

    Open Energy Info (EERE)

    EUHYFIS Hydrogen Filling Station Consortium Jump to: navigation, search Name: EUHYFIS (Hydrogen Filling Station Consortium) Place: Oldenburg, Germany Zip: 26123 Sector: Hydro,...

  6. Trona Injection Tests: Mirant Potomac River Station, Unit 1,...

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

    Trona Injection Tests: Mirant Potomac River Station, Unit 1, November 12 to December 23, 2005, Summary Report Trona Injection Tests: Mirant Potomac River Station, Unit 1, November ...

  7. Carboli 2 Geothermal Power Station | Open Energy Information

    Open Energy Info (EERE)

    Station General Information Name Carboli 2 Geothermal Power Station Sector Geothermal energy Location Information Location Tuscany, Italy Geothermal Resource Area Larderello...

  8. Cornia 2 Geothermal Power Station | Open Energy Information

    Open Energy Info (EERE)

    Station General Information Name Cornia 2 Geothermal Power Station Sector Geothermal energy Location Information Location Tuscany, Italy Geothermal Resource Area Larderello...

  9. Valle Secolo Geothermal Power Station | Open Energy Information

    Open Energy Info (EERE)

    Station General Information Name Valle Secolo Geothermal Power Station Sector Geothermal energy Location Information Geothermal Resource Area Larderello Geothermal Area Geothermal...

  10. Carboli 1 Geothermal Power Station | Open Energy Information

    Open Energy Info (EERE)

    Station General Information Name Carboli 1 Geothermal Power Station Sector Geothermal energy Location Information Location Tuscany, Italy Geothermal Resource Area Larderello...

  11. Bagnore 3 Geothermal Power Station | Open Energy Information

    Open Energy Info (EERE)

    Station General Information Name Bagnore 3 Geothermal Power Station Sector Geothermal energy Location Information Location Tuscany, Italy Geothermal Resource Area Mount Amiata...

  12. MHK Technologies/Jiangxia Tidal Power Station | Open Energy Informatio...

    Open Energy Info (EERE)

    Jiangxia Tidal Power Station < MHK Technologies Jump to: navigation, search << Return to the MHK database homepage Jiangxia Tidal Power Station.jpg Technology Profile Primary...

  13. Selva 1 Geothermal Power Station | Open Energy Information

    Open Energy Info (EERE)

    Station General Information Name Selva 1 Geothermal Power Station Sector Geothermal energy Location Information Location Tuscany, Italy Geothermal Resource Area Larderello...

  14. Le Prata Geothermal Power Station | Open Energy Information

    Open Energy Info (EERE)

    Station General Information Name Le Prata Geothermal Power Station Sector Geothermal energy Location Information Location Tuscany, Italy Geothermal Resource Area Larderello...

  15. La Leccia Geothermal Power Station | Open Energy Information

    Open Energy Info (EERE)

    Station General Information Name La Leccia Geothermal Power Station Sector Geothermal energy Location Information Location Tuscany, Italy Geothermal Resource Area Larderello...

  16. Nuova Lago Geothermal Power Station | Open Energy Information

    Open Energy Info (EERE)

    Station General Information Name Nuova Lago Geothermal Power Station Sector Geothermal energy Location Information Location Tuscany, Italy Geothermal Resource Area Larderello...

  17. Penrose Power Station Biomass Facility | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search Name Penrose Power Station Biomass Facility Facility Penrose Power Station Sector Biomass Facility Type Landfill Gas Location Los Angeles County,...

  18. Toyon Power Station Biomass Facility | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search Name Toyon Power Station Biomass Facility Facility Toyon Power Station Sector Biomass Facility Type Landfill Gas Location Los Angeles County,...

  19. EA-1996: Glass Buttes Radio Station, Lake County, Oregon | Department...

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

    6: Glass Buttes Radio Station, Lake County, Oregon EA-1996: Glass Buttes Radio Station, Lake County, Oregon SUMMARY The Bureau of Land Management (BLM), with DOE's Bonneville Power...

  20. Scram signal generator

    DOE Patents [OSTI]

    Johanson, Edward W. (New Lenox, IL); Simms, Richard (Westmont, IL)

    1981-01-01

    A scram signal generating circuit for nuclear reactor installations monitors a flow signal representing the flow rate of the liquid sodium coolant which is circulated through the reactor, and initiates reactor shutdown for a rapid variation in the flow signal, indicative of fuel motion. The scram signal generating circuit includes a long-term drift compensation circuit which processes the flow signal and generates an output signal representing the flow rate of the coolant. The output signal remains substantially unchanged for small variations in the flow signal, attributable to long term drift in the flow rate, but a rapid change in the flow signal, indicative of a fast flow variation, causes a corresponding change in the output signal. A comparator circuit compares the output signal with a reference signal, representing a given percentage of the steady state flow rate of the coolant, and generates a scram signal to initiate reactor shutdown when the output signal equals the reference signal.

  1. DOE - NNSA/NFO -- News & Views NRDS Nuclear Rocket

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

    Nuclear Rocket Development Station Tested Nuclear Rocket for Mars Mission Photo - NERVA reactor experimental engine In the mid-1950s, the United States initiated a nuclear rocket program called "Project Rover." The Nevada Test Site (NTS) was selected to test nuclear reactors and engines, and perform various ground tests. The tests, performed in the southwest corner of NTS (Area 25), ended in 1972. The Atomic Energy Commission (AEC) and the National Aeronautics and Space Administration

  2. EIS-0215: Pinon Pine Power Project, Tracy Station, NV

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy (DOE) prepared this statement to assess the environmental and human health issues associated with the Pinon Pine Power Project, a proposed demonstration project that would be cost-shared by DOE and the Sierra Pacific Power Company (SPPCo.) under DOE's Clean Coal Technology Program. The proposed Federal action is for DOE to provide cost-shared funding support for the construction and operation of the Pinon Pine Power Project, a coal-fired power generating facility, which would be a nominal, 800-ton-per-day (104 megawatt (MW) gross generation) air-blown, Integrated Gasification Combined-Cycle plant proposed by SPPCo. at its Tracy Power Station near Reno, Nevada.

  3. Ridge station eases Florida's waste-disposal problems

    SciTech Connect (OSTI)

    Swanekamp, R.

    1994-10-01

    Two results of Florida's continuing population growth are (1) a critical need for electricity, and (2) a solid-waste disposal crisis. During a recent winter cold snap, electric demand in one service territory surged 25% over generating capacity and 10% over net system capability. Rolling blackouts ensued. At the same time, Florida's fragile wetlands environment is suffering from years of unfettered development. Groundwater sources are contaminated, landfill space is scarce, and illegal tire dumps blight the landscape. The recently constructed Ridge generating station in Polk County, Fla. is addressing both the state's electrical and environmental needs. Ridge, which entered commercial operation in May, burns a unique mix of urban woodwaste and scrap tires to provide 45 MW of critically needed electricity while keeping large quantities of solid waste out of landfills. When pipeline construction at an adjacent landfill is completed, the facility also will burn the methane gases produced when garbage decomposes.

  4. Tampa Electric Company`s Polk Power Station IGCC project

    SciTech Connect (OSTI)

    Jenkins, S.D.

    1995-12-31

    Tampa Electric Company (TEC) is in the construction phase of its new Polk Power Station Unit No. 1. This unique project incorporates the use of Integrated Gasification Combined Cycle (IGCC) technology for electric power production. The project is being partially funded by the US Department of Energy (DOE), as part of the Clean Coal Technology Program. This will help to demonstrate this state-of-the-art technology, providing utilities with the ability to use a wide range of coals in an efficient, environmentally superior manner. During the summer of 1994, TEC began site development at the new Polk Power Station. Since that time, most of the Site work has been completed, and erection and installation of the power plant equipment is well underway. This is the first time that IGCC technology will be installed at a new unit at a greenfield site. This is a major endeavor for TEC in that Polk Unit No. 1 is a major addition to the existing generating capacity and it involves the demonstration of technology new to utility power generation. As a part of the Cooperative Agreement with the DOE, TEC will also be demonstrating the use of a new Hot Gas Clean-Up System which has a potential for greater IGCC efficiency.

  5. Generation Planning (pbl/generation)

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

    Generation Hydro Power Wind Power Monthly GSP BPA White Book Dry Year Tools Firstgov Generation Planning Thumbnail image of BPA White Book BPA White Book (1998-2014) Draft Dry...

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

    National Nuclear Security Administration (NNSA)

    This Site Budget IG Web Policy Privacy No Fear Act Accessibility FOIA Sitemap Federal Government The White House DOE.gov USA.gov Jobs Apply for Our Jobs Our Jobs Working at NNSA...

  7. nuclear security

    National Nuclear Security Administration (NNSA)

    3%2A en Shaping the future of nuclear detection http:nnsa.energy.govblogshaping-future-nuclear-detection

    Learning techniques to combat nuclear trafficking, touring the...

  8. Generic implications of ATWS events at the Salem Nuclear Power Plant. Licensee and staff actions

    SciTech Connect (OSTI)

    Not Available

    1983-08-01

    This report, Volume 2 of two volumes of NUREG-1000, describes the intermediate term actions to be taken by licensees and applicants of the US Nuclear Regulatory Commission (NRC), on the one hand, and by NRC staff, on the other, to address the generic issues raised by two anticipated transients without scram (ATWS) at the Salem Nuclear Generating Station, Unit 1, on February 22 and 25, 1983. These actions came about as a result of the findings of NUREG-1000, Volume 1, and of reviews by the NRC Committee to Review Generic Requirements, the NRC Program Offices, and the Commission. The actions to be taken by licensees and applicants have been detailed in a letter pursuant to 10 CFR 50.54(f).

  9. Solar Radiation Monitoring Station (SoRMS): Humboldt State University, Arcata, California (Data)

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Wilcox, S.; Andreas, A.

    A partnership with HSU and U.S. Department of Energy's National Renewable Energy Laboratory (NREL) to collect solar data to support future solar power generation in the United States. The measurement station monitors global horizontal, direct normal, and diffuse horizontal irradiance to define the amount of solar energy that hits this particular location.

  10. Solar Radiation Monitoring Station (SoRMS): Humboldt State University, Arcata, California (Data)

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Wilcox, S.; Andreas, A.

    2007-05-02

    A partnership with HSU and U.S. Department of Energy's National Renewable Energy Laboratory (NREL) to collect solar data to support future solar power generation in the United States. The measurement station monitors global horizontal, direct normal, and diffuse horizontal irradiance to define the amount of solar energy that hits this particular location.

  11. Nuclear Power in Space

    DOE R&D Accomplishments [OSTI]

    1994-01-01

    In the early years of the United States space program, lightweight batteries, fuel cells, and solar modules provided electric power for space missions. As missions became more ambitious and complex, power needs increased and scientists investigated various options to meet these challenging power requirements. One of the options was nuclear energy. By the mid-1950s, research had begun in earnest on ways to use nuclear power in space. These efforts resulted in the first radioisotope thermoelectric generators (RTGs), which are nuclear power generators build specifically for space and special terrestrial uses. These RTGs convert the heat generated from the natural decay of their radioactive fuel into electricity. RTGs have powered many spacecraft used for exploring the outer planets of the solar system and orbiting the sun and Earth. They have also landed on Mars and the moon. They provide the power that enables us to see and learn about even the farthermost objects in our solar system.

  12. Nuclear Science

    Energy Savers [EERE]

    and Engineering Education Sourcebook 2013 American Nuclear Society US Department of Energy Nuclear Science & Engineering Education Sourcebook 2013 North American Edition American Nuclear Society Education, Training, and Workforce Division US Department of Energy Office of Nuclear Energy Editor and Founder John Gilligan Professor of Nuclear Engineering North Carolina State University Version 5.13 Welcome to the 2013 Edition of the Nuclear Science and Engineering Education (NS&EE)

  13. Nuclear reactor characteristics and operational history

    Gasoline and Diesel Fuel Update (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 Generation, Table 2. Ownership Data Table 3. Nuclear Reactor Characteristics and Operational History PDF XLS Plant Name Generator ID Type Reactor Supplier and Model Construction Start Grid Connection Original Expiration Date License Renewal Application License Renewal Issued Extended Expiration Arkansas Nuclear One 1

  14. Nuclear Reactor Technologies | Department of Energy

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

    Reactor Technologies Nuclear Reactor Technologies TVA Watts Bar Nuclear Power Plant | Photo courtesy of Tennessee Valley Authority TVA Watts Bar Nuclear Power Plant | Photo courtesy of Tennessee Valley Authority Nuclear power has reliably and economically contributed almost 20% of electrical generation in the United States over the past two decades. It remains the single largest contributor (more than 70%) of non-greenhouse-gas-emitting electric power generation in the United States. Small

  15. nuclear enterprise

    National Nuclear Security Administration (NNSA)

    Outlines Accomplishments in Stockpile Stewardship, Nuclear Nonproliferation, Naval Reactors and Managing the Nuclear Enterprise

    The...

  16. Nuclear Energy

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

    Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel Cycle Defense Waste Management ...

  17. SCDAP severe core-damage studies: BWR ATWS and PWR station blackout

    SciTech Connect (OSTI)

    Laats, E.T.; Chambers, R.; Driskell, W.E.

    1983-01-01

    The Severe Accident Sequence Analysis (SASA) Program, sponsored by the US Nuclear Regulatory Commission (NRC), is addressing a number of accident scenarios that potentially pose a health hazard to the public. Two of the scenarios being analyzed in detail at the Idaho National Engineering Laboratory (INEL) are the station blackout at the Bellefonte nuclear plant and the anticipated transient without scram (ATWS) at the Browns Ferry-1 plant. The INEL analyses of the station blackout and ATWS have been divided into four parts, which represent the sequence being followed in this study. First, the evaluation of long term irradiation effects prior to the station blackout or ATWS was conducted using the FRAPCON-2 fuel rod behavior code; second, the reactor primary and secondary coolant system behavior is being analyzed with the RELAP5 code; third, the degradation of the core is being analyzed with the SCDAP code; and finally, the containment building response is being analyzed with the CONTEMPT code. This paper addresses only the SCDAP/MODO degraded core analyses for both the station blackout and ATWS scenarios.

  18. 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

  19. 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

  20. Tennessee Nuclear Profile - Power Plants

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

    Tennessee 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" "Sequoyah Unit 1, Unit 2","2,278","18,001",64.9,"Tennessee Valley Authority" "Watts Bar Nuclear Plant Unit 1","1,123","9,738",35.1,"Tennessee Valley

  1. 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

  2. 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

  3. 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

  4. Distributed Generation

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

    Untapped Value of Backup Generation While new guidelines and regulations such as IEEE (Institute of Electrical and Electronics Engineers) 1547 have come a long way in addressing interconnection standards for distributed generation, utilities have largely overlooked the untapped potential of these resources. Under certain conditions, these units (primarily backup generators) represent a significant source of power that can deliver utility services at lower costs than traditional centralized

  5. Hydrogen Fueling - Coming Soon to a Station Near You (Brochure)

    SciTech Connect (OSTI)

    Not Available

    2009-04-01

    Fact sheet providing information useful to local permitting officials facing hydrogen fueling station proposals.

  6. MELCOR calculations for a low-pressure short-term station blackout in a BWR-6

    SciTech Connect (OSTI)

    Carbajo, J.J. [Martin Marietta Energy Systems, Oak Ridge, TN (United States)

    1995-12-31

    A postulated, low-pressure, short term station blackout severe accident has been analyzed using the MELCOR code for the Grand Gulf nuclear power plant. Different versions have been used with three different models of the plant. This paper presents results of the effects of different plant models and versions of MELCOR on the calculated results and to present the best-estimating timing of events for this transient.

  7. Well-to-wheels Analysis of Energy Use and Greenhouse Gas Emissions of Hydrogen Produced with Nuclear Energy

    SciTech Connect (OSTI)

    Wu, Ye; Wang, Michael Q.; Vyas, Anant D.; Wade, David C.; Taiwo, Temitope A.

    2004-07-01

    A fuel-cycle model-called the Greenhouse gases, Regulated Emissions, and Energy use in Transportation (GREET) model-has been developed at Argonne National Laboratory to evaluate well-to-wheels (WTW) energy and emission impacts of motor vehicle technologies fueled with various transportation fuels. The GREET model contains various hydrogen (H{sub 2}) production pathways for fuel-cell vehicles (FCVs) applications. In this effort, the GREET model was expanded to include four nuclear H{sub 2} production pathways: (1) H{sub 2} production at refueling stations via electrolysis using Light Water Reactor (LWR)-generated electricity; (2) H{sub 2} production in central plants via thermo-chemical water cracking using steam from High Temperature Gas cooled Reactor (HTGR); (3) H{sub 2} production in central plants via high-temperature electrolysis using HTGR-generated electricity and steam; and (4) H{sub 2} production at refueling stations via electrolysis using HTGR-generated electricity The WTW analysis of these four options include these stages: uranium ore mining and milling; uranium ore transportation; uranium conversion; uranium enrichment; uranium fuel fabrication; uranium fuel transportation; electricity or H{sub 2} production in nuclear power plants; H{sub 2} transportation; H{sub 2} compression; and H{sub 2} FCVs operation. Due to large differences in electricity requirements for uranium fuel enrichment between gas diffusion and centrifuge technologies, two scenarios were designed for uranium enrichment: (1) 55% of fuel enriched through gaseous diffusion technology and 45% through centrifuge technology (the current technology split for U.S. civilian nuclear power plants); and (2) 100% fuel enrichment using the centrifuge technology (a future trend). Our well-to-pump (WTP) results show that significant reductions in fossil energy use and greenhouse gas (GHG) emissions are achieved by nuclear-based H{sub 2} compared to natural gas-based H{sub 2} production via steam methane reforming for a unit of H{sub 2} delivered at refueling stations. In particular, 73-98% of GHG emissions and 81- 99% of fossil energy use are reduced by nuclear-based H{sub 2} relative to natural gas-based H{sub 2}, depending on the uranium enrichment technology and type of nuclear reactor used. When H{sub 2} is applied to FCVs, the WTW results also show large benefit in reducing fossil energy use and GHG emissions. (authors)

  8. Case Study: Mobile Photovoltaic System at Bechler Meadows Ranger Station, Yellowstone National Park (Brochure), Federal Energy Management Program (FEMP)

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

    Mobile Photovoltaic System at Bechler Meadows Ranger Station, Yellowstone National Park Introduction This report describes the performance of a mobile photovoltaic (PV) system installed in 2011 to provide power to Bechler Ranger Station in Yellowstone National Park, Wyo. This small, remote outpost is not served by the electric utility grid and previously relied on a propane generator as the only source of power. Mobile Photovoltaic Systems Mobile solar systems consist of photovoltaic (PV)

  9. November 10, 2004: First hydrogen refueling station opens in Washington,

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

    DC. | Department of Energy 0, 2004: First hydrogen refueling station opens in Washington, DC. November 10, 2004: First hydrogen refueling station opens in Washington, DC. November 10, 2004: First hydrogen refueling station opens in Washington, DC. November 10, 2004 Secretary Abraham joins representatives of Shell and General Motors in the opening of the nation's first integrated gasoline/hydrogen refueling station in Washington, D.C. The station will be used to refuel General Motors' fuel

  10. NREL: Technology Deployment - Mobile App Puts Alternative Fueling Station

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

    Locations in the Palm of Your Hand Mobile App Puts Alternative Fueling Station Locations in the Palm of Your Hand News NREL Developed Mobile App for Alternative Fueling Station Locations Released Energy Department Launches Alternative Fueling Station Locator App Using the Enhanced Alternative Fueling Station Locator Alternative Fueling Stations Database Sponsors U.S. Department of Energy Related Stories Remote Shading Tool Has Potential to Reduce Solar Soft Costs by 17 Cents/Watt Contact

  11. Alternative Fuels Data Center: Alternative Fueling Station Counts by State

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Locate Stations Printable Version Share this resource Send a link to Alternative Fuels Data Center: Alternative Fueling Station Counts by State to someone by E-mail Share Alternative Fuels Data Center: Alternative Fueling Station Counts by State on Facebook Tweet about Alternative Fuels Data Center: Alternative Fueling Station Counts by State on Twitter Bookmark Alternative Fuels Data Center: Alternative Fueling Station Counts by State on Google Bookmark Alternative Fuels Data Center:

  12. Alternative Fuels Data Center: About the Alternative Fueling Station Data

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Locate Stations Printable Version Share this resource Send a link to Alternative Fuels Data Center: About the Alternative Fueling Station Data to someone by E-mail Share Alternative Fuels Data Center: About the Alternative Fueling Station Data on Facebook Tweet about Alternative Fuels Data Center: About the Alternative Fueling Station Data on Twitter Bookmark Alternative Fuels Data Center: About the Alternative Fueling Station Data on Google Bookmark Alternative Fuels Data Center: About the

  13. Alternative Fuels Data Center: Green Fueling Station Powers Fleets in

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Upstate New York Green Fueling Station Powers Fleets in Upstate New York to someone by E-mail Share Alternative Fuels Data Center: Green Fueling Station Powers Fleets in Upstate New York on Facebook Tweet about Alternative Fuels Data Center: Green Fueling Station Powers Fleets in Upstate New York on Twitter Bookmark Alternative Fuels Data Center: Green Fueling Station Powers Fleets in Upstate New York on Google Bookmark Alternative Fuels Data Center: Green Fueling Station Powers Fleets in

  14. Alternative Fuels Data Center: Hydrogen Fueling Station Locations

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Hydrogen Printable Version Share this resource Send a link to Alternative Fuels Data Center: Hydrogen Fueling Station Locations to someone by E-mail Share Alternative Fuels Data Center: Hydrogen Fueling Station Locations on Facebook Tweet about Alternative Fuels Data Center: Hydrogen Fueling Station Locations on Twitter Bookmark Alternative Fuels Data Center: Hydrogen Fueling Station Locations on Google Bookmark Alternative Fuels Data Center: Hydrogen Fueling Station Locations on Delicious Rank

  15. Pump station for radioactive waste water

    DOE Patents [OSTI]

    Whitton, John P.; Klos, Dean M.; Carrara, Danny T.; Minno, John J.

    2003-11-18

    A pump station for transferring radioactive particle containing waste water, includes: (a.) an enclosed sump having a vertically elongated right frusto conical wall surface and a bottom surface and (b.) a submersible volute centrifugal pump having a horizontally rotating impeller and a volute exterior surface. The sump interior surface, the bottom surface and the volute exterior surface are made of stainless steel having a 30 Ra or finer surface finish. A 15 Ra finish has been found to be most cost effective. The pump station is used for transferring waste water, without accumulation of radioactive fines.

  16. Technological advancements in NGV station design

    SciTech Connect (OSTI)

    Ledbetter, G.S.; Grimmer, J.E.; Ketcham, E.T.

    1995-12-31

    Hurricane Compressors` SPRINT System (patent pending) is designed to increase the rate of flow from compressed natural gas (CNG) fuel stations and provide greater utilization of stored CNG than is available from traditional compressor stations. Using a novel method of adapting compressor operation to changes in CNG storage system pressures, this advanced technology provides an alternative mechanism for fuel delivery when demand for fuel is high. Transfer of CNG may be made at higher rates of flow than would be possible either from a pressure depleted storage system or directly from the compressor.

  17. GET TO KNOW National Nuclear Science Week

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

    GET TO KNOW National Nuclear Science Week January 23 - 27, 2012 www.nwinitiative.org Did You Know Nuclear Medicine heals many Americans. 18 million nuclear medicine procedures are performed each year among 305 million people in the United States. We depend on nuclear for electric power. 20 percent of our nation's electricity is generated from 104 operating reactors across the United States. Nearly half of South Carolina's electricity and one-fourth of Georgia's electric power come from nuclear

  18. Advanced Nuclear Reactors | Department of Energy

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

    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

  19. 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 to FY2013 Click on the icons to find out the values of the awards given to each school. The darker the icon, the more recent the award. Drag and zoom map to see more recipients. Investing in the next generation of nuclear energy leaders and advancing university-led nuclear innovation is vital to fulfilling the Office of Nuclear Energy's (NE) mission. This is accomplished primarily through NE's Nuclear Energy

  20. Vallecitos Nuclear Center, California, Site Fact Sheet

    Office of Legacy Management (LM)

    08/03/2015 Page 1 of 1 This fact sheet provides information about the Vallecitos Nuclear Center, California, Site. The U.S. Department of Energy Office of Legacy Management is responsible for maintaining records for the government-sponsored research conducted at this facility. Location of the Vallecitos Nuclear Center, California, Site Site Description and History The Vallecitos Nuclear Center (VNC) is a 1,600 acre nuclear research facility and the site of a former electricity generating nuclear

  1. Office of Nuclear Energy | Department of Energy

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

    Office of Nuclear Energy Small Modular Reactors Small Modular Reactors The Small Modular Reactor program advances the licensing and commercialization of this next-generation technology in the United States. Read more Middle School STEM Curriculum Middle School STEM Curriculum The Harnessed Atom curriculum offers essential principles and fundamental concepts on energy and nuclear science. Read more Educating Future Nuclear Engineers Educating Future Nuclear Engineers The Nuclear Energy University

  2. Exploratory Nuclear Reactor Safety Analysis and Visualization...

    Office of Scientific and Technical Information (OSTI)

    algorithms and codes for both design and safety analysis. In particular, the new generation of system analysis ... We model a large-scale nuclear simulation dataset as a ...

  3. LANL, Sandia, Cray Set to Build Next Generation NNSA Supercomputer |

    National Nuclear Security Administration (NNSA)

    National Nuclear Security Administration LANL, Sandia, Cray Set to Build Next Generation NNSA Supercomputer | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact

  4. Presented at the Second International Meeting on Next Generation Safeguards

    National Nuclear Security Administration (NNSA)

    | National Nuclear Security Administration Second International Meeting on Next Generation Safeguards | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets

  5. Argonne nuclear pioneer: Leonard Koch

    SciTech Connect (OSTI)

    Koch, Leonard

    2012-01-01

    Leonard Koch joined Argonne National Laboratory in 1948. He helped design and build Experimental Breeder Reactor-1 (EBR-1), the first reactor to generate useable amounts of electricity from nuclear energy.

  6. 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.

  7. Technical Design Report, Second Target Station

    SciTech Connect (OSTI)

    Galambos, John D.; Anderson, David E.; Bechtol, D.; Bethea, Katie L.; Brown, N.; Carden, W. F.; Chae, Steven M.; Clark, A.; Counce, Deborah M.; Craft, K.; Crofford, Mark T.; Collins, Richard M.; Cousineau, Sarah M.; Curry, Douglas E.; Cutler, Roy I.; Dayton, Michael J.; Dean, Robert A.; Deibele, Craig E.; Doleans, Marc; Dye, T.; Eason, Bob H.; Eckroth, James A.; Fincrock, C.; Fritts, S.; Gallmeier, Franz X.; Gawne, Ken R.; Hartman, Steven M.; Herwig, Kenneth W.; Hess, S.; Holmes, Jeffrey A.; Horak, Charlie M.; Howell, Matthew P.; Iverson, Erik B.; Jacobs, Lorelei L.; Jones, Larry C.; Johnson, B.; Johnson, S.; Kasemir, Kay; Kim, Sang-Ho; Laughon, Gregory J.; Lu, W.; Mahoney, Kelly L.; Mammosser, John; McManamy, T.; Michilini, M.; Middendorf, Mark E.; O'Neal, Ed; Nemec, B.; Peters, Roy Cecil; Plum, Michael A.; Reagan, G.; Remec, Igor; Rennich, Mark J.; Riemer, Bernie; Saethre, Robert B.; Schubert, James Phillip; Shishlo, Andrei P.; Smith, C. Craig; Strong, William Herb; Tallant, Kathie M.; Tennant, David Alan; Thibadeau, Barbara M.; Trumble, S.; Trotter, Steven M.; Wang, Z.; Webb, Steven B.; Williams, Derrick C.; White, Karen S.; Zhao, Jinkui

    2015-01-01

    The Second Target Station (STS) is a proposed upgrade for SNS. It includes a doubling of the accelerator power and an additional instrument hall. The new instrument hall will receive a 467 kW 10 Hz beam. The parameters and preliminary design aspects of the STS are presented for the accelerator, target systems, instrument hall, instruments and civil construction aspects.

  8. 14th Annual international meeting of wind turbine test stations: Proceedings

    SciTech Connect (OSTI)

    Not Available

    1994-11-01

    These proceedings are of the 14th Annual International Meeting of Test Stations. As the original charter states these meetings are intended to be an international forum for sharing wind turbine testing experiences. By sharing their experiences they can improve testing skills and techniques. As with all new industries the quality of the products is marked by how well they learn from their experiences and incorporate this learning into the next generation of products. The test station`s role in this process is to provide accurate information to the companies they serve. This information is used by designers to conform and improve their designs. It is also used by certification agencies for confirming the quality of these designs. By sharing of experiences they are able to accomplished these goals, serve these customers better and ultimately improve the international wind energy industry.

  9. Exelôn. Generation

    Office of Environmental Management (EM)

    Exelôn. Generation 4300 Winfield Road Warrenville, Illinois 60555 Writer's Direct Dial: 630/657-3753 Writer's Direct Fax: 630/657-4323 Tamra.Domever@exeloncorp corn March 21, 2011 Memorandum Memorializing Ex Parte Communication To: expartecommunications@hg.doe.gov (sent via email) On March 14, 2011, representatives of Exelon Generation Company, LLC and Exelon Nuclear Partners (referred to collectively as "Exelon") met with staff of the U.S. Department of Energy to discuss Exelon's

  10. Hydrogen Station Cost Estimates: Comparing Hydrogen Station Cost Calculator Results with other Recent Estimates

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

    Hydrogen Station Cost Estimates Comparing Hydrogen Station Cost Calculator Results with other Recent Estimates M. Melaina and M. Penev National Renewable Energy Laboratory Technical Report NREL/TP-5400-56412 September 2013 NREL is a national laboratory of the U.S. Department of Energy Office of Energy Efficiency & Renewable Energy Operated by the Alliance for Sustainable Energy, LLC This report is available at no cost from the National Renewable Energy Laboratory (NREL) at

  11. 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

  12. EIA - State Nuclear Profiles

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

    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

  13. Nuclear Structure Revealed by High-Precision Mass Measurements

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

    Revealed by High-Precision Mass Measurements at SHIPTRAP / GSI Michael Block GSI Darmstadt Helmholtzinstitut Mainz Institut für Kernchemie Johannes Gutenberg Universität Mainz SHE Symposium 2015 - College Station M. Bender et al., Phys. Lett. B 515 (2001) 42 Nuclear Shells: Magic Numbers in SHE? M. Bender et al., Phys. Lett. B 515 (2001) 42 Nuclear Shells: Magic Numbers in SHE? high-precision mass measurements provide * accurate absolute binding energies to map nuclear shell effects * anchor

  14. Microwave generator

    DOE Patents [OSTI]

    Kwan, T.J.T.; Snell, C.M.

    1987-03-31

    A microwave generator is provided for generating microwaves substantially from virtual cathode oscillation. Electrons are emitted from a cathode and accelerated to an anode which is spaced apart from the cathode. The anode has an annular slit there through effective to form the virtual cathode. The anode is at least one range thickness relative to electrons reflecting from the virtual cathode. A magnet is provided to produce an optimum magnetic field having the field strength effective to form an annular beam from the emitted electrons in substantial alignment with the annular anode slit. The magnetic field, however, does permit the reflected electrons to axially diverge from the annular beam. The reflected electrons are absorbed by the anode in returning to the real cathode, such that substantially no reflexing electrons occur. The resulting microwaves are produced with a single dominant mode and are substantially monochromatic relative to conventional virtual cathode microwave generators. 6 figs.

  15. Nuclear Navy

    SciTech Connect (OSTI)

    1994-12-31

    This video tells the story of the Navy`s development of nuclear power and its application in long-range submarines and the growing nuclear surface force. Narrated by Frank Blair.

  16. Nuclear Energy!

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

    more about Nuclear Energy When: Saturday, October 19 | 1:00 p.m. - 3:00 p.m. Where: Aiken ... an IndyCar driver, see the Nuclear Clean Air Energy race car and receive a special ...

  17. Preliminary Thermal Modeling of HI-Storm 100S-218 Version B Storage Modules at Hope Creek Cuclear Power Station ISFSI

    SciTech Connect (OSTI)

    Cuta, Judith M.; Adkins, Harold E.

    2013-08-30

    As part of the Used Fuel Disposition Campaign of the U. S. Department of Energy, Office of Nuclear Energy (DOE-NE) Fuel Cycle Research and Development, a consortium of national laboratories and industry is performing visual inspections and temperature measurements of selected storage modules at various locations around the United States. This report documents thermal analyses in in support of the inspections at the Hope Creek Nuclear Generating Station ISFSI. This site utilizes the HI-STORM100 vertical storage system developed by Holtec International. This is a vertical storage module design, and the thermal models are being developed using COBRA-SFS (Michener, et al., 1987), a code developed by PNNL for thermal-hydraulic analyses of multi assembly spent fuel storage and transportation systems. This report describes the COBRA-SFS model in detail, and presents pre-inspection predictions of component temperatures and temperature distributions. The final report will include evaluation of inspection results, and if required, additional post-test calculations, with appropriate discussion of results.

  18. Tomorrow's Nuclear Reactors are Closer Than You Think | Department of

    Energy Savers [EERE]

    Energy Tomorrow's Nuclear Reactors are Closer Than You Think Tomorrow's Nuclear Reactors are Closer Than You Think March 1, 2016 - 1:00pm Addthis Dr. Rachel Slaybaugh is among the new generation of scientists seeking to revolutionize nuclear energy. She is an assistant professor of nuclear engineering at the University of California-Berkeley. | Photo courtesy of UC Berkeley. Dr. Rachel Slaybaugh is among the new generation of scientists seeking to revolutionize nuclear energy. She is an

  19. Radioactive Waste Issues in Major Nuclear Incidents | Department of Energy

    Energy Savers [EERE]

    Radioactive Waste Issues in Major Nuclear Incidents Radioactive Waste Issues in Major Nuclear Incidents S.Y. Chen*, Illinois Institute of Technology Abstract: Large amounts of radioactive waste had been generated in major nuclear accidents such as the Chernobyl nuclear accident in Ukraine of 1986 and the recent Fukushima nuclear accident in Japan of 2011. The wastes were generated due to the accidental releases of radioactive materials that resulted in widespread contamination throughout the

  20. RELAP5/MOD3 simulation of the station blackout experiment conducted at the IIST facility

    SciTech Connect (OSTI)

    Ferng, Y.M.; Liu, T.J.; Lee, C.H. [Inst. of Nuclear Energy Research, Lung-Tan (Taiwan, Province of China)

    1996-10-01

    Thermal-hydraulic responses in the station blackout experiment conducted at the IIST facility are simulated through the use of the advanced system code RELAP5/MOD3. Typical behaviors occurring in the IIST station blackout transient are characterized by secondary boiloff, primary saturation and pressurization, and subsequent core uncovery and heatup. As the coolant inventory within the steam generator secondary system boils dry, the primary system pressure increases as a result of degradation of the heat removal ability of the steam generator secondary side. This pressurization phenomenon causes the pressurizer safety valve to open and the primary coolant to deplete through the valve, causing the core to eventually become uncovered. The same response can be exactly simulated by the current model. The current calculated results show fairly good agreement with the experimental data, but the timing of the events occurring in the station blackout transient is calculated earlier than the measured value. The overall comparison of key parameters between the calculated results and IIST test data, however, reveals that the current RELAP5/MOD3 model can provide reasonable station blackout modeling for simulating long-term system behavior.

  1. Help Design the Hydrogen Fueling Station of Tomorrow | Department...

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

    Help Design the Hydrogen Fueling Station of Tomorrow Help Design the Hydrogen Fueling Station of Tomorrow January 9, 2014 - 2:20pm Addthis University students can join the...

  2. Help Design the Hydrogen Fueling Station of Tomorrow | Department...

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

    Help Design the Hydrogen Fueling Station of Tomorrow Help Design the Hydrogen Fueling Station of Tomorrow January 10, 2014 - 12:00am Addthis The Energy Department posted a blog...

  3. H2FIRST Reference Station Design Task: Project Deliverable 2...

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

    Reference Station Design Task: Project Deliverable 2-2 H2FIRST Reference Station Design Task: Project Deliverable 2-2 This H2FIRST project report, published in April 2015, presents ...

  4. Fact #816: February 10, 2014 Natural Gas Refueling Stations Grow...

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

    6: February 10, 2014 Natural Gas Refueling Stations Grow Over the Last Ten Years Fact 816: February 10, 2014 Natural Gas Refueling Stations Grow Over the Last Ten Years In 2003...

  5. Regional Consumer Hydrogen Demand and Optimal Hydrogen Refueling Station Siting

    SciTech Connect (OSTI)

    Melendez, M.; Milbrandt, A.

    2008-04-01

    Using a GIS approach to spatially analyze key attributes affecting hydrogen market transformation, this study proposes hypothetical hydrogen refueling station locations in select subregions to demonstrate a method for determining station locations based on geographic criteria.

  6. Webinar May 12: Overview of Station Analysis Tools Developed...

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

    economics and incorporates a station's capital and operating cost based on key design variables such as station capacity and mode of hydrogen delivery. To complement HRSAM, H2FAST...

  7. Rocky Mountain Research Station and LANL build

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

    tech tool predicts fire behavior in bark beetle-ravaged forests August 9, 2012 Rocky Mountain Research Station and LANL build better computer models LOS ALAMOS, N. M. and FORT COLLINS, CO., August 9, 2012-Fire fighters facing fast-moving wildfires need better tools to predict erratic fire behavior, especially in forests with dead trees caused by massive outbreaks of bark beetles whose predations create an abundance of dead fuel and changes in the tree canopy structure. Tools typically available

  8. AMF Deployment, McMurdo Station, Antarctica

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

    Antarctica McMurdo Deployment AMF Home McMurdo Home Experiment Planning Abstract and Related Campaigns Science Plan AWARE Website Deployment Operations Baseline Instruments and Data Plots at the Archive Weather & Climate Support for the AWARE Project Outreach News & Press AWARE Log of Events Backgrounder (PDF, 1.5MB) Poster (JPEG, 1.3MB) Images Contacts Paul Ortega, AMF Operations Hanna Goss, Media Contact Dan Lubin, Principal Investigator AMF Deployment, McMurdo Station, Antarctica

  9. Regression analysis of technical parameters affecting nuclear power plant performances

    SciTech Connect (OSTI)

    Ghazy, R.; Ricotti, M. E.; Trueco, P.

    2012-07-01

    Since the 80's many studies have been conducted in order to explicate good and bad performances of commercial nuclear power plants (NPPs), but yet no defined correlation has been found out to be totally representative of plant operational experience. In early works, data availability and the number of operating power stations were both limited; therefore, results showed that specific technical characteristics of NPPs were supposed to be the main causal factors for successful plant operation. Although these aspects keep on assuming a significant role, later studies and observations showed that other factors concerning management and organization of the plant could instead be predominant comparing utilities operational and economic results. Utility quality, in a word, can be used to summarize all the managerial and operational aspects that seem to be effective in determining plant performance. In this paper operational data of a consistent sample of commercial nuclear power stations, out of the total 433 operating NPPs, are analyzed, mainly focusing on the last decade operational experience. The sample consists of PWR and BWR technology, operated by utilities located in different countries, including U.S. (Japan)) (France)) (Germany)) and Finland. Multivariate regression is performed using Unit Capability Factor (UCF) as the dependent variable; this factor reflects indeed the effectiveness of plant programs and practices in maximizing the available electrical generation and consequently provides an overall indication of how well plants are operated and maintained. Aspects that may not be real causal factors but which can have a consistent impact on the UCF, as technology design, supplier, size and age, are included in the analysis as independent variables. (authors)

  10. explicit representation of uncertainty in solar generation

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

    solar generation - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel Cycle Defense Waste Management Programs Advanced Nuclear

  11. explicit representation of uncertainty in wind generation

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

    wind generation - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel Cycle Defense Waste Management Programs Advanced Nuclear

  12. Electricity production levelized costs for nuclear, gas and coal

    Office of Scientific and Technical Information (OSTI)

    Levelized costs for nuclear, gas and coal for Electricity, under the Mexican scenario. Javier C. Palacios, Gustavo Alonso, Ramón Ramírez, Armando Gómez, Javier Ortiz, Luis C. Longoria. Instituto Nacional de Investigaciones Nucleares México palacios@nuclear.inin.mx, galonso@nuclear.inin.mx . ABSTRACT In the case of new nuclear power stations, it is necessary to pay special attention to the financial strategy that will be applied, time of construction, investment cost, and the discount and

  13. SOARCA Peach Bottom Atomic Power Station Long-Term Station Blackout Uncertainty Analysis: Convergence of the Uncertainty Results

    SciTech Connect (OSTI)

    Bixler, Nathan E.; Osborn, Douglas M.; Sallaberry, Cedric Jean-Marie; Eckert-Gallup, Aubrey Celia; Mattie, Patrick D.; Ghosh, S. Tina

    2014-02-01

    This paper describes the convergence of MELCOR Accident Consequence Code System, Version 2 (MACCS2) probabilistic results of offsite consequences for the uncertainty analysis of the State-of-the-Art Reactor Consequence Analyses (SOARCA) unmitigated long-term station blackout scenario at the Peach Bottom Atomic Power Station. The consequence metrics evaluated are individual latent-cancer fatality (LCF) risk and individual early fatality risk. Consequence results are presented as conditional risk (i.e., assuming the accident occurs, risk per event) to individuals of the public as a result of the accident. In order to verify convergence for this uncertainty analysis, as recommended by the Nuclear Regulatory Commissions Advisory Committee on Reactor Safeguards, a high source term from the original population of Monte Carlo runs has been selected to be used for: (1) a study of the distribution of consequence results stemming solely from epistemic uncertainty in the MACCS2 parameters (i.e., separating the effect from the source term uncertainty), and (2) a comparison between Simple Random Sampling (SRS) and Latin Hypercube Sampling (LHS) in order to validate the original results obtained with LHS. Three replicates (each using a different random seed) of size 1,000 each using LHS and another set of three replicates of size 1,000 using SRS are analyzed. The results show that the LCF risk results are well converged with either LHS or SRS sampling. The early fatality risk results are less well converged at radial distances beyond 2 miles, and this is expected due to the sparse data (predominance of zero results).

  14. Kraftwerk Union KWU Siemens Power Generation | Open Energy Information

    Open Energy Info (EERE)

    Services Product: KWU is a provider of components and services to the commercial nuclear utility industry. References: Kraftwerk Union (KWU) - Siemens Power Generation.1...

  15. Seismic margin review of the Maine Yankee Atomic Power Station: Fragility analysis

    SciTech Connect (OSTI)

    Ravindra, M. K.; Hardy, G. S.; Hashimoto, P. S.; Griffin, M. J.

    1987-03-01

    This Fragility Analysis is the third of three volumes for the Seismic Margin Review of the Maine Yankee Atomic Power Station. Volume 1 is the Summary Report of the first trial seismic margin review. Volume 2, Systems Analysis, documents the results of the systems screening for the review. The three volumes are part of the Seismic Margins Program initiated in 1984 by the Nuclear Regulatory Commission (NRC) to quantify seismic margins at nuclear power plants. The overall objectives of the trial review are to assess the seismic margins of a particular pressurized water reactor, and to test the adequacy of this review approach, quantification techniques, and guidelines for performing the review. Results from the trial review will be used to revise the seismic margin methodology and guidelines so that the NRC and industry can readily apply them to assess the inherent quantitative seismic capacity of nuclear power plants.

  16. List of Refueling Stations Incentives | Open Energy Information

    Open Energy Info (EERE)

    Renewable Fuel Vehicles Other Alternative Fuel Vehicles Refueling Stations Ethanol Methanol Biodiesel No Alternative Vehicle Conversion Credits - Corporate (Louisiana) Corporate...

  17. Washington DC's First Electric Vehicle Charging Station | Department of

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

    Energy DC's First Electric Vehicle Charging Station Washington DC's First Electric Vehicle Charging Station November 17, 2010 - 11:28am Addthis Street signage for Washington, DC's first electric vehicle charging station located on the northwest corner of the intersection of U and 14th streets. | Department of Energy Photo | Street signage for Washington, DC's first electric vehicle charging station located on the northwest corner of the intersection of U and 14th streets. | Department of

  18. Hydrogen Fueling Station in Honolulu, Hawaii Feasibility Analysis |

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

    Department of Energy Fueling Station in Honolulu, Hawaii Feasibility Analysis Hydrogen Fueling Station in Honolulu, Hawaii Feasibility Analysis This feasibility report assesses the technical and economic feasibility of developing a vacant, undeveloped General Services Administration-owned property into an income-producing site equipped with a hydrogen fueling station and a covered 175-stall parking structure with roof-top solar panels. According to the analysis, the proposed station will

  19. Nuova Molinetto Geothermal Power Station | Open Energy Information

    Open Energy Info (EERE)

    General Information Name Nuova Molinetto Geothermal Power Station Sector Geothermal energy Location Information Location Tuscany, Italy Geothermal Resource Area Larderello...

  20. Monteverdi 1 Geothermal Power Station | Open Energy Information

    Open Energy Info (EERE)

    General Information Name Monteverdi 1 Geothermal Power Station Sector Geothermal energy Location Information Location Tuscany, Italy Geothermal Resource Area Larderello...