National Library of Energy BETA

Sample records for units nuclear plant

  1. ATWS analysis for Browns Ferry Nuclear Plant Unit 1

    SciTech Connect (OSTI)

    Dallman, R.J.; Jouse, W.C.

    1985-01-01

    Analyses of postulated Anticipated Transients Without Scram (ATWS) were performed at the Idaho National Engineering Laboratory (INEL). The Browns Ferry Nuclear Plant Unit 1 (BFNP1) was selected as the subject of this work because of the cooperation of the Tennessee Valley Authority (TVA). The work is part of the Severe Accident Sequence Analysis (SASA) Program of the US Nuclear Regulatory Commission (NRC). A Main Steamline Isolation Valve (MSIV) closure served as the transient initiator for these analyses, which proceeded a complete failure to scram. Results from the analyses indicate that operator mitigative actions are required to prevent overpressurization of the primary containment. Uncertainties remain concerning the effectiveness of key mitigative actions. The effectiveness of level control as a power reduction procedure is limited. Power level resulting from level control only reduce the Pressure Suppression Pool (PSP) heatup rate from 6 to 4F/min.

  2. Contribution of Anticipated Transients Without Scram (ATWS) to core melt at United States nuclear power plants

    SciTech Connect (OSTI)

    Giachetti, R.T. (Giachetti (Richard T.), Ann Arbor, MI (USA))

    1989-09-01

    This report looks at WASH-1400 and several other Probabilistic Risk Assessments (PRAs) and Probabilistic Safety Studies (PSSs) to determine the contribution of Anticipated Transients Without Scram (ATWS) events to the total core melt probability at eight nuclear power plants in the United States. After considering each plant individually, the results are compared from plant to plant to see if any generic conclusions regarding ATWS, or core melt in general, can be made. 8 refs., 34 tabs.

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

    SciTech Connect (OSTI)

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

    1991-01-01

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

  4. BWR ATWS simulations for Browns Ferry Nuclear Plant Unit 1

    SciTech Connect (OSTI)

    Dallman, R.J.

    1984-01-01

    Under auspices of the US Nuclear Regulatory Commission, simulations of anticipated transients without scram (ATWS) in a boiling water reactor are being performed. A methodology has been developed to study the ATWS, and deterministic analyses have been conducted. Results are presented for one of the most probable (albeit hypothetical) sequences leading to core and containment damage. Areas presenting calculational uncertainties are identified, and requirements for their resolution are proposed.

  5. Volume I, Summary Report: A Roadmap to Deploy New Nuclear Power Plants in the United States by 2010:

    Office of Energy Efficiency and Renewable Energy (EERE)

    Nuclear power plants in the United States currently produce about 20 percent of the nation’s electricity. This nuclear-generated electricity is safe, clean and economical, and does not emit...

  6. Wisconsin Nuclear Profile - Point Beach Nuclear Plant

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

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

  7. Arizona Nuclear Profile - Power Plants

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

    (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Palo Verde Unit 1, Unit 2, Unit 3","3,937","31,200",100.0,"Arizona Public Service Co" "1 Plant 3 ...

  8. EIS No. 20100312 EIS Comanche Peak Nuclear Power Plant Units 3 and 4

    SciTech Connect (OSTI)

    Bjornstad, David J

    2010-08-01

    In accordance with Section 309(a) of the Clean Air Act, EPA is required to make its comments on EISs issued by other Federal agencies public. Historically, EPA has met this mandate by publishing weekly notices of availability of EPA comments, which includes a brief summary of EPA's comment letters, in the Federal Register. Since February 2008, EPA has been including its comment letters on EISs on its Web site at: http://www.epa.gov/compliance/nepa/eisdata.html. Including the entire EIS comment letters on the Web site satisfies the Section 309(a) requirement to make EPA's comments on EISs available to the public. Accordingly, on March 31, 2010, EPA discontinued the publication of the notice of availability of EPA comments in the Federal Register. EIS No. 20100312, Draft EIS, NRC, TX, Comanche Peak Nuclear Power Plant Units 3 and 4, Application for Combined Licenses (COLs) for Construction Permits and Operating Licenses, (NUREG-1943), Hood and Somervell Counties, TX, Comment Period Ends: 10/26/2010.

  9. Kansas Nuclear Profile - Power Plants

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

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

  10. Vermont Nuclear Profile - Power Plants

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

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

  11. 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

  12. Severe Accident Sequence Analysis Program: Anticipated transient without scram simulations for Browns Ferry Nuclear Plant Unit 1

    SciTech Connect (OSTI)

    Dallman, R J; Gottula, R C; Holcomb, E E; Jouse, W C; Wagoner, S R; Wheatley, P D

    1987-05-01

    An analysis of five anticipated transients without scram (ATWS) was conducted at the Idaho National Engineering Laboratory (INEL). The five detailed deterministic simulations of postulated ATWS sequences were initiated from a main steamline isolation valve (MSIV) closure. The subject of the analysis was the Browns Ferry Nuclear Plant Unit 1, a boiling water reactor (BWR) of the BWR/4 product line with a Mark I containment. The simulations yielded insights to the possible consequences resulting from a MSIV closure ATWS. An evaluation of the effects of plant safety systems and operator actions on accident progression and mitigation is presented.

  13. Risk-based inspection guide for Crystal River Unit 3 Nuclear Power Plant

    SciTech Connect (OSTI)

    Smith, B.W.; Dukelow, J.S.; Vo, T.V.; Harris, M.S.; Gore, B.F.; Hunt, S.T. )

    1991-06-01

    The Level 1 probabilistic risk assessment (PRA) for Crystal River Unit 3 (CR-3) has been analyzed to identify plant systems and components important to minimizing public risk, as measured by system contributions to plant core damage frequency, and to identify the primary failure modes for these components. The report presents a series of tables, organized by system and prioritized by risk importance, which identify components associated with 98% of the inspectable risk due to plant operation. The systems addressed, in descending order to risk importance are: Low Pressure Injection, AC Power, Service Water, Demineralized Water, High Pressure Injection, DC Power, Emergency Feedwater, Reactor Coolant Pressure Control, and Power Conversion. This ranking is based on the Fussell-Vesely measure of risk importance, i.e., the fraction of the total core damage frequency which involves failures of the system of interest. 3 refs., 9 figs., 13 tabs.

  14. 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

  15. 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

  16. 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

  17. 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

  18. 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

  19. Georgia Nuclear Profile - Power Plants

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

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

  20. Alabama Nuclear Profile - Power Plants

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

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

  1. Washington Nuclear Profile - Power Plants

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

    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

  2. Mississippi Nuclear Profile - Power Plants

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

    mwh)","Share of State nuclear net generation (percent)","Owner" "Grand Gulf Unit 1","1,251","9,643",100.0,"System Energy Resources, Inc" "1 Plant 1 Reactor","1,251","9,643",100.0

  3. Massachusetts Nuclear Profile - Power Plants

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

    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 independent ...

  4. Iowa Nuclear Profile - Power Plants

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

    of State nuclear net generation (percent)","Owner" "Duane Arnold Energy Center Unit 1",601,"4,451",100.0,"NextEra Energy Duane Arnold LLC" "1 Plant 1 Reactor",601,"4,451",100.0

  5. 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

  6. 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

  7. Ohio Nuclear Profile - Power Plants

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

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

  8. Arizona Nuclear Profile - Power Plants

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

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

  9. 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

  10. Michigan Nuclear Profile - Power Plants

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

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

  11. Owners of nuclear power plants

    SciTech Connect (OSTI)

    Hudson, C.R.; White, V.S.

    1996-11-01

    Commercial nuclear power plants in this country can be owned by a number of separate entities, each with varying ownership proportions. Each of these owners may, in turn, have a parent/subsidiary relationship to other companies. In addition, the operator of the plant may be a different entity as well. This report provides a compilation on the owners/operators for all commercial power reactors in the United States. While the utility industry is currently experiencing changes in organizational structure which may affect nuclear plant ownership, the data in this report is current as of July 1996. The report is divided into sections representing different aspects of nuclear plant ownership.

  12. Owners of Nuclear Power Plants

    SciTech Connect (OSTI)

    Reid, R.L.

    2000-01-12

    Commercial nuclear power plants in this country can be owned by a number of separate entities, each with varying ownership proportions. Each of these owners may, in turn, have a parent/subsidiary relationship to other companies. In addition, the operator of the plant may be a different entity as well. This report provides a compilation on the owners/operators for all commercial power reactors in the United States. While the utility industry is currently experiencing changes in organizational structure which may affect nuclear plant ownership, the data in this report is current as of November 1999. The report is divided into sections representing different aspects of nuclear plant ownership.

  13. Nebraska Nuclear Profile - Power Plants

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

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

  14. Louisiana Nuclear Profile - Power Plants

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

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

  15. Minnesota Nuclear Profile - Power Plants

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

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

  16. Florida Nuclear Profile - Power Plants

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

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

  17. 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

  18. Energy Praises the Nuclear Regulatory Commission Approval of the First United States Nuclear Plant Site in Over 30 Years

    Broader source: Energy.gov [DOE]

    WASHINGTON, DC - The U.S. Department of Energy (DOE) today commended the Nuclear Regulatory Commission's decision to approve the first-ever Early Site Permit (ESP) for the Exelon Generation Company...

  19. Iowa Nuclear Profile - Power Plants

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

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

  20. Mississippi Nuclear Profile - Power Plants

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

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

  1. Missouri Nuclear Profile - Power Plants

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

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

  2. Safety evaluation report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391): Supplement No. 19

    SciTech Connect (OSTI)

    1995-11-01

    Supplement No. 19 to the Safety Evaluation Report for the application filed by the Tennessee Valley Authority for license to operate Watts Bar Nuclear Plant, Units 1 and 2, Docket Nos. 50-390 and 50-391, located in Rhea County Tennessee, has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. The purpose of this supplement is to update the Safety Evaluation with (1) additional information submitted by the applicant since Supplement No. 18 was issued, and (2) matters that the staff had under review when Supplement No. 18 was issued.

  3. Safety Evaluation Report related to the operation of Watts Bar Nuclear Plant, Units 1 and 2 (Docket Nos. 50-390 and 50-391). Supplement No. 12

    SciTech Connect (OSTI)

    Tam, P.S.

    1993-10-01

    Supplement No. 12 to the Safety Evaluation Report for the application filed by the Tennessee Valley Authority for license to operate Watts Bar Nuclear Plant, Units 1 and 2, Docket Nos. 50-390 and 50-391, located in Rhea County, Tennessee, has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. The purpose of this supplement is to update the Safety Evaluation of (1) additional information submitted by the applicant since Supplement No. 11 was issued, and (2) matters that the staff had under review when Supplement No. 11 was issued.

  4. Common cause failure analysis of the rodded scram system of the Arkansas Nuclear One-Unit 1 Plant

    SciTech Connect (OSTI)

    Montague, D.F.; Campbell, D.J.; Flanagan, G.F.

    1986-10-01

    This study demonstrates the use of a formal method for common cause failure analysis in a reliability analysis of the Arkansas Nuclear One - Unit 1 rodded scram system. The scram system failure of interest is loss of capability of the system to shut the reactor down when required. The results of this analysis support the ATWS program sponsored by the US Nuclear Regulatory Commission. The methods used in this analysis support the NRC's Risk Methods Integration and Evaluation Program (RMIEP).

  5. Vermont Nuclear Profile - Power Plants

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

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

  6. Connecticut Nuclear Profile - Power Plants

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

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

  7. Georgia Nuclear Profile - Power Plants

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

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

  8. Ohio Nuclear Profile - Power Plants

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

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

  9. Virginia Nuclear Profile - Power Plants

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

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

  10. Minnesota Nuclear Profile - Power Plants

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

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

  11. Alabama Nuclear Profile - Power Plants

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

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

  12. Wisconsin Nuclear Profile - Power Plants

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

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

  13. Texas Nuclear Profile - Power Plants

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

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

  14. Tennessee Nuclear Profile - Power Plants

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

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

  15. Illinois Nuclear Profile - Power Plants

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

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

  16. Michigan Nuclear Profile - Power Plants

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

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

  17. Nebraska Nuclear Profile - Power Plants

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

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

  18. Florida Nuclear Profile - Power Plants

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

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

  19. Maryland Nuclear Profile - Power Plants

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

    "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net generation (percent)","Owner" "Calvert Cliffs Nuclear Power Plant ...

  20. Assessment of RELAP5/MOD2 code using loss of offsite power transient data of KNU (Korea Nuclear Unit) No. 1 Plant

    SciTech Connect (OSTI)

    Chung, Bud-Dong; Kim, Hho-Jung . Korea Nuclear Safety Center); Lee, Young-Jin )

    1990-04-01

    This report presents a code assessment study based on a real plant transient that occurred on June 9, 1981 at the KNU {number sign}1 (Korea Nuclear Unit Number 1). KNU {number sign}1 is a two-loop Westinghouse PWR plant of 587 Mwe. The loss of offsite power transient occurred at the 77.5% reactor power with 0.5%/hr power ramp. The real plant data were collected from available on-line plant records and computer diagnostics. The transient was simulated by RELAP5/MOD2/36.05 and the results were compared with the plant data to assess the code weaknesses and strengths. Some nodalization studies were performed to contribute to developing a guideline for PWR nodalization for the transient analysis. 5 refs., 18 figs., 3 tabs.

  1. NUCLEAR POWER PLANT

    DOE Patents [OSTI]

    Carter, J.C.; Armstrong, R.H.; Janicke, M.J.

    1963-05-14

    A nuclear power plant for use in an airless environment or other environment in which cooling is difficult is described. The power plant includes a boiling mercury reactor, a mercury--vapor turbine in direct cycle therewith, and a radiator for condensing mercury vapor. (AEC)

  2. Design-Basis Flood Estimation for Site Characterization at Nuclear Power Plants in the United States of America

    SciTech Connect (OSTI)

    Prasad, Rajiv; Hibler, Lyle F.; Coleman, Andre M.; Ward, Duane L.

    2011-11-01

    The purpose of this document is to describe approaches and methods for estimation of the design-basis flood at nuclear power plant sites. Chapter 1 defines the design-basis flood and lists the U.S. Nuclear Regulatory Commission's (NRC) regulations that require estimation of the design-basis flood. For comparison, the design-basis flood estimation methods used by other Federal agencies are also described. A brief discussion of the recommendations of the International Atomic Energy Agency for estimation of the design-basis floods in its member States is also included.

  3. Virginia Nuclear Profile - Power Plants

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

    nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal ... Electric & Power Co" "2 Plants 4 Reactors","3,501","26,572",100.0 "Note: ...

  4. Shutdown and low-power operation at commercial nuclear power plants in the United States. Final report

    SciTech Connect (OSTI)

    Not Available

    1993-09-01

    The report contains the results of the NRC Staff`s evaluation of shutdown and low-power operations at US commercial nuclear power plants. The report describes studies conducted by the staff in the following areas: Operating experience related to shutdown and low-power operations, probabilistic risk assessment of shutdown and low-power conditions and utility programs for planning and conducting activities during periods the plant is shut down. The report also documents evaluations of a number of technical issues regarding shutdown and low-power operations performed by the staff, including the principal findings and conclusions. Potential new regulatory requirements are discussed, as well as potential changes in NRC programs. A draft report was issued for comment in February 1992. This report is the final version and includes the responses to the comments along with the staff regulatory analysis of potential new requirements.

  5. Tennessee Nuclear Profile - Watts Bar Nuclear Plant

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

    Watts Bar Nuclear Plant" "Unit","Summer capacity (mw)","Net generation (thousand mwh)","Summer capacity factor (percent)","Type","Commercial operation date","License expiration date" 1,"1,123","9,738",99.0,"PWR","application/vnd.ms-excel","application/vnd.ms-excel" ,"1,123","9,738",99.0 "Data for 2010" "PWR = Pressurized Light Water

  6. New York Nuclear Profile - Power Plants

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

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

  7. 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

  8. Washington Nuclear Profile - Power Plants

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

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

  9. California Nuclear Profile - Power Plants

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

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

  10. Pennsylvania Nuclear Profile - Power Plants

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

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

  11. Louisiana Nuclear Profile - Power Plants

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

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

  12. Joint US/Russian study on the development of a decommissioning strategy plan for RBMK-1000 unit No. 1 at the Leningrad Nuclear Power Plant

    SciTech Connect (OSTI)

    1997-12-01

    The objective of this joint U.S./Russian study was to develop a safe, technically feasible, economically acceptable strategy for decommissioning Leningrad Nuclear Power Plant (LNPP) Unit No. 1 as a representative first-generation RBMK-1000 reactor. The ultimate goal in developing the decommissioning strategy was to select the most suitable decommissioning alternative and end state, taking into account the socioeconomic conditions, the regulatory environment, and decommissioning experience in Russia. This study was performed by a group of Russian and American experts led by Kurchatov Institute for the Russian efforts and by the Pacific Northwest National Laboratory for the U.S. efforts and for the overall project.

  13. 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..."8,291",62.4,"NextEra Energy Point Beach LLC" "2 Plants 3 Reactors","1,584","13,281",100.0

  14. North Carolina Nuclear Profile - Power Plants

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

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

  15. South Carolina Nuclear Profile - Power Plants

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

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

  16. A Roadmap to Deploy New Nuclear Power Plants in the United States by 2010: Volume II, Main Report

    Office of Energy Efficiency and Renewable Energy (EERE)

    The objective of this document is to provide the Department of Energy (DOE) and the nuclear industry with the basis for a plan to ensure the availability of near-term nuclear energy options that...

  17. NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; 05 NUCLEAR FUELS...

    Office of Scientific and Technical Information (OSTI)

    Title list of documents made publicly available, January 1-31, 1998 NONE 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; 05 NUCLEAR FUELS; BIBLIOGRAPHIES; NUCLEAR POWER PLANTS;...

  18. United States and Italy Sign Nuclear Energy Agreements | Department of

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

    Energy Italy Sign Nuclear Energy Agreements United States and Italy Sign Nuclear Energy Agreements September 30, 2009 - 1:23pm Addthis U.S. Secretary of Energy Steven Chu and Italian Minister for Economic Development Claudio Scajola today signed two important nuclear energy agreements that may lead to construction of new nuclear power plants and improved cooperation on advanced nuclear energy systems and fuel cycle technologies in both countries. The U.S.-Italy Joint Declaration Concerning

  19. Owners of nuclear power plants

    SciTech Connect (OSTI)

    Not Available

    1982-11-01

    The list indicates percentage ownership of commercial nuclear power plants by utility companies as of September 1, 1982. The list includes all plants licensed to operate, under construction, docketed for NRC safety and environmental reviews, or under NRC antitrust review. Part I lists plants alphabetically with their associated applicants and percentage ownership. Part II lists applicants alphabetically with their associated plants and percentage ownership. Part I also indicates which plants have received operating licenses.

  20. Secretary Chu Visits Vogtle Nuclear Power Plant | Department of Energy

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

    Vogtle Nuclear Power Plant Secretary Chu Visits Vogtle Nuclear Power Plant February 15, 2012 - 3:54pm Addthis Secretary Chu traveled to Waynesboro, Georgia, to visit the Vogtle nuclear power plant, the site of what will be the first new nuclear reactors to be built in the United States in three decades. | Image credit: Southern Company. Secretary Chu traveled to Waynesboro, Georgia, to visit the Vogtle nuclear power plant, the site of what will be the first new nuclear reactors to be built in

  1. 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

  2. Owners of nuclear power plants

    SciTech Connect (OSTI)

    Wood, R.S.

    1991-07-01

    This report indicates percentage ownership of commercial nuclear power plants by utility companies. The report includes all plants operating, under construction, docketed for NRC safety and environmental reviews, or under NRC antitrust review, but does not include those plants announced but not yet under review or those plants formally cancelled. Part 1 of the report lists plants alphabetically with their associated applicants or licensees and percentage ownership. Part 2 lists applicants or licensees alphabetically with their associated plants and percentage ownership. Part 1 also indicates which plants have received operating licenses (OLS).

  3. Naval Nuclear Propulsion Plants | National Nuclear Security Administra...

    National Nuclear Security Administration (NNSA)

    Naval Nuclear Propulsion Plants In naval nuclear propulsion plants, fissioning of uranium atoms in the reactor core produces heat. Because the fission process also produces...

  4. United States Department of Energy`s reactor core protection evaluation methodology for fires at RBMK and VVER nuclear power plants. Revision 1

    SciTech Connect (OSTI)

    1997-06-01

    This document provides operators of Soviet-designed RBMK (graphite moderated light water boiling water reactor) and VVER (pressurized light water reactor) nuclear power plants with a systematic Methodology to qualitatively evaluate plant response to fires and to identify remedies to protect the reactor core from fire-initiated damage.

  5. The United Kingdom Nuclear Science Forum

    SciTech Connect (OSTI)

    MacMahon, Desmond; Judge, Steven; Forrest, Robin

    2005-05-24

    The United Kingdom Nuclear Science Forum effectively acts as the United Kingdom's Nuclear Data Committee. As such it is the interface between the UK nuclear data community and international nuclear data centres. This paper outlines the Forum's terms of reference and describes some of its recent activities.

  6. New Jersey Nuclear Profile - Power Plants

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

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

  7. New York Nuclear Profile - Power Plants

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

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

  8. North Carolina Nuclear Profile - Power Plants

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

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

  9. New Hampshire Nuclear Profile - Power Plants

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

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

  10. Missouri Nuclear Profile - Power Plants

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

    "Callaway Unit 1","1,190","8,996",100.0,"Union Electric Co" "1 Plant 1 Reactor","1,190","8,996",100.0 "Note: Totals may not equal sum of components due to ...

  11. Preliminary development of an integrated approach to the evaluation of pressurized thermal shock as applied to the Oconee Unit 1 Nuclear Power Plant

    SciTech Connect (OSTI)

    Burns, T J; Cheverton, R D; Flanagan, G F; White, J D; Ball, D G; Lamonica, L B; Olson, R

    1986-05-01

    An evaluation of the risk to the Oconee-1 nuclear plant due to pressurized thermal shock (PTS) has been Completed by Oak Ridge National Laboratory (ORNL). This evaluaion was part of a Nuclear Regulatory Commission (NRC) program designed to study the PTS risk to three nuclear plants: Oconee-1, a Babcock and Wilco reactor plant owned and operated by Duke Power Company; Calvert Cliffs-1, a Combustion Engineering reactor plant owned and operated by Baltimore Gas and Electric company; and H.B. Robinson-2, a Westinghouse reactor plant owned and operated by Carolina Power and Light Company. Studies of Calvert Cliffs-1 and H.B. Robinson-2 are still underway. The specific objectives of the Oconee-1 study were to: (1) provide a best estimate of the probability of a through-the-wall crack (TWC) occurring in the reactor pressure vessel as a result of PTS; (2) determine dominant accident sequences, plant features, operator and control actions and uncertainty in the PTS risk; and (3) evaluate effectiveness of potential corrective measures.

  12. Dynamic Simulation Nuclear Power Plants

    Energy Science and Technology Software Center (OSTI)

    1992-03-03

    DSNP (Dynamic Simulator for Nuclear Power-Plants) is a system of programs and data files by which a nuclear power plant, or part thereof, can be simulated. The acronym DSNP is used interchangeably for the DSNP language, the DSNP libraries, the DSNP precompiler, and the DSNP document generator. The DSNP language is a special-purpose, block-oriented, digital-simulation language developed to facilitate the preparation of dynamic simulations of a large variety of nuclear power plants. It is amore » user-oriented language that permits the user to prepare simulation programs directly from power plant block diagrams and flow charts by recognizing the symbolic DSNP statements for the appropriate physical components and listing these statements in a logical sequence according to the flow of physical properties in the simulated power plant. Physical components of nuclear power plants are represented by functional blocks, or modules. Many of the more complex components are represented by several modules. The nuclear reactor, for example, has a kinetic module, a power distribution module, a feedback module, a thermodynamic module, a hydraulic module, and a radioactive heat decay module. These modules are stored in DSNP libraries in the form of a DSNP subroutine or function, a block of statements, a macro, or a combination of the above. Basic functional blocks such as integrators, pipes, function generators, connectors, and many auxiliary functions representing properties of materials used in nuclear power plants are also available. The DSNP precompiler analyzes the DSNP simulation program, performs the appropriate translations, inserts the requested modules from the library, links these modules together, searches necessary data files, and produces a simulation program in FORTRAN.« less

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

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

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

  14. Maryland Nuclear Profile - Calvert Cliffs Nuclear Power Plant

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

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

  15. National Nuclear Security Administration United States Department...

    National Nuclear Security Administration (NNSA)

    United States Department of Energy Washington, DC 20585 Prevent, Counter, and Respond-A ... Department of EnergyNational Nuclear Security Administration | March 2016 Prevent, ...

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

    National Nuclear Security Administration (NNSA)

    Security Administration | (NNSA) United States-Japan Nuclear Security Working Group March 24, 2014 The United States and Japan established a bilateral Nuclear Security Working Group (NSWG) in 2011 in response to a shared desire to demonstrate leadership in strengthening nuclear security worldwide and in support of the Nuclear Security Summit process. This group developed a Roadmap containing tangible actions in support of shared objectives and goals. When taken together, these goals

  17. Technical-evaluation report on the adequacy of station electric-distribution-system voltages for the Prairie Island Nuclear Generating Plant, Units 1 and 2. (Docket Nos. 50-282, 50-306)

    SciTech Connect (OSTI)

    Selan, J C

    1982-09-17

    This report documents the technical evaluation of the adequacy of the station electric distribution system voltages for the Prairie Island Nuclear Generating Plant, Units 1 and 2. The evaluation is to determine if the onsite distribution system in conjunction with the offsite power sources has sufficient capacity to automatically start and operate all Class 1E loads within the equipment voltage ratings under certain conditions established by the Nuclear Regulatory Commission. The evaluation finds that with some minor transformer loading modifications, hardware changes and the results of equipment testing and manufacturer data, the offsite sources were demonstrated to supply adequate voltage to the Class 1E equipment under worst case conditions.

  18. South Carolina Nuclear Profile - Power Plants

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

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

  19. United States and Japan Sign Joint Nuclear Energy Action Plan...

    Office of Environmental Management (EM)

    Japan Sign Joint Nuclear Energy Action Plan to Promote Nuclear Energy Cooperation United States and Japan Sign Joint Nuclear Energy Action Plan to Promote Nuclear Energy ...

  20. Advanced nuclear plant control complex

    DOE Patents [OSTI]

    Scarola, Kenneth; Jamison, David S.; Manazir, Richard M.; Rescorl, Robert L.; Harmon, Daryl L.

    1993-01-01

    An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system (72) which is nuclear qualified for rapid response to changes in plant parameters and a component control system (64) which together provide a discrete monitoring and control capability at a panel (14-22, 26, 28) in the control room (10). A separate data processing system (70), which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs (84) and a large, overhead integrated process status overview board (24). The discrete indicator and alarm system (72) and the data processing system (70) receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board (24) is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof.

  1. EIS-0476: Vogtle Electric Generating Plant, Units 3 and 4

    Office of Energy Efficiency and Renewable Energy (EERE)

    This EIS evaluates the environmental impacts of construction and startup of the proposed Units 3 and 4 at the Vogtle Electric Generating Plant in Burke County, Georgia. DOE adopted two Nuclear Regulatory Commission EISs associated with this project (i.e., NUREG-1872, issued 8/2008, and NUREG-1947, issued 3/2011).

  2. Sabotage at Nuclear Power Plants

    SciTech Connect (OSTI)

    Purvis, James W.

    1999-07-21

    Recently there has been a noted worldwide increase in violent actions including attempted sabotage at nuclear power plants. Several organizations, such as the International Atomic Energy Agency and the US Nuclear Regulatory Commission, have guidelines, recommendations, and formal threat- and risk-assessment processes for the protection of nuclear assets. Other examples are the former Defense Special Weapons Agency, which used a risk-assessment model to evaluate force-protection security requirements for terrorist incidents at DOD military bases. The US DOE uses a graded approach to protect its assets based on risk and vulnerability assessments. The Federal Aviation Administration and Federal Bureau of Investigation conduct joint threat and vulnerability assessments on high-risk US airports. Several private companies under contract to government agencies use formal risk-assessment models and methods to identify security requirements. The purpose of this paper is to survey these methods and present an overview of all potential types of sabotage at nuclear power plants. The paper discusses emerging threats and current methods of choice for sabotage--especially vehicle bombs and chemical attacks. Potential consequences of sabotage acts, including economic and political; not just those that may result in unacceptable radiological exposure to the public, are also discussed. Applicability of risk-assessment methods and mitigation techniques are also presented.

  3. Science, society, and America's nuclear waste: Unit 3, The Nuclear Waste Policy Act

    SciTech Connect (OSTI)

    Not Available

    1992-01-01

    This teachers guide is unit 3, the nuclear waste policy act, in a four-unit secondary curriculum. It is intended to provide information about scientific and societal issues related to the management of spent nuclear fuel from generation of electricity at nuclear powerplants and high-level radioactive waste from US national defense activities. The curriculum, supporting classroom activities, and teaching materials present a brief discussion of energy and electricity generation, including that produced at nuclear power plants; information on sources, amounts, location, and characteristics of spent nuclear fuel and high-level radioactive waste; sources, types and effects of radiation; US policy for managing and disposing of spent nuclear fuel and high-level radioactive waste and what other countries are doing; and the components of the nuclear waste management system.

  4. Prediction of Technological Failures in Nuclear Power Plant Operation

    SciTech Connect (OSTI)

    Salnykov, A. A.

    2015-01-15

    A method for predicting operating technological failures in nuclear power plants which makes it possible to reduce the unloading of the generator unit during the onset and development of an anomalous engineering state of the equipment by detecting a change in state earlier and taking suitable measures. With the circulating water supply loop of a nuclear power plant as an example, scenarios and algorithms for predicting technological failures in the operation of equipment long before their actual occurrence are discussed.

  5. Analysis of the LaSalle Unit 2 nuclear power plant: Risk Methods Integration and Evaluation Program (RMIEP). Volume 8, Seismic analysis

    SciTech Connect (OSTI)

    Wells, J.E.; Lappa, D.A.; Bernreuter, D.L.; Chen, J.C.; Chuang, T.Y.; Johnson, J.J.; Campbell, R.D.; Hashimoto, P.S.; Maslenikov, O.R.; Tiong, L.W.; Ravindra, M.K.; Kincaid, R.H.; Sues, R.H.; Putcha, C.S.

    1993-11-01

    This report describes the methodology used and the results obtained from the application of a simplified seismic risk methodology to the LaSalle County Nuclear Generating Station Unit 2. This study is part of the Level I analysis being performed by the Risk Methods Integration and Evaluation Program (RMIEP). Using the RMIEP developed event and fault trees, the analysis resulted in a seismically induced core damage frequency point estimate of 6.OE-7/yr. This result, combined with the component importance analysis, indicated that system failures were dominated by random events. The dominant components included diesel generator failures (failure to swing, failure to start, failure to run after started), and condensate storage tank.

  6. Naval Nuclear Propulsion Plants | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    | (NNSA) Naval Nuclear Propulsion Plants In naval nuclear propulsion plants, fissioning of uranium atoms in the reactor core produces heat. Because the fission process also produces radiation, shielding is placed around the reactor to protect the crew. Despite close proximity to a reactor core, a typical crewmember receives less exposure to radiation than one who remains ashore and works in an office building. In naval nuclear propulsion plants, fissioning of uranium atoms in the reactor

  7. UNITED STATES NUCLEAR REGULATORY COMMISSION

    Office of Legacy Management (LM)

    WASHINGTON, 0. C. 20555 AUG i 3 1979 ,,~---Y--*. FCAF:Wi3 )I 70-364 : i: SNM-414,jAmendment No. 3 --A Babcock and Wilcox Company Nuclear Materials Division ATTN: Mr. Michael A. Austin Manager, Technical Control 609 North Warren Avenue Apollo, Pennsylvania 15613 Gentiemen: (1 i' \ (. \ In accordance with your application dated June 18, 1979, and pursuant to Title 10, Code of Federal Regulations, Part 70, Materials License SNM-414 is hereby amended to: 1. Delete the function of the Regulatory

  8. Nuclear Decommissioning Authority of the United Kingdom NDA ...

    Open Energy Info (EERE)

    Decommissioning Authority of the United Kingdom NDA Jump to: navigation, search Name: Nuclear Decommissioning Authority of the United Kingdom (NDA) Place: Cumbria, England, United...

  9. Pantex Plant | National Nuclear Security Administration | (NNSA)

    National Nuclear Security Administration (NNSA)

    Pantex Plant The Pantex Plant, near Amarillo, Texas, is charged with maintaining the safety, security and effectiveness of the nation's nuclear weapons stockpile. It is managed and operated by Consolidated Nuclear Security, LLC for the NNSA Production Office. Work performed at Pantex includes support of the nuclear weapons life extension programs; nuclear weapons dismantlement; the development, testing and fabrication of high explosive components; and interim storage and surveillance of

  10. Postconstruction report of the United Nuclear Corporation Disposal Site at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Environmental Restoration Program

    SciTech Connect (OSTI)

    Oakley, L.B.; Siberell, J.K.; Voskuil, T.L.

    1993-06-01

    Remedial actions conducted under the auspices of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) were completed at the Y-12 United Nuclear Corporation (UNC) Disposal Site in August 1992. The purpose of this Postconstruction Report is to summarize numerous technical reports and provide CERCLA documentation for completion of the remedial actions. Other CERCLA reports, such as the Feasibility Study for the UNC Disposal Site, provide documentation leading up to the remedial action decision. The remedial action chosen, placement of a modified RCRA cap, was completed successfully, and performance standards were either met or exceeded. This remedial action provided solutions to two environmentally contaminated areas and achieved the goal of minimizing the potential for contamination of the shallow groundwater downgradient of the site, thereby providing protection of human health and the environment. Surveillance and maintenance of the cap will be accomplished to ensure cap integrity, and groundwater monitoring downgradient of the site will continue to confirm the acceptability of the remedial action chosen.

  11. United States and Italy Sign Agreements to Advance Developments in Nuclear

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

    Energy | Department of Energy Italy Sign Agreements to Advance Developments in Nuclear Energy United States and Italy Sign Agreements to Advance Developments in Nuclear Energy September 30, 2009 - 12:00am Addthis Washington, D.C. - U.S. Secretary of Energy Steven Chu and Italian Minister for Economic Development Claudio Scajola today signed two important nuclear energy agreements that may lead to construction of new nuclear power plants and improved cooperation on advanced nuclear energy

  12. July 2010, Status and Outlook for Nuclear Energy In the United States |

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

    Department of Energy July 2010, Status and Outlook for Nuclear Energy In the United States July 2010, Status and Outlook for Nuclear Energy In the United States The U.S. nuclear power industry continues to make pro- gress toward the construction of new nuclear power plants in the United States. Currently, 13 license applica- tions are under active review by the Nuclear Regulatory Commission (NRC) for up to 22 new reactors. The De- partment of Energy has awarded conditional commit- ments for

  13. Radioactive Effluents from Nuclear Power Plants Annual Report 2007

    SciTech Connect (OSTI)

    U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation

    2010-12-10

    This report describes radioactive effluents from commercial nuclear power plants (NPPs) in the United States. This information was reported by the licensees for radioactive discharges that occurred in 2007. The report provides information relevant to the potential impact of NPPs on the environment and on public health.

  14. Radioactive Effluents from Nuclear Power Plants Annual Report 2008

    SciTech Connect (OSTI)

    U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation

    2010-12-10

    This report describes radioactive effluents from commercial nuclear power plants (NPPs) in the United States. This information was reported by the licensees for radioactive discharges that occurred in 2008. The report provides information relevant to the potential impact of NPPs on the environment and on public health.

  15. Inventory of power plants in the United States, 1993

    SciTech Connect (OSTI)

    Not Available

    1994-12-01

    The Inventory of Power Plants in the United States is prepared annually by the Survey Management Division, Office of Coal, Nuclear, Electric and Alternate Fuels, Energy Information Administration (EIA), U.S. Department of Energy (DOE). The purpose of this publication is to provide year-end statistics about electric generating units operated by electric utilities in the United States (the 50 States and the District of Columbia). The publication also provides a 10-year outlook of future generating unit additions. Data summarized in this report are useful to a wide audience including Congress, Federal and State agencies, the electric utility industry, and the general public. Data presented in this report were assembled and published by the EIA to fulfill its data collection and dissemination responsibilities as specified in the Federal Energy Administration Act of 1974 (Public Law 93-275) as amended.

  16. United States Marks 20 Years without Underground Nuclear Explosive...

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

    United States Marks 20 Years without Underground Nuclear Explosive Testing September 21, 2012 WASHINGTON, DC -- Twenty years ago, on September 23, 1992, the United States conducted ...

  17. DOE Announces Loan Guarantee Applications for Nuclear Power Plant...

    Office of Environmental Management (EM)

    Loan Guarantee Applications for Nuclear Power Plant Construction DOE Announces Loan Guarantee Applications for Nuclear Power Plant Construction October 2, 2008 - 3:43pm Addthis ...

  18. Safeguards Issues at Nuclear Reactors and Enrichment Plants ...

    Office of Scientific and Technical Information (OSTI)

    Safeguards Issues at Nuclear Reactors and Enrichment Plants Citation Details In-Document Search Title: Safeguards Issues at Nuclear Reactors and Enrichment Plants Authors: Boyer, ...

  19. Safeguards Issues at Nuclear Reactors and Enrichment Plants ...

    Office of Scientific and Technical Information (OSTI)

    Safeguards Issues at Nuclear Reactors and Enrichment Plants Citation Details In-Document Search Title: Safeguards Issues at Nuclear Reactors and Enrichment Plants You are ...

  20. EM Shares Waste Isolation Pilot Plant Lessons Learned with Nuclear...

    Office of Environmental Management (EM)

    Shares Waste Isolation Pilot Plant Lessons Learned with Nuclear Energy Agency EM Shares Waste Isolation Pilot Plant Lessons Learned with Nuclear Energy Agency April 14, 2016 - ...

  1. Naval Nuclear Propulsion Plants | National Nuclear Security Administra...

    National Nuclear Security Administration (NNSA)

    and works in an office building. U.S. naval nuclear propulsion plants use a pressurized-water reactor design that has two basic systems: the primary system and the secondary...

  2. Arkansas Nuclear Profile - Power Plants

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

    net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation ...,"1,835","15,023",100.0,"Entergy Arkansas Inc" "1 Plant 2 Reactors","1,835","15,023",100.0

  3. United States -Japan Joint Nuclear Energy Action Plan | Department of

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

    Energy -Japan Joint Nuclear Energy Action Plan United States -Japan Joint Nuclear Energy Action Plan President Bush of the United States and Prime Minister Koizumi of Japan have both stated their strong support for the contribution of nuclear power to energy security and the global environment. Japan was the first nation to endorse President Bush's Global Nuclear Energy Partnership. This describes a background of the partnership. United States -Japan Joint Nuclear Energy Action Plan (551.62

  4. Nuclear Energy In the United States Executive Summary

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

    0 Status and Outlook for Nuclear Energy In the United States Executive Summary The U.S. nuclear power industry continues to make pro- gress toward the construction of new nuclear...

  5. Pantex Plant | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Pantex Plant On Womens Equality Day, we celebrate NNSA's talented Women in STEM New Pantex Plant sensors provide ample warning to protect NNSA operations from lightning NNSA is charged with making sure the nation's nuclear deterrent is safe, secure, and effective. That mission includes protecting the Nuclear Security Enterprise from forces of nature. One natural threat, lightning, can damage electronics and even degrade concrete buildings and... NNSA's systems administrators keep the computers

  6. Inventory of power plants in the United States 1994

    SciTech Connect (OSTI)

    1995-10-18

    The Inventory of Power Plants in the US provides year-end statistics on generating units operated by electric utilities in the US (the 50 States and the District of Columbia). Statistics presented in this report reflect the status of generating units as of December 31, 1994. The publication also provides a 10-year outlook for generating unit additions. This report is prepared annually by the Coal and Electric Data and Renewables Division; Office of Coal, Nuclear, Electric and Alternate Fuels; Energy Information Administration (EIA); US Department of Energy (DOE). Data summarized in this report are useful to a wide audience including Congress, Federal, and State agencies; the electric utility industry; and the general public. This is a report of electric utility data; in cases where summary data of nonutility capacity are presented, it is specifically noted as such.

  7. Analysis of nuclear power plant component failures

    SciTech Connect (OSTI)

    Not Available

    1984-01-01

    Items are shown that have caused 90% of the nuclear unit outages and/or deratings between 1971 and 1980 and the magnitude of the problem indicated by an estimate of power replacement cost when the units are out of service or derated. The funding EPRI has provided on these specific items for R and D and technology transfer in the past and the funding planned in the future (1982 to 1986) are shown. EPRI's R and D may help the utilities on only a small part of their nuclear unit outage problems. For example, refueling is the major cause for nuclear unit outages or deratings and the steam turbine is the second major cause for nuclear unit outages; however, these two items have been ranked fairly low on the EPRI priority list for R and D funding. Other items such as nuclear safety (NRC requirements), reactor general, reactor and safety valves and piping, and reactor fuel appear to be receiving more priority than is necessary as determined by analysis of nuclear unit outage causes.

  8. US nuclear power plant operating cost and experience summaries

    SciTech Connect (OSTI)

    Kohn, W.E.; Reid, R.L.; White, V.S.

    1998-02-01

    NUREG/CR-6577, U.S. Nuclear Power Plant Operating Cost and Experience Summaries, has been prepared to provide historical operating cost and experience information on U.S. commercial nuclear power plants. Cost incurred after initial construction are characterized as annual production costs, representing fuel and plant operating and maintenance expenses, and capital expenditures related to facility additions/modifications which are included in the plant capital asset base. As discussed in the report, annual data for these two cost categories were obtained from publicly available reports and must be accepted as having different degrees of accuracy and completeness. Treatment of inconclusive and incomplete data is discussed. As an aid to understanding the fluctuations in the cost histories, operating summaries for each nuclear unit are provided. The intent of these summaries is to identify important operating events; refueling, major maintenance, and other significant outages; operating milestones; and significant licensing or enforcement actions. Information used in the summaries is condensed from annual operating reports submitted by the licensees, plant histories contained in Nuclear Power Experience, trade press articles, and the Nuclear Regulatory Commission (NRC) web site (www.nrc.gov).

  9. Inventory of Power Plants in the United States, October 1992

    SciTech Connect (OSTI)

    Not Available

    1993-10-27

    The Inventory of Power Plants in the United States is prepared annually by the Survey Management Division, Office of Coal, Nuclear, Electric and Alternate Fuels, Energy Information Administration (EIA), US Department of Energy (DOE). The purpose of this publication is to provide year-end statistics about electric generating units operated by electric utilities in the United States (the 50 States and the District of Columbia). The publication also provides a 10-year outlook of future generating unit additions. Data summarized in this report are useful to a wide audience including Congress, Federal and State agencies, the electric utility industry, and the general public. Data presented in this report were assembled and published by the EIA to fulfill its data collection and dissemination responsibilities as specified in the Federal Energy Administration Act of 1974 (Public Law 93-275) as amended. The report is organized into the following chapters: Year in Review, Operable Electric Generating Units, and Projected Electric Generating Unit Additions. Statistics presented in these chapters reflect the status of electric generating units as of December 31, 1992.

  10. New Hampshire Nuclear Profile - Power Plants

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

    "Seabrook Unit 1","1,247","10,910",100.0,"NextEra Energy Seabrook LLC" "1 Plant 1 Reactor","1,247","10,910",100.0 "Note: Totals may not equal sum of components due to ...

  11. Science, society, and America`s nuclear waste: Unit 3, The Nuclear Waste Policy Act. Teacher guide

    SciTech Connect (OSTI)

    Not Available

    1992-11-01

    This teachers guide is unit 3, the nuclear waste policy act, in a four-unit secondary curriculum. It is intended to provide information about scientific and societal issues related to the management of spent nuclear fuel from generation of electricity at nuclear powerplants and high-level radioactive waste from US national defense activities. The curriculum, supporting classroom activities, and teaching materials present a brief discussion of energy and electricity generation, including that produced at nuclear power plants; information on sources, amounts, location, and characteristics of spent nuclear fuel and high-level radioactive waste; sources, types and effects of radiation; US policy for managing and disposing of spent nuclear fuel and high-level radioactive waste and what other countries are doing; and the components of the nuclear waste management system.

  12. Nuclear plant cancellations: causes, costs, and consequences

    SciTech Connect (OSTI)

    Not Available

    1983-04-01

    This study was commissioned in order to help quantify the effects of nuclear plant cancellations on the Nation's electricity prices. This report presents a historical overview of nuclear plant cancellations through 1982, the costs associated with those cancellations, and the reasons that the projects were terminated. A survey is presented of the precedents for regulatory treatment of the costs, the specific methods of cost recovery that were adopted, and the impacts of these decisions upon ratepayers, utility stockholders, and taxpayers. Finally, the report identifies a series of other nuclear plants that remain at risk of canellation in the future, principally as a result of similar demand, finance, or regulatory problems cited as causes of cancellation in the past. The costs associated with these potential cancellations are estimated, along with their regional distributions, and likely methods of cost recovery are suggested.

  13. Integrated Risk Assessment for the LaSalle Unit 2 Nuclear Power Plant, Phenomenology and Risk Uncertainty Evaluation Program (PRUEP), MELCOR code calculations. Volume 3

    SciTech Connect (OSTI)

    Shaffer, C.J. [Science and Engineering Associates, Albuquerque, NM (United States); Miller, L.A.; Payne, A.C. Jr.

    1992-10-01

    A Level III Probabilistic Risk Assessment (PRA) has been performed for LaSalle Unit 2 under the Risk Methods Integration and Evaluation Program (RMIEP) and the Phenomenology and Risk Uncertainty Evaluation Program (PRUEP). This report documents the phenomenological calculations and sources of. uncertainty in the calculations performed with HELCOR in support of the Level II portion of the PRA. These calculations are an integral part of the Level II analysis since they provide quantitative input to the Accident Progression Event Tree (APET) and Source Term Model (LASSOR). However, the uncertainty associated with the code results must be considered in the use of the results. The MELCOR calculations performed include four integrated calculations: (1) a high-pressure short-term station blackout, (2) a low-pressure short-term station blackout, (3) an intermediate-term station blackout, and (4) a long-term station blackout. Several sensitivity studies investigating the effect of variations in containment failure size and location, as well as hydrogen ignition concentration are also documented.

  14. Integrated Risk Assessment for the LaSalle Unit 2 Nuclear Power Plant, Phenomenology and Risk Uncertainty Evaluation Program (PRUEP), MELCOR code calculations

    SciTech Connect (OSTI)

    Shaffer, C.J. (Science and Engineering Associates, Albuquerque, NM (United States)); Miller, L.A.; Payne, A.C. Jr.

    1992-10-01

    A Level III Probabilistic Risk Assessment (PRA) has been performed for LaSalle Unit 2 under the Risk Methods Integration and Evaluation Program (RMIEP) and the Phenomenology and Risk Uncertainty Evaluation Program (PRUEP). This report documents the phenomenological calculations and sources of. uncertainty in the calculations performed with HELCOR in support of the Level II portion of the PRA. These calculations are an integral part of the Level II analysis since they provide quantitative input to the Accident Progression Event Tree (APET) and Source Term Model (LASSOR). However, the uncertainty associated with the code results must be considered in the use of the results. The MELCOR calculations performed include four integrated calculations: (1) a high-pressure short-term station blackout, (2) a low-pressure short-term station blackout, (3) an intermediate-term station blackout, and (4) a long-term station blackout. Several sensitivity studies investigating the effect of variations in containment failure size and location, as well as hydrogen ignition concentration are also documented.

  15. Application of Nuclear Energy for Seawater Desalination: Design Concepts of Nuclear Desalination Plants

    SciTech Connect (OSTI)

    Faibish, R.S.; Konishi, T.; Gasparini, M.

    2002-07-01

    Nuclear energy is playing an important role in electricity generation, producing 16% of the world's electricity. However, most of the world's energy consumption is in the form of heat, in which case nuclear energy could also play an important role. In particular, process heat for seawater desalination using nuclear energy has been of growing interest to some Member States of the International Atomic Energy Agency over the past two decades. This growing interest stems from increasingly acute freshwater shortages in many arid and semi-arid zones around the world. Indeed, several national and international nuclear desalination demonstration programs are already under way or being planned. Of particular interest are projects for seawater nuclear desalination plants in coastal regions, where saline feed water can serve the dual purpose of cooling water for the nuclear reactor and as feed water for the desalination plant. In principle any nuclear reactor can provide energy (low-grade heat and/or electricity), as required by desalination processes. However, there are some additional requirements to be met under specific conditions in order to introduce nuclear desalination. Technical issues include meeting more stringent safety requirements (nuclear reactors themselves and nuclear-desalination integrated complexes in particular), and performance improvement of the integrated systems. Economic competitiveness is another important factor to be considered for a broader deployment of nuclear desalination. For technical robustness and economic competitiveness a number of design variants of coupling configurations of nuclear desalination integrated plant concepts are being evaluated. This paper identifies and discusses various factors, which support the attractiveness of nuclear desalination. It further summarizes some of the key approaches recommended for nuclear desalination complex design and gives an overview of various design concepts of nuclear desalination plants, which

  16. The Advanced BWR Nuclear Plant: Safe, economic nuclear energy

    SciTech Connect (OSTI)

    Redding, J.R.

    1994-12-31

    The safety and economics of Advanced BWR Nuclear Power Plants are outlined. The topics discussed include: ABWR Programs: status in US and Japan; ABWR competitiveness: safety and economics; SBWR status; combining ABWR and SBWR: the passive ABWR; and Korean/GE partnership.

  17. United States-Republic of Korea (ROK) International Nuclear Energy...

    Energy Savers [EERE]

    States-Republic of Korea (ROK) International Nuclear Energy Research Initiative (INERI) Annual Steering Committee Meeting United States-Republic of Korea (ROK) International ...

  18. Nuclear power plant simulators: their use in operator training and requalification

    SciTech Connect (OSTI)

    Jones, D.W.; Baer, D.K.; Francis, C.C.

    1980-07-01

    This report presents the results of a study performed for the Nuclear Regulatory Commission to evaluate the capabilities and use of nuclear power plant simulators either built or being built by the US nuclear power industry; to determine the adequacy of existing standards for simulator design and for the training of power plant operators on simulators; and to assess the issues about simulator training programs raised by the March 28, 1979, accident at Three Mile Island Unit 2.

  19. National Nuclear Security Administration United States Department...

    National Nuclear Security Administration (NNSA)

    and respond to the threats of nuclear proliferation and terrorism make a vital ... The JCPOA has dramatically reduced the threat of nuclear proliferation by blocking Iran's ...

  20. New Seismic Model Will Refine Hazard Analysis at U.S. Nuclear Plants |

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

    Department of Energy Seismic Model Will Refine Hazard Analysis at U.S. Nuclear Plants New Seismic Model Will Refine Hazard Analysis at U.S. Nuclear Plants January 31, 2012 - 2:09pm Addthis The Electric Power Research Institute (EPRI), the U.S. Department of Energy (DOE), and the U.S. Nuclear Regulatory Commission (NRC) released a new seismic study today that will help U.S. nuclear facilities in the central and eastern United States reassess seismic hazards. The Central and Eastern United

  1. News Release Closure of Russian Nuclear Plant.PDF

    National Nuclear Security Administration (NNSA)

    CONTACTS: FOR IMMEDIATE RELEASE Jonathan Kiell, 202586-7371 September 27, 2001 Date Set for Closure of Russian Nuclear Weapons Plant U.S. National Nuclear Security Administration ...

  2. Date Set for Closure of Russian Nuclear Weapons Plant - NNSA...

    National Nuclear Security Administration (NNSA)

    Date Set for Closure of Russian Nuclear Weapons Plant - NNSA Is Helping Make It Happen | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission ...

  3. Natural Gas Processing Plants in the United States: 2010 Update...

    Gasoline and Diesel Fuel Update (EIA)

    3. Btu Content at Plant Inlets for Processing Plants in the United States, 2009 Minimum Annual Btu Content Maximum Annual Btu Content Average Annual Btu Content Alaska 850 1071 985...

  4. 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

  5. Advanced nuclear plant control room complex

    DOE Patents [OSTI]

    Scarola, Kenneth; Jamison, David S.; Manazir, Richard M.; Rescorl, Robert L.; Harmon, Daryl L.

    1993-01-01

    An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system (72) which is nuclear qualified for rapid response to changes in plant parameters and a component control system (64) which together provide a discrete monitoring and control capability at a panel (14-22, 26, 28) in the control room (10). A separate data processing system (70), which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs (84) and a large, overhead integrated process status overview board (24). The discrete indicator and alarm system (72) and the data processing system (70) receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board (24) is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof.

  6. Radiological Assessment of effects from Fukushima Daiichi Nuclear Power Plant

    Broader source: Energy.gov [DOE]

    NNSA presentation on Radiological Assessment of effects from Fukushima Daiichi Nuclear Power Plant from May 13, 2011

  7. UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I

    Office of Legacy Management (LM)

    and Lab Branch Division of Nuclear Materials Safety Docket No. 040-07123 License No. ... SUB-748 file cc wencl: State of New York NATIONAL LEAD COMPANY ?La;R Pile cOpt NUCLEAR ...

  8. Autonomous Control of Nuclear Power Plants

    SciTech Connect (OSTI)

    Basher, H.

    2003-10-20

    A nuclear reactor is a complex system that requires highly sophisticated controllers to ensure that desired performance and safety can be achieved and maintained during its operations. Higher-demanding operational requirements such as reliability, lower environmental impacts, and improved performance under adverse conditions in nuclear power plants, coupled with the complexity and uncertainty of the models, necessitate the use of an increased level of autonomy in the control methods. In the opinion of many researchers, the tasks involved during nuclear reactor design and operation (e.g., design optimization, transient diagnosis, and core reload optimization) involve important human cognition and decisions that may be more easily achieved with intelligent methods such as expert systems, fuzzy logic, neural networks, and genetic algorithms. Many experts in the field of control systems share the idea that a higher degree of autonomy in control of complex systems such as nuclear plants is more easily achievable through the integration of conventional control systems and the intelligent components. Researchers have investigated the feasibility of the integration of fuzzy logic, neural networks, genetic algorithms, and expert systems with the conventional control methods to achieve higher degrees of autonomy in different aspects of reactor operations such as reactor startup, shutdown in emergency situations, fault detection and diagnosis, nuclear reactor alarm processing and diagnosis, and reactor load-following operations, to name a few. With the advancement of new technologies and computing power, it is feasible to automate most of the nuclear reactor control and operation, which will result in increased safety and economical benefits. This study surveys current status, practices, and recent advances made towards developing autonomous control systems for nuclear reactors.

  9. National Nuclear Security Administration United States Department of Energy

    National Nuclear Security Administration (NNSA)

    United States Department of Energy Washington, DC 20585 Prevent, Counter, and Respond-A Strategic Plan to Reduce Global Nuclear Threats FY 2017-FY 2021 Report to Congress March 2016 This page left blank intentionally. Department of Energy/National Nuclear Security Administration | March 2016 Prevent, Counter, and Respond--A Strategic Plan to Reduce Global Nuclear Threats (FY 2017-FY 2021)| Page i Message from the Administrator The Department of Energy's National Nuclear Security Administration

  10. Seismic requirements for design of nuclear power plants and nuclear test facilities

    SciTech Connect (OSTI)

    Not Available

    1985-02-01

    This standard establishes engineering requirements for the design of nuclear power plants and nuclear test facilities to accommodate vibratory effects of earthquakes.

  11. Fatigue monitoring in Nuclear Power Plants

    SciTech Connect (OSTI)

    Ware, A.G.; Shah, V.N.

    1995-04-01

    This paper summarizes fatigue monitoring methods and surveys their application in the nuclear power industry. The paper is based on a review of the technical literature. Two main reasons for fatigue monitoring are more frequent occurrence of some transients than that assumed in the fatigue design analysis and the discovery of stressors that were not included in the fatigue design analysis but may cause significant fatigue damage at some locations. One fatigue monitoring method involves use of plant operating data and procedures to update the fatigue usage. Another method involves monitoring of plant operating parameters using existing, or if needed, supplementary plant instrumentation for online computation of fatigue usage. Use of fatigue monitoring has better defined the operational transients. Most operational transients have been found less severe and fewer in numbers than anticipated in the design fatigue analysis. Use of fatigue monitoring has assisted in quantifying newly discovered stressors and has helped in detecting the presence of thermal stratification of unsuspected locations.

  12. Owners of nuclear power plants: Percentage ownership of commercial nuclear power plants by utility companies

    SciTech Connect (OSTI)

    Wood, R.S.

    1987-08-01

    The following list indicates percentage ownership of commercial nuclear power plants by utility companies as of June 1, 1987. The list includes all plants licensed to operate, under construction, docked for NRC safety and environmental reviews, or under NRC antitrust review. It does not include those plants announced but not yet under review or those plants formally canceled. In many cases, ownership may be in the process of changing as a result of altered financial conditions, changed power needs, and other reasons. However, this list reflects only those ownership percentages of which the NRC has been formally notified. Part I lists plants alphabetically with their associated applicants/licensees and percentage ownership. Part II lists applicants/licensees alphabetically with their associated plants and percentage ownership. Part I also indicates which plants have received operating licenses (OL's). Footnotes for both parts appear at the end of this document.

  13. Lesson 7 - Waste from Nuclear Power Plants | Department of Energy

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

    7 - Waste from Nuclear Power Plants Lesson 7 - Waste from Nuclear Power Plants This lesson takes a look at the waste from electricity production at nuclear power plants. It considers the different types of waste generated, as well as how we deal with each type of waste. Specific topics covered include: Nuclear Waste Some radioactive Types of radioactive waste Low-level waste High-level waste Disposal and storage Low-level waste disposal Spent fuel storage Waste isolation Reprocessing

  14. Guidance for Deployment of Mobile Technologies for Nuclear Power Plant

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

    Field Workers | Department of Energy Guidance for Deployment of Mobile Technologies for Nuclear Power Plant Field Workers Guidance for Deployment of Mobile Technologies for Nuclear Power Plant Field Workers This report is a guidance document prepared for the benefit of commercial nuclear power plants' (NPPs) supporting organizations and personnel who are considering or undertaking deployment of mobile technology for the purpose of improving human performance and plant status control (PSC)

  15. 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)

  16. United States and Mexico to Partner in Fight Against Nuclear...

    Energy Savers [EERE]

    United States and Mexico to Partner in Fight Against Nuclear Smuggling April 16, 2007 - 12:36pm Addthis WASHINGTON, DC - U.S. Secretary of Energy Samuel W. Bodman and Mexican ...

  17. Cesium Removal at Fukushima Nuclear Plant - 13215

    SciTech Connect (OSTI)

    Braun, James L.; Barker, Tracy A.

    2013-07-01

    The Great East Japan Earthquake that took place on March 11, 2011 created a number of technical challenges at the Fukushima Daiichi Nuclear Plant. One of the primary challenges involved the treatment of highly contaminated radioactive wastewater. Avantech Inc. developed a unique patent pending treatment system that addressed the numerous technical issues in an efficient and safe manner. Our paper will address the development of the process from concept through detailed design, identify the lessons learned, and provide the updated results of the project. Specific design and operational parameters/benefits discussed in the paper include: - Selection of equipment to address radionuclide issues; - Unique method of solving the additional technical issues associated with Hydrogen Generation and Residual Heat; - Operational results, including chemistry, offsite discharges and waste generation. Results show that the customized process has enabled the utility to recycle the wastewater for cooling and reuse. This technology had a direct benefit to nuclear facilities worldwide. (authors)

  18. Fact Sheet: United States-Japan Joint Nuclear Energy Action Plan...

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

    United States-Japan Joint Nuclear Energy Action Plan Fact Sheet: United States-Japan Joint Nuclear Energy Action Plan PDF icon Fact Sheet: United States-Japan Joint Nuclear Energy ...

  19. United States nuclear tests, July 1945 through September 1992

    SciTech Connect (OSTI)

    Not Available

    1994-12-01

    This document lists chronologically and alphabetically by name all nuclear tests and simultaneous detonations conducted by the United States from July 1945 through September 1992. Several tests conducted during Operation Dominic involved missile launches from Johnston Atoll. Several of these missile launches were aborted, resulting in the destruction of the missile and nuclear device either on the pad or in the air.

  20. A Study of United States Hydroelectric Plant Ownership

    SciTech Connect (OSTI)

    Hall, Douglas G.; Reeves, Kelly S.

    2006-06-01

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

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

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

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

  2. DOE Announces Loan Guarantee Applications for Nuclear Power Plant

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

    Construction | Department of Energy Loan Guarantee Applications for Nuclear Power Plant Construction DOE Announces Loan Guarantee Applications for Nuclear Power Plant Construction October 2, 2008 - 3:43pm Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced it has received 19 Part I applications from 17 electric power companies for federal loan guarantees to support the construction of 14 nuclear power plants in response to its June 30, 2008 solicitation. The

  3. Ongoing Space Nuclear Systems Development in the United States

    SciTech Connect (OSTI)

    S. Bragg-Sitton; J. Werner; S. Johnson; Michael G. Houts; Donald T. Palac; Lee S. Mason; David I. Poston; A. Lou Qualls

    2011-10-01

    Reliable, long-life power systems are required for ambitious space exploration missions. Nuclear power and propulsion options can enable a bold, new set of missions and introduce propulsion capabilities to achieve access to science destinations that are not possible with more conventional systems. Space nuclear power options can be divided into three main categories: radioisotope power for heating or low power applications; fission power systems for non-terrestrial surface application or for spacecraft power; and fission power systems for electric propulsion or direct thermal propulsion. Each of these areas has been investigated in the United States since the 1950s, achieving various stages of development. While some nuclear systems have achieved flight deployment, others continue to be researched today. This paper will provide a brief overview of historical space nuclear programs in the U.S. and will provide a summary of the ongoing space nuclear systems research, development, and deployment in the United States.

  4. Commercial Nuclear Reprocessing in the United States

    SciTech Connect (OSTI)

    Sherrill, Charles Leland; Balatsky, Galya Ivanovna

    2015-09-09

    The short presentation outline: Reprocessing Overview; Events leading up to Carter’s Policy; Results of the decision; Policy since Nuclear Nonproliferation Act. Conclusions reached: Reprocessing ban has become an easy and visible fix to the public concern about proliferation, but has not completely stopped proliferation; and, Reprocessing needs to become detached from political considerations, so technical research can continue, regardless of the policy decisions we decide to take.

  5. Safeguards Issues at Nuclear Reactors and Enrichment Plants ...

    Office of Scientific and Technical Information (OSTI)

    explosive devices or for purposes unknown, and deterrence ... Country of Publication: United States Language: English Subject: 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 21 SPECIFIC ...

  6. SUPERCRITICAL STEAM CYCLE FOR NUCLEAR POWER PLANT

    SciTech Connect (OSTI)

    Tsiklauri, Georgi V.; Talbert, Robert J.; Schmitt, Bruce E.; Filippov, Gennady A.; Bogojavlensky, Roald G.; Grishanin, Evgeny I.

    2005-07-01

    Revolutionary improvement of the nuclear plant safety and economy with light water reactors can be reached with the application of micro-fuel elements (MFE) directly cooled by a supercritical pressure light-water coolant-moderator. There are considerable advantages of the MFE as compared with the traditional fuel rods, such as: Using supercritical and superheated steam considerably increases the thermal efficiency of the Rankine cycle up to 44-45%. Strong negative coolant and void reactivity coefficients with a very short thermal delay time allow the reactor to shutdown quickly in the event of a reactivity or power excursion. Core melting and the creation of corium during severe accidents are impossible. The heat transfer surface area is larger by several orders of magnitude due to the small spherical dimensions of the MFE. The larger heat exchange surface significantly simplifies residual heat removal by natural convection and radiation from the core to a subsequent passive system of heat removal.

  7. Inspection of Nuclear Power Plant Containment Structures

    SciTech Connect (OSTI)

    Graves, H.L.; Naus, D.J.; Norris, W.E.

    1998-12-01

    Safety-related nuclear power plant (NPP) structures are designed to withstand loadings from a number of low-probability external and interval events, such as earthquakes, tornadoes, and loss-of-coolant accidents. Loadings incurred during normal plant operation therefore generally are not significant enough to cause appreciable degradation. However, these structures are susceptible to aging by various processes depending on the operating environment and service conditions. The effects of these processes may accumulate within these structures over time to cause failure under design conditions, or lead to costly repair. In the late 1980s and early 1990s several occurrences of degradation of NPP structures were discovered at various facilities (e.g., corrosion of pressure boundary components, freeze- thaw damage of concrete, and larger than anticipated loss of prestressing force). Despite these degradation occurrences and a trend for an increasing rate of occurrence, in-service inspection of the safety-related structures continued to be performed in a somewhat cursory manner. Starting in 1991, the U.S. Nuclear Regulatory Commission (USNRC) published the first of several new requirements to help ensure that adequate in-service inspection of these structures is performed. Current regulatory in-service inspection requirements are reviewed and a summary of degradation experience presented. Nondestructive examination techniques commonly used to inspect the NPP steel and concrete structures to identify and quantify the amount of damage present are reviewed. Finally, areas where nondestructive evaluation techniques require development (i.e., inaccessible portions of the containment pressure boundary, and thick heavily reinforced concrete sections are discussed.

  8. Next Generation Nuclear Plant GAP Analysis Report

    SciTech Connect (OSTI)

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

    2008-12-01

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

  9. Science, society, and America's nuclear waste: Unit 3, The Nuclear Waste Policy Act

    SciTech Connect (OSTI)

    Not Available

    1992-01-01

    This is the 3rd unit, (The Nuclear Waste Policy Act) a four-unit secondary curriculum. It is intended to provide information about scientific and societal issues related to the management of spent nuclear fuel from generation of electricity at nuclear powerplants and high-level radioactive waste from US national defense activities. The curriculum, supporting classroom activities, and teaching materials present a brief discussion of energy and electricity generation, including that produced at nuclear powerplants; information on sources, amounts, location, and characteristics of spent nuclear fuel and high-level radioactive waste; sources, types and effects of radiation; US policy for managing and disposing of spent nuclear fuel and high-level radioactive waste and what other countries are doing; and the components of the nuclear waste management system.

  10. Science, society, and America`s nuclear waste: Unit 3, The Nuclear Waste Policy Act

    SciTech Connect (OSTI)

    Not Available

    1992-11-01

    This is the 3rd unit, (The Nuclear Waste Policy Act) a four-unit secondary curriculum. It is intended to provide information about scientific and societal issues related to the management of spent nuclear fuel from generation of electricity at nuclear powerplants and high-level radioactive waste from US national defense activities. The curriculum, supporting classroom activities, and teaching materials present a brief discussion of energy and electricity generation, including that produced at nuclear powerplants; information on sources, amounts, location, and characteristics of spent nuclear fuel and high-level radioactive waste; sources, types and effects of radiation; US policy for managing and disposing of spent nuclear fuel and high-level radioactive waste and what other countries are doing; and the components of the nuclear waste management system.

  11. Inventory of power plants in the United States as of January 1, 1997

    SciTech Connect (OSTI)

    1997-12-01

    The Inventory of Power Plants in the United States provides annual statistics on generating units operated by electric utilities in the United States (the 50 States and the District of Columbia). Statistics presented in this report reflect the status of generating units as of January 1, 1997. The publication also provides a 10-yr outlook for generating unit additions. This report is prepared annually by the Coal and Electric Data and Renewables Division; Office of Coal, Nuclear, Electric and Alternate Fuels; Energy Information Administration (EIA); U.S. Department of Energy (DOE). Data summarized in this report are useful to a wide audience including Congress; Federal and State agencies; the electric utility industry; and the general public. Data presented in this report were assembled and published by the EIA to fulfill its data collection and dissemination responsibilities as specified in the Federal Energy Administration Act of 1974 (Public Law 93-275) as amended.

  12. Inventory of power plants in the United States as of January 1, 1996

    SciTech Connect (OSTI)

    1996-12-01

    The Inventory of Power Plants in the United States provides annual statistics on generating units operated by electric utilities in the United States (the 50 States and the District of Columbia). Statistics presented in this report reflect the status of generating units as of January 1, 1996. The publication also provides a 10-year outlook for generating unit additions. This report is prepared annually by the Coal and Electric Data and Renewables Division; Office of Coal, Nuclear, Electric and Alternate Fuels; Energy Information Administration (EIA); U.S. Department of Energy (DOE). Data summarized in this report are useful to a wide audience including Congress; Federal and State agencies; the electric utility industry; and the general public. Data presented in this report were assembled and published by the EIA to fulfill its data collection and dissemination responsibilities as specified in the Federal Energy Administration Act of 1974 as amended.

  13. Plutonium Processing Plant Deactivated | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration | (NNSA) Plutonium Processing Plant Deactivated Plutonium Processing Plant Deactivated Hanford, WA The Plutonium Uranium Extraction Facility (PUREX), the largest of the Nation's Cold War plutonium processing plants, is deactivated a year ahead of schedule

  14. 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.

  15. 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.

  16. Design issues concerning Iran`s Bushehr nuclear power plant VVER-1000 conversion

    SciTech Connect (OSTI)

    Carson, C.F.

    1996-12-31

    On January 8, 1995, the Atomic Energy Organization of Iran (AEOI) signed a contract for $800 million with the Russian Federation Ministry for Atomic Energy (Minatom) to complete Bushehr nuclear power plant (BNPP) unit 1. The agreement called for a Russian VVER-1000/320 pressurized water reactor (PWR) to be successfully installed into the existing German-built BNPP facilities in 5 yr. System design differences, bomb damage, and environmental exposure are key issues with which Minatom must contend in order to fulfill the contract. The AEOI under the Shah of Iran envisioned Bushehr as the first of many nuclear power plants, with Iran achieving 24 GW(electric) by 1993 and 34 GW(electric) by 2000. Kraftwerk Union AG (KWU) began construction of the two-unit plant near the Persian Gulf town of Halileh in 1975. Unit 1 was {approx}80% complete and unit 2 was {approx}50% complete when construction was interrupted by the 1979 Iranian Islamic revolution. Despite repeated AEOI attempts to lure KWU and other companies back to Iran to complete the plant, Western concerns about nuclear proliferation in Iran and repeated bombings of the plant during the 1980-1988 Iran-Iraq war dissuaded Germany from resuming construction.

  17. The Status of Plant Life Assessment Program of Wolsong Unit 1

    SciTech Connect (OSTI)

    Taek-Ho, Song; Ill-Seok, Jeong; Sung-Yull, Hong; Sue-Deuk, Lee

    2006-07-01

    Wolsong Unit 1 is a CANDU plant which began its commercial operation in 1983 with design life of 30 years. Korea Electric Power Research Institute (KEPRI) had performed the phase 1 of plant life assessment program of Wolsong Unit 1 from the year of 2000 to 2003. The following program phase II is on going to 2007 in order to assess in-detail life evaluation and aging management program development. The phase 1 performed life evaluations of critical components such as fuel channels, feeder pipes, steam-generators and so on. The phase II assesses aging degradations and residual life of the components, structures, and systems (SSCs) screened as important to the continued operation beyond its design life. This paper summarizes recent trends of CANDU PLiM (plant lifetime management) in Canada and introduces the status of Wolsong Unit 1 plant life assessment program in Korea. KEPRI and KHNP (Korea Hydro and Nuclear Power) had performed aging analysis of the fuel channels and feeder pipes of Wolsong Unit 1. The aging analysis showed that some fuel channels could be elongated longer and the thickness of some feeder pipes less than the criteria before plant design life. (authors)

  18. Nuclear plant-aging research on reactor protection systems

    SciTech Connect (OSTI)

    Meyer, L.C.

    1988-01-01

    This report presents the rsults of a review of the Reactor Trip System (RTS) and the Engineered Safety Feature Actuating System (ESFAS) operating experiences reported in Licensee Event Reports (LER)s, the Nuclear Power Experience data base, Nuclear Plant Reliability Data System, and plant maintenance records. Our purpose is to evaluate the potential significance of aging, including cycling, trips, and testing as contributors to degradation of the RTS and ESFAS. Tables are presented that show the percentage of events for RTS and ESFAS classified by cause, components, and subcomponents for each of the Nuclear Steam Supply System vendors. A representative Babcock and Wilcox plant was selected for detailed study. The US Nuclear Regulatory Commission's Nuclear Plant Aging Research guidelines were followed in performing the detailed study that identified materials susceptible to aging, stressors, environmental factors, and failure modes for the RTS and ESFAS as generic instrumentation and control systems. Functional indicators of degradation are listed, testing requirements evaluated, and regulatory issues discussed.

  19. Mesoscale to plant-scale models of nuclear waste reprocessing.

    SciTech Connect (OSTI)

    Noble, David Frederick; O'Hern, Timothy John; Moffat, Harry K.; Nemer, Martin B.; Domino, Stefan Paul; Rao, Rekha Ranjana; Cipiti, Benjamin B.; Brotherton, Christopher M.; Jove-Colon, Carlos F.; Pawlowski, Roger Patrick

    2010-09-01

    Imported oil exacerabates our trade deficit and funds anti-American regimes. Nuclear Energy (NE) is a demonstrated technology with high efficiency. NE's two biggest political detriments are possible accidents and nuclear waste disposal. For NE policy, proliferation is the biggest obstacle. Nuclear waste can be reduced through reprocessing, where fuel rods are separated into various streams, some of which can be reused in reactors. Current process developed in the 1950s is dirty and expensive, U/Pu separation is the most critical. Fuel rods are sheared and dissolved in acid to extract fissile material in a centrifugal contactor. Plants have many contacts in series with other separations. We have taken a science and simulation-based approach to develop a modern reprocessing plant. Models of reprocessing plants are needed to support nuclear materials accountancy, nonproliferation, plant design, and plant scale-up.

  20. Portsmouth Gaseous Diffusion Plant- Quadrant I Groundwater Investigative (5-Unit) Area Plume

    Broader source: Energy.gov [DOE]

    Groundwater Database Report - Portsmouth Gaseous Diffusion Plant - Quadrant I Groundwater Investigative (5-Unit) Area Plume

  1. P.C. 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BWR...

    Office of Scientific and Technical Information (OSTI)

    Erosioncorrosion-induced pipe wall thinning in US Nuclear Power Plants Wu, P.C. 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BWR TYPE REACTORS; PIPES; CORROSION; EROSION;...

  2. A story of revival: United Coal's East Gulf preparation plant

    SciTech Connect (OSTI)

    2009-04-15

    Some say beauty is in the eye of the beholder, but when United Coal purchased the assets of White Mountain Mining in late 2005, the attractiveness of the acquired assets did not require much debate. Whilst the Pocahontas Coal reserves included in the acquisition were very desirable for producing coke, the East Gulf preparation plant was in poor condition. In order to minimize cost, maintenance and manpower whilst increasing production, the circuits in the existing plant were modified and the Barvoy Vessel was replaced with a single, pump fed, 30-inch Krebs HM cyclone. A spiral circuit was added as were screen bowl centrifuges. Finally the plant was given a structural upgrade and a new siding was installed. With the East Gulf restoration project complete, the United Coal Co. (UCC) and Pocahontas Coal are now considering expanding the Affinity complex. 2 figs., 6 photos.

  3. Multi-unit Operations in Non-Nuclear Systems: Lessons Learned for Small Modular Reactors

    SciTech Connect (OSTI)

    OHara J. M.; Higgins, J.; DAgostino, A.

    2012-01-17

    The nuclear-power community has reached the stage of proposing advanced reactor designs to support power generation for decades to come. Small modular reactors (SMRs) are one approach to meet these energy needs. While the power output of individual reactor modules is relatively small, they can be grouped to produce reactor sites with different outputs. Also, they can be designed to generate hydrogen, or to process heat. Many characteristics of SMRs are quite different from those of current plants and may be operated quite differently. One difference is that multiple units may be operated by a single crew (or a single operator) from one control room. The U.S. Nuclear Regulatory Commission (NRC) is examining the human factors engineering (HFE) aspects of SMRs to support licensing reviews. While we reviewed information on SMR designs to obtain information, the designs are not completed and all of the design and operational information is not yet available. Nor is there information on multi-unit operations as envisioned for SMRs available in operating experience. Thus, to gain a better understanding of multi-unit operations we sought the lesson learned from non-nuclear systems that have experience in multi-unit operations, specifically refineries, unmanned aerial vehicles and tele-intensive care units. In this paper we report the lessons learned from these systems and the implications for SMRs.

  4. Overview of the United States spent nuclear fuel program

    SciTech Connect (OSTI)

    Hurt, W.L.

    1997-12-01

    As a result of the end of the Cold War, the mission of the US Department of Energy (DOE) has shifted from an emphasis on nuclear weapons development and production to an emphasis on the safe management and disposal of excess nuclear materials including spent nuclear fuel from both production and research reactors. Within the US, there are two groups managing spent nuclear fuel. Commercial nuclear power plants are managing their spent nuclear fuel at the individual reactor sites until the planned repository is opened. All other spent nuclear fuel, including research reactors, university reactors, naval reactors, and legacy material from the Cold War is managed by DOE. DOE`s mission is to safely and efficiently manage its spent nuclear fuel and prepare it for disposal. This mission involves correcting existing vulnerabilities in spent fuel storage; moving spent fuel from wet basins to dry storage; processing at-risk spent fuel; and preparing spent fuel in road-ready condition for repository disposal. Most of DOE`s spent nuclear fuel is stored in underwater basins (wet storage). Many of these basins are outdated, and spent fuel is to be removed and transferred to more modern basins or to new dry storage facilities. In 1995, DOE completed a complex-wide environmental impact analysis that resulted in spent fuel being sent to one of three principal DOE sites for interim storage (up to 40 years) prior to shipment to a repository. This regionalization by fuel type will allow for economies of scale yet minimize unnecessary transportation. This paper discusses the national SNF program, ultimate disposition of SNF, and the technical challenges that have yet to be resolved, namely, release rate testing, non-destructive assay, alternative treatments, drying, and chemical reactivity.

  5. Fresh nuclear fuel measurements at Ukrainian nuclear power plants

    SciTech Connect (OSTI)

    Kuzminski, Jozef; Ewing, Tom; Dickman, Debbie; Gavrilyuk, Victor; Drapey, Sergey; Kirischuk, Vladimir; Strilchuk, Nikolay

    2009-01-01

    In 2005, the Provisions on Nuclear Material Measurement System was enacted in Ukraine as an important regulatory driver to support international obligations in nuclear safeguards and nonproliferation. It defines key provisions and requirements for material measurement and measurement control programs to ensure the quality and reliability of measurement data within the framework of the State MC&A System. Implementing the Provisions requires establishing a number of measurement techniques for both fresh and spent nuclear fuel for various types of Ukrainian reactors. Our first efforts focused on measurements of fresh nuclear fuel from a WWR-1000 power reactor.

  6. 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 –

  7. Secretary Bodman Announces Federal Risk Insurance for Nuclear Power Plants

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

    & Touts Robust Economy | Department of Energy Federal Risk Insurance for Nuclear Power Plants & Touts Robust Economy Secretary Bodman Announces Federal Risk Insurance for Nuclear Power Plants & Touts Robust Economy August 4, 2006 - 8:42am Addthis ATLANTA, GA - After touring Georgia Power and speaking to its employees, U.S. Department of Energy (DOE) Secretary Samuel W. Bodman today announced completion of the final rule that establishes the process for utility companies building

  8. Method for assigning sites to projected generic nuclear power plants

    SciTech Connect (OSTI)

    Holter, G.M.; Purcell, W.L.; Shutz, M.E.; Young, J.R.

    1986-07-01

    Pacific Northwest Laboratory developed a method for forecasting potential locations and startup sequences of nuclear power plants that will be required in the future but have not yet been specifically identified by electric utilities. Use of the method results in numerical ratings for potential nuclear power plant sites located in each of the 10 federal energy regions. The rating for each potential site is obtained from numerical factors assigned to each of 5 primary siting characteristics: (1) cooling water availability, (2) site land area, (3) power transmission land area, (4) proximity to metropolitan areas, and (5) utility plans for the site. The sequence of plant startups in each federal energy region is obtained by use of the numerical ratings and the forecasts of generic nuclear power plant startups obtained from the EIA Middle Case electricity forecast. Sites are assigned to generic plants in chronological order according to startup date.

  9. I UNITED STATES NUCLEAR REGU.LATORYCOMMISS& REGION I

    Office of Legacy Management (LM)

    ' \*-'- I UNITED STATES NUCLEAR REGU.LATORYCOMMISS& REGION I 63, PARK AVENUE KING OF PRUSSIA. PENNSY LVANIA 19406 I..*. :+ 2 6 JUN 1979 2.lr.b The Commonwealth of Massachusetts Department of Public Health Division of Health Care Standards 8 Regulation ATTN: Mr. Gerald S. Parker, Director Radiation Control Programs 80 Boylston Street, Room 835 Boston, Massachusetts 02116 Dear Mr. Parker: Enclosed for your information and retention is a copy of the NRC, Region I Investigation Report No.

  10. United States and France Sign Joint Statement on Civil Liability for Nuclear Damage

    Broader source: Energy.gov [DOE]

    The United States and France today issued the Joint Statement on Civil Liability for Nuclear Damage that sets forth the common views of the United States and France on civil nuclear liability

  11. N.R. 20 FOSSIL-FUELED POWER PLANTS; 21 SPECIFIC NUCLEAR REACTORS...

    Office of Scientific and Technical Information (OSTI)

    20 FOSSIL-FUELED POWER PLANTS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 14 SOLAR ENERGY; 15 GEOTHERMAL ENERGY; GEOTHERMAL POWER PLANTS; COMPUTERIZED SIMULATION; HEAT...

  12. Managing aging in nuclear power plants: Insights from NRC`s Maintenance Team Inspection reports

    SciTech Connect (OSTI)

    Fresco, A.; Subudhi, M.

    1992-12-31

    A plant`s maintenance program is the principal vehicle through which age-related degradation is managed. From 1988 to 1991, the NRC evaluated the maintenance program of every nuclear power plant in the United States. Forty-four out of a total of sixty-seven of the reports issued on these in-depth team inspections have been reviewed for insights into the strengths and weaknesses of the programs as related to the need to understand and manage the effects of aging on nuclear plant structures, systems, and components (SSCs). Relevant information has been extracted from these inspection reports sorted into several categories; including Specific Aging Insights, Preventive Maintenance, Predictive Maintenance and Condition Monitoring, Post Maintenance Testing, Failure Trending, Root Cause Analysis and Usage of Probabilistic Risk Assessment in the Maintenance Process. Specific examples of inspection and monitoring techniques successfully used by utilities to detect degradation due to aging have been identified.

  13. The Regulatory Challenges of Decommissioning Nuclear Power Plants in Korea - 13101

    SciTech Connect (OSTI)

    Lee, Jungjoon; Ahn, Sangmyeon; Choi, Kyungwoo; Kim, Juyoul; Kim, Juyub

    2013-07-01

    As of 2012, 23 units of nuclear power plants are in operation, but there is no experience of permanent shutdown and decommissioning of nuclear power plant in Korea. It is realized that, since late 1990's, improvement of the regulatory framework for decommissioning has been emphasized constantly from the point of view of International Atomic Energy Agency (IAEA)'s safety standards. And it is known that now IAEA prepare the safety requirement on decommissioning of facilities, its title is the Safe Decommissioning of Facilities, General Safety Requirement Part 6. According to the result of IAEA's Integrated Regulatory Review Service (IRRS) mission to Korea in 2011, it was recommended that the regulatory framework for decommissioning should require decommissioning plans for nuclear installations to be constructed and operated and these plans should be updated periodically. In addition, after the Fukushima nuclear disaster in Japan in March of 2011, preparedness for early decommissioning caused by an unexpected severe accident became also important issues and concerns. In this respect, it is acknowledged that the regulatory framework for decommissioning of nuclear facilities in Korea need to be improved. First of all, we identify the current status and relevant issues of regulatory framework for decommissioning of nuclear power plants compared to the IAEA's safety standards in order to achieve our goal. And then the plan is to be established for improvement of regulatory framework for decommissioning of nuclear power plants in Korea. After dealing with it, it is expected that the revised regulatory framework for decommissioning could enhance the safety regime on the decommissioning of nuclear power plants in Korea in light of international standards. (authors)

  14. Radioactive materials released from nuclear power plants

    SciTech Connect (OSTI)

    Tichler, J.; Norden, K.; Congemi, J. )

    1991-05-01

    Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1988 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1988 release data are summarized in tabular form. Data covering specific radionuclides are summarized. 16 tabs.

  15. Radioactive materials released from nuclear power plants

    SciTech Connect (OSTI)

    Tichler, J.; Norden, K.; Congemi, J. )

    1989-10-01

    Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1987 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1987 release data are summarized in tabular form. Data covering specific radionuclides are summarized. 16 tabs.

  16. Radioactive materials released from nuclear power plants

    SciTech Connect (OSTI)

    Tichler, J.; Benkovitz, C.

    1981-11-01

    Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1979 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1979 release data are compared with previous year's releases in tabular form. Data covering specific radionuclides are summarized.

  17. Liquid metal cooled nuclear reactor plant system

    DOE Patents [OSTI]

    Hunsbedt, Anstein; Boardman, Charles E.

    1993-01-01

    A liquid metal cooled nuclear reactor having a passive cooling system for removing residual heat resulting for fuel decay during reactor shutdown, or heat produced during a mishap. The reactor system is enhanced with sealing means for excluding external air from contact with the liquid metal coolant leaking from the reactor vessel during an accident. The invention also includes a silo structure which resists attack by leaking liquid metal coolant, and an added unique cooling means.

  18. Managing aging in nuclear power plants: Insights from NRC maintenance team inspection reports

    SciTech Connect (OSTI)

    Fresco, A.; Subudhi, M.; Gunther, W.; Grove, E.; Taylor, J.

    1993-12-01

    A plant`s maintenance program is the principal vehicle through which age-related degradation is managed. From 1988 to 1991, the NRC evaluated the maintenance program of every nuclear power plant in the United States. Forty-four out of a total of 67 of the reports issued on these in-depth team inspections were reviewed for insights into the strengths and weaknesses of the programs as related to the need to understand and manage the effects of aging on nuclear plant systems, structures, and components. Relevant information was extracted from these inspection reports and sorted into several categories, including Specific Aging Insights, Preventive Maintenance, Predictive Maintenance and Condition Monitoring, Post Maintenance Testing, Failure Trending, Root Cause Analysis and Usage of Probabilistic Risk Assessment in the Maintenance Process. Specific examples of inspection and monitoring techniques successfully used by utilities to detect degradation due to aging have been identified. The information also was sorted according to systems and components, including: Auxiliary Feedwater, Main Feedwater, High Pressure Injection for both BWRs and PWRs, Service Water, Instrument Air, and Emergency Diesel Generator Air Start Systems, and Emergency Diesel Generators Air Start Systems, emergency diesel generators, electrical components such as switchgear, breakers, relays, and motor control centers, motor operated valves and check valves. This information was compared to insights gained from the Nuclear Plant Aging Research (NPAR) Program. Attributes of plant maintenance programs where the NRC inspectors felt that improvement was needed to properly address the aging issue also are discussed.

  19. Report on aging of nuclear power plant reinforced concrete structures

    SciTech Connect (OSTI)

    Naus, D.J.; Oland, C.B.; Ellingwood, B.R.

    1996-03-01

    The Structural Aging Program provides the US Nuclear Regulatory Commission with potential structural safety issues and acceptance criteria for use in continued service assessments of nuclear power plant safety-related concrete structures. The program was organized under four task areas: Program Management, Materials Property Data Base, Structural Component Assessment/Repair Technology, and Quantitative Methodology for Continued Service Determinations. Under these tasks, over 90 papers and reports were prepared addressing pertinent aspects associated with aging management of nuclear power plant reinforced concrete structures. Contained in this report is a summary of program results in the form of information related to longevity of nuclear power plant reinforced concrete structures, a Structural Materials Information Center presenting data and information on the time variation of concrete materials under the influence of environmental stressors and aging factors, in-service inspection and condition assessments techniques, repair materials and methods, evaluation of nuclear power plant reinforced concrete structures, and a reliability-based methodology for current and future condition assessments. Recommendations for future activities are also provided. 308 refs., 61 figs., 50 tabs.

  20. Managing aging in nuclear power plants: Insights from NRC's Maintenance Team Inspection reports

    SciTech Connect (OSTI)

    Fresco, A.; Subudhi, M.

    1992-01-01

    A plant's maintenance program is the principal vehicle through which age-related degradation is managed. From 1988 to 1991, the NRC evaluated the maintenance program of every nuclear power plant in the United States. Forty-four out of a total of sixty-seven of the reports issued on these in-depth team inspections have been reviewed for insights into the strengths and weaknesses of the programs as related to the need to understand and manage the effects of aging on nuclear plant structures, systems, and components (SSCs). Relevant information has been extracted from these inspection reports sorted into several categories; including Specific Aging Insights, Preventive Maintenance, Predictive Maintenance and Condition Monitoring, Post Maintenance Testing, Failure Trending, Root Cause Analysis and Usage of Probabilistic Risk Assessment in the Maintenance Process. Specific examples of inspection and monitoring techniques successfully used by utilities to detect degradation due to aging have been identified.

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

    SciTech Connect (OSTI)

    G. O. Hayner; E.L. Shaber

    2004-09-01

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

  2. Service experience and reliability improvement: Nuclear, fossil, and petrochemical plants

    SciTech Connect (OSTI)

    Bamford, W.H.; Cipolla, R.C.; Warke, W.R.; Onyewuenyi, O.A.; Bagnoli, D.; Phillips, J.H.; Prager, M.; Becht, C. IV

    1994-01-01

    This publication contains papers presented at the following four symposia conducted at the 1994 Pressure Vessels and Piping Conference in Minneapolis, Minnesota, June 19--23: Service Experience in Nuclear Plants; Risk-Based Inspection and Evaluation; Service Experience in Operating Fossil Power Plants; and Service Experience in Petrochemical Plants. These symposia were sponsored by the Materials and Fabrication and the Design and Analysis Committees of the ASME Pressure Vessels and Piping Division. The objective of these symposia was to disseminate information on issues and degradation that have resulted from the operation of nuclear, fossil, and petrochemical power plants, as well as related reliability issues. Thirty-nine papers have been processed separately for inclusion on the data base.

  3. United States and the Republic of Korea Sign Agreement for Civil Nuclear

    National Nuclear Security Administration (NNSA)

    Cooperation | National Nuclear Security Administration | (NNSA) United States and the Republic of Korea Sign Agreement for Civil Nuclear Cooperation June 15, 2015 Washington, DC - Today Secretary of Energy Ernest J. Moniz and Korean Foreign Minister Yun signed the successor United States - Republic of Korea Agreement for Civil Nuclear Cooperation, or 123 Agreement, as they are referred to in the United States. The United States and the Republic of Korea (ROK) are world leaders in civil

  4. United States and Japan Sign Joint Nuclear Energy Action Plan to Promote

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

    Nuclear Energy Cooperation | Department of Energy Japan Sign Joint Nuclear Energy Action Plan to Promote Nuclear Energy Cooperation United States and Japan Sign Joint Nuclear Energy Action Plan to Promote Nuclear Energy Cooperation April 25, 2007 - 12:36pm Addthis WASHINGTON, DC - United States Department of Energy Secretary Samuel W. Bodman and Japan's Ministers Akira Amari, Bunmei Ibuki, and Taro Aso, this week presented to U.S. President George W. Bush and Japanese Prime Minister Shinzo

  5. United States-Russia Joint Statement on the Results of the Nuclear Energy

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

    and Nuclear Security Working Group Meeting | Department of Energy States-Russia Joint Statement on the Results of the Nuclear Energy and Nuclear Security Working Group Meeting United States-Russia Joint Statement on the Results of the Nuclear Energy and Nuclear Security Working Group Meeting December 10, 2010 - 12:00am Addthis Moscow - Earlier this week, Deputy Secretary of Energy Daniel Poneman, representing the United States government, signed a joint statement with Russia's Director

  6. U.S. Job Creation Due to Nuclear Power Resurgence in The United States — Volumes 1 and 2

    SciTech Connect (OSTI)

    Catherine M. Plowman

    2004-11-01

    The recent revival of interest in nuclear power is causing a reexamination of the role of nuclear power in the United States. This renewed interest has led to questions regarding the capability and capacity of current U.S. industries to support a renewal of nuclear power plant deployment. This study was conducted to provide an initial estimate of jobs to be gained in the U.S. through the repatriation of the nuclear manufacturing industry. In the course of the study, related job categories were also modeled to provide an additional estimate of the potential expansion of existing industries (i.e., plant construction and operations) in conjunction with the repatriation of manufacturing jobs.

  7. kansas city plant | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    kansas city plant KCNSC leader recognized as community role model Allen Brown, senior production scheduler at the Kansas City National Security Campus (KCNSC) in Kansas City, Mo., was recently selected as a 2016 Black Achiever Award recipient. Brown was nominated by the operator of the NSC and his employer, Honeywell Federal Manufacturing & Technologies, for... Cold weather encourages warm hearts in Kansas City Most of us just reach into the closet to pull on a warm coat to shield us from

  8. Aging assessment of large electric motors in nuclear power plants

    SciTech Connect (OSTI)

    Villaran, M.; Subudhi, M.

    1996-03-01

    Large electric motors serve as the prime movers to drive high capacity pumps, fans, compressors, and generators in a variety of nuclear plant systems. This study examined the stressors that cause degradation and aging in large electric motors operating in various plant locations and environments. The operating history of these machines in nuclear plant service was studied by review and analysis of failure reports in the NPRDS and LER databases. This was supplemented by a review of motor designs, and their nuclear and balance of plant applications, in order to characterize the failure mechanisms that cause degradation, aging, and failure in large electric motors. A generic failure modes and effects analysis for large squirrel cage induction motors was performed to identify the degradation and aging mechanisms affecting various components of these large motors, the failure modes that result, and their effects upon the function of the motor. The effects of large motor failures upon the systems in which they are operating, and on the plant as a whole, were analyzed from failure reports in the databases. The effectiveness of the industry`s large motor maintenance programs was assessed based upon the failure reports in the databases and reviews of plant maintenance procedures and programs.

  9. Seismic risk management solution for nuclear power plants

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

    Coleman, Justin; Sabharwall, Piyush

    2014-12-01

    Nuclear power plants should safely operate during normal operations and maintain core-cooling capabilities during off-normal events, including external hazards (such as flooding and earthquakes). Management of external hazards to expectable levels of risk is critical to maintaining nuclear facility and nuclear power plant safety. Seismic risk is determined by convolving the seismic hazard with seismic fragilities (capacity of systems, structures, and components). Seismic isolation (SI) is one protective measure showing promise to minimize seismic risk. Current SI designs (used in commercial industry) reduce horizontal earthquake loads and protect critical infrastructure from the potentially destructive effects of large earthquakes. The benefitmore » of SI application in the nuclear industry is being recognized and SI systems have been proposed in American Society of Civil Engineer Standard 4, ASCE-4, to be released in the winter of 2014, for light water reactors facilities using commercially available technology. The intent of ASCE-4 is to provide criteria for seismic analysis of safety related nuclear structures such that the responses to design basis seismic events, computed in accordance with this standard, will have a small likelihood of being exceeded. The U.S. nuclear industry has not implemented SI to date; a seismic isolation gap analysis meeting was convened on August 19, 2014, to determine progress on implementing SI in the U.S. nuclear industry. The meeting focused on the systems and components that could benefit from SI. As a result, this article highlights the gaps identified at this meeting.« less

  10. Seismic risk management solution for nuclear power plants

    SciTech Connect (OSTI)

    Coleman, Justin; Sabharwall, Piyush

    2014-12-01

    Nuclear power plants should safely operate during normal operations and maintain core-cooling capabilities during off-normal events, including external hazards (such as flooding and earthquakes). Management of external hazards to expectable levels of risk is critical to maintaining nuclear facility and nuclear power plant safety. Seismic risk is determined by convolving the seismic hazard with seismic fragilities (capacity of systems, structures, and components). Seismic isolation (SI) is one protective measure showing promise to minimize seismic risk. Current SI designs (used in commercial industry) reduce horizontal earthquake loads and protect critical infrastructure from the potentially destructive effects of large earthquakes. The benefit of SI application in the nuclear industry is being recognized and SI systems have been proposed in American Society of Civil Engineer Standard 4, ASCE-4, to be released in the winter of 2014, for light water reactors facilities using commercially available technology. The intent of ASCE-4 is to provide criteria for seismic analysis of safety related nuclear structures such that the responses to design basis seismic events, computed in accordance with this standard, will have a small likelihood of being exceeded. The U.S. nuclear industry has not implemented SI to date; a seismic isolation gap analysis meeting was convened on August 19, 2014, to determine progress on implementing SI in the U.S. nuclear industry. The meeting focused on the systems and components that could benefit from SI. As a result, this article highlights the gaps identified at this meeting.

  11. Proceedings of the Third International Workshop on the implementation of ALARA at nuclear power plants

    SciTech Connect (OSTI)

    Khan, T.A.; Roecklein, A.K.

    1995-03-01

    This report contains the papers presented and the discussions that took place at the Third International Workshop on ALARA Implementation at Nuclear Power Plants, held in Hauppauge, Long Island, New York from May 8--11, 1994. The purpose of the workshop was to bring together scientists, engineers, health physicists, regulators, managers and other persons who are involved with occupational dose control and ALARA issues. The countries represented were: Canada, Finland, France, Germany, Japan, Korea, Mexico, the Netherlands, Spain, Sweden, the United Kingdom and the United States. The workshop was organized into twelve sessions and three panel discussions. Individual papers have been cataloged separately.

  12. Energy Praises the Nuclear Regulatory Commission Approval of...

    Office of Environmental Management (EM)

    Praises the Nuclear Regulatory Commission Approval of the First United States Nuclear Plant Site in Over 30 Years Energy Praises the Nuclear Regulatory Commission Approval of the ...

  13. Aging management guideline for commercial nuclear power plants - heat exchangers

    SciTech Connect (OSTI)

    Booker, S.; Lehnert, D.; Daavettila, N.; Palop, E.

    1994-06-01

    This Aging Management Guideline (AMG) describes recommended methods for effective detection and mitigation of age-related degradation mechanisms in commercial nuclear power plant heat exchangers important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein.

  14. Interactive nuclear plant analyzer for VVER-440 reactor

    SciTech Connect (OSTI)

    Shier, W.; Horak, W.; Kennett, R.

    1992-05-01

    This document discusses an interactive nuclear plant analyzer (NPA) which has been developed for a VVER-440, Model 213 reactor for use in the training of plant personnel, the development and verification of plant operating procedures, and in the analysis of various anticipated operational occurrences and accident scenarios. This NPA is operational on an IBM RISC-6000 workstation and utilizes the RELAP5/MOD2 computer code for the calculation of the VVER-440 reactor response to the interactive commands initiated by the NPA operator.

  15. 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

  16. Nuclear physics detector technology applied to plant biology research

    SciTech Connect (OSTI)

    Weisenberger, Andrew G.; Kross, Brian J.; Lee, Seung Joo; McKisson, John E.; Xi, Wenze; Zorn, Carl J.; Howell, Calvin; Crowell, A.S.; Reid, C.D.; Smith, Mark

    2013-08-01

    The ability to detect the emissions of radioactive isotopes through radioactive decay (e.g. beta particles, x-rays and gamma-rays) has been used for over 80 years as a tracer method for studying natural phenomena. More recently a positron emitting radioisotope of carbon: {sup 11}C has been utilized as a {sup 11}CO{sub 2} tracer for plant ecophysiology research. Because of its ease of incorporation into the plant via photosynthesis, the {sup 11}CO{sub 2} radiotracer is a powerful tool for use in plant biology research. Positron emission tomography (PET) imaging has been used to study carbon transport in live plants using {sup 11}CO{sub 2}. Presently there are several groups developing and using new PET instrumentation for plant based studies. Thomas Jefferson National Accelerator Facility (Jefferson Lab) in collaboration with the Duke University Phytotron and the Triangle Universities Nuclear Laboratory (TUNL) is involved in PET detector development for plant imaging utilizing technologies developed for nuclear physics research. The latest developments of the use of a LYSO scintillator based PET detector system for {sup 11}CO{sub 2} tracer studies in plants will be briefly outlined.

  17. An introduction to the design, commissioning and operation of nuclear air cleaning systems for Qinshan Nuclear Power Plant

    SciTech Connect (OSTI)

    Xinliang Chen; Jiangang Qu; Minqi Shi

    1995-02-01

    This paper introduces the design evolution, system schemes and design and construction of main nuclear air cleaning components such as HEPA filter, charcoal adsorber and concrete housing etc. for Qinshan 300MW PWR Nuclear Power Plant (QNPP), the first indigenously designed and constructed nuclear power plant in China. The field test results and in-service test results, since the air cleaning systems were put into operation 18 months ago, are presented and evaluated. These results demonstrate that the design and construction of the air cleaning systems and equipment manufacturing for QNPP are successful and the American codes and standards invoked in design, construction and testing of nuclear air cleaning systems for QNPP are applicable in China. The paper explains that the leakage rate of concrete air cleaning housings can also be assured if sealing measures are taken properly and embedded parts are designed carefully in the penetration areas of the housing and that the uniformity of the airflow distribution upstream the HEPA filters can be achieved generally no matter how inlet and outlet ducts of air cleaning unit are arranged.

  18. Assessment of inservice conditions of safety-related nuclear plant structures

    SciTech Connect (OSTI)

    Ashar, H.; Bagchi, G.

    1995-06-01

    The report is a compilation from a number of sources of information related to the condition Of structures and civil engineering features at operating nuclear power plants in the United States. The most significant information came from the hands-on inspection of the six old plants (licensed prior to 1977) performed by the staff of the Civil Engineering and Geosciences Branch (ECGB) in the Division of Engineering of the Office of Nuclear Reactor Regulation. For the containment structures, most of the information related to the degraded conditions came from the licensees as part of the Licensing Event Report System (10 CFR 50.73), or as part of the requirement under limiting condition of operation of the plant-specific Technical Specifications. Most of the information related to the degradation of other Structures and civil engineering features was extracted from the industry survey, the reported incidents, and the plant visits. The report discusses the condition of the structures and civil engineering features at operating nuclear power plants and provides information that would help detect, alleviate, and correct the degraded conditions of the structures and civil engineering features.

  19. United States-Japan Nuclear Security Working Group Fact Sheet | National

    National Nuclear Security Administration (NNSA)

    Nuclear Security Administration | (NNSA) United States-Japan Nuclear Security Working Group Fact Sheet March 27, 2012 Since the announcement of establishing the U.S.-Japan Nuclear Security Working Group at the U.S.-Japan Summit meeting in November 2010, this Group has successfully fulfilled its responsibility to identify and coordinate tangible outcomes for the 2012 Nuclear Security Summit, including the promotion of robust security for nuclear materials at civilian nuclear facilities and

  20. 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.

  1. Online Monitoring of Plant Assets in the Nuclear Industry

    SciTech Connect (OSTI)

    Nancy Lybeck; Vivek Agarwal; Binh Pham; Richard Rusaw; Randy Bickford

    2013-10-01

    Today’s online monitoring technologies provide opportunities to perform predictive and proactive health management of assets within many different industries, in particular the defense and aerospace industries. The nuclear industry can leverage these technologies to enhance safety, productivity, and reliability of the aging fleet of existing nuclear power plants. The U.S. Department of Energy’s Light Water Reactor Sustainability Program is collaborating with the Electric Power Research Institute’s (EPRI’s) Long-Term Operations program to implement online monitoring in existing nuclear power plants. Proactive online monitoring in the nuclear industry is being explored using EPRI’s Fleet-Wide Prognostic and Health Management (FW-PHM) Suite software, a set of web-based diagnostic and prognostic tools and databases that serves as an integrated health monitoring architecture. This paper focuses on development of asset fault signatures used to assess the health status of generator step-up transformers and emergency diesel generators in nuclear power plants. Asset fault signatures describe the distinctive features based on technical examinations that can be used to detect a specific fault type. Fault signatures are developed based on the results of detailed technical research and on the knowledge and experience of technical experts. The Diagnostic Advisor of the FW-PHM Suite software matches developed fault signatures with operational data to provide early identification of critical faults and troubleshooting advice that could be used to distinguish between faults with similar symptoms. This research is important as it will support the automation of predictive online monitoring techniques in nuclear power plants to diagnose incipient faults, perform proactive maintenance, and estimate the remaining useful life of assets.

  2. The United States Plutonium Balance, 1944-2009 | National Nuclear...

    National Nuclear Security Administration (NNSA)

    Pits The United States Plutonium Balance, 1944-2009 The United States Plutonium Balance, 1944-2009 The United States has released an inventory of its plutonium balances...

  3. 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...

  4. National Nuclear Security Administration United States Department of Energy

    National Nuclear Security Administration (NNSA)

    Atlantic 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 National Security Site NPAC Nonproliferation Policy and Arms Control Program NPT

  5. Natural Gas Processing Plants in the United States: 2010 Update...

    Gasoline and Diesel Fuel Update (EIA)

    7. Natural Gas Processing Plants in Alaska, 2009 Figure 7. Natural Gas Processing Plants in Alaska, 2009...

  6. Requirements for advanced simulation of nuclear reactor and chemicalseparation plants.

    SciTech Connect (OSTI)

    Palmiotti, G.; Cahalan, J.; Pfeiffer, P.; Sofu, T.; Taiwo, T.; Wei,T.; Yacout, A.; Yang, W.; Siegel, A.; Insepov, Z.; Anitescu, M.; Hovland,P.; Pereira, C.; Regalbuto, M.; Copple, J.; Willamson, M.

    2006-12-11

    This report presents requirements for advanced simulation of nuclear reactor and chemical processing plants that are of interest to the Global Nuclear Energy Partnership (GNEP) initiative. Justification for advanced simulation and some examples of grand challenges that will benefit from it are provided. An integrated software tool that has its main components, whenever possible based on first principles, is proposed as possible future approach for dealing with the complex problems linked to the simulation of nuclear reactor and chemical processing plants. The main benefits that are associated with a better integrated simulation have been identified as: a reduction of design margins, a decrease of the number of experiments in support of the design process, a shortening of the developmental design cycle, and a better understanding of the physical phenomena and the related underlying fundamental processes. For each component of the proposed integrated software tool, background information, functional requirements, current tools and approach, and proposed future approaches have been provided. Whenever possible, current uncertainties have been quoted and existing limitations have been presented. Desired target accuracies with associated benefits to the different aspects of the nuclear reactor and chemical processing plants were also given. In many cases the possible gains associated with a better simulation have been identified, quantified, and translated into economical benefits.

  7. Innovative applications of technology for nuclear power plant productivity improvements

    SciTech Connect (OSTI)

    Naser, J. A.

    2012-07-01

    The nuclear power industry in several countries is concerned about the ability to maintain high plant performance levels due to aging and obsolescence, knowledge drain, fewer plant staff, and new requirements and commitments. Current plant operations are labor-intensive due to the vast number of operational and support activities required by commonly used technology in most plants. These concerns increase as plants extend their operating life. In addition, there is the goal to further improve performance while reducing human errors and increasingly focus on reducing operations and maintenance costs. New plants are expected to perform more productively than current plants. In order to achieve and increase high productivity, it is necessary to look at innovative applications of modern technologies and new concepts of operation. The Electric Power Research Inst. is exploring and demonstrating modern technologies that enable cost-effectively maintaining current performance levels and shifts to even higher performance levels, as well as provide tools for high performance in new plants. Several modern technologies being explored can provide multiple benefits for a wide range of applications. Examples of these technologies include simulation, visualization, automation, human cognitive engineering, and information and communications technologies. Some applications using modern technologies are described. (authors)

  8. Sandia tops $6.5 million in United Way donations | National Nuclear...

    National Nuclear Security Administration (NNSA)

    tops 6.5 million in United Way donations | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing...

  9. Indicator system for advanced nuclear plant control complex

    DOE Patents [OSTI]

    Scarola, Kenneth; Jamison, David S.; Manazir, Richard M.; Rescorl, Robert L.; Harmon, Daryl L.

    1993-01-01

    An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system (72) which is nuclear qualified for rapid response to changes in plant parameters and a component control system (64) which together provide a discrete monitoring and control capability at a panel (14-22, 26, 28) in the control room (10). A separate data processing system (70), which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs (84) and a large, overhead integrated process status overview board (24). The discrete indicator and alarm system (72) and the data processing system (70) receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board (24) is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof.

  10. United States -Japan Joint Nuclear Energy Action Plan

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

    -Japan Joint Nuclear Energy Action Plan 1. Introduction 1.1 Background and Objective ... for the contribution of nuclear power to energy security and the global environment. ...

  11. Handbook of nuclear power plant seismic fragilities, Seismic Safety Margins Research Program

    SciTech Connect (OSTI)

    Cover, L.E.; Bohn, M.P.; Campbell, R.D.; Wesley, D.A.

    1983-12-01

    The Seismic Safety Margins Research Program (SSMRP) has a gola to develop a complete fully coupled analysis procedure (including methods and computer codes) for estimating the risk of an earthquake-induced radioactive release from a commercial nuclear power plant. As part of this program, calculations of the seismic risk from a typical commercial nuclear reactor were made. These calculations required a knowledge of the probability of failure (fragility) of safety-related components in the reactor system which actively participate in the hypothesized accident scenarios. This report describes the development of the required fragility relations and the data sources and data reduction techniques upon which they are based. Both building and component fragilities are covered. The building fragilities are for the Zion Unit 1 reactor which was the specific plant used for development of methodology in the program. Some of the component fragilities are site-specific also, but most would be usable for other sites as well.

  12. Development of Advanced Technologies to Reduce Design, Fabrication and Construction for Future Nuclear Power Plants

    SciTech Connect (OSTI)

    O'Connell, J. Michael

    2002-01-01

    OAK-B135 Development of Advanced Technologies to Reduce Design, Fabrication and Construction for Future Nuclear Power Plants

  13. Review of maintenance personnel practices at nuclear power plants

    SciTech Connect (OSTI)

    Chockie, A.D.; Badalamente, R.V.; Hostick, C.J.; Vickroy, S.C.; Bryant, J.L.; Imhoff, C.H.

    1984-05-01

    As part of the Nuclear Regulatory Commission (NRC) sponsored Maintenance Qualifications and Staffing Project, the Pacific Northwest Laboratory (PNL) has conducted a preliminary assessment of nuclear power plant (NPP) maintenance practices. As requested by the NRC, the following areas within the maintenance function were examined: personnel qualifications, maintenance training, overtime, shiftwork and staffing levels. The purpose of the assessment was to identify the primary safety-related problems that required further analysis before specific recommendations can be made on the regulations affecting NPP maintenance operations.

  14. 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.

  15. Infrastructure development assistance modeling for nuclear power plant

    SciTech Connect (OSTI)

    Park, J. H.; Hwang, K.; Park, K. M.; Kim, S. W.; Lee, S. M.

    2012-07-01

    The purpose of this paper is to develop a model, a general frame to be utilized in assisting newcomer countries to start a nuclear power program. A nuclear power plant project involves technical complexity and high level of investment with long duration. Considering newcomers are mostly developing countries that lack the national infrastructure, key infrastructure issues may constitute the principal constraints to the development of a nuclear power program. In this regard, it is important to provide guidance and support to set up an appropriate infrastructure when we help them with the first launch of nuclear power plant project. To date, as a sole nuclear power generation company, KHNP has been invited many times to mentor or assist newcomer countries for their successful start of a nuclear power program since Republic of Korea is an exemplary case of a developing country which began nuclear power program from scratch and became a major world nuclear energy country in a short period of time. Through hosting events organized to aid newcomer countries' initiation of nuclear power projects, difficulties have been recognized. Each event had different contents according to circumstances because they were held as an unstructured and one-off thing. By developing a general model, we can give more adequate and effective aid in an efficient way. In this paper, we created a model to identify necessary infrastructures at the right stage, which was mainly based on a case of Korea. Taking into account the assistance we received from foreign companies and our own efforts for technological self-reliance, we have developed a general time table and specified activities required to do at each stage. From a donor's perspective, we explored various ways to help nuclear infrastructure development including technical support programs, training courses, and participating in IAEA technical cooperation programs on a regular basis. If we further develop the model, the next task would be to

  16. Advanced maintenance, inspection & repair technology for nuclear power plants

    SciTech Connect (OSTI)

    Hinton, B.M.

    1994-12-31

    Maintenance, inspection, and repair technology for nuclear power plants is outlined. The following topics are discussed: technology for reactor systems, reactor refueling bridge, fuel inspection system, fuel shuffling software, fuel reconstitution, CEA/RCCA/CRA inspection, vessel inspection capabilities, CRDM inspection and repair, reactor internals inspection and repair, stud tensioning system, stud/nut cleaning system, EDM machining technology, MI Cable systems, core exit T/C nozzle assemblies, technology for steam generators, genesis manipulator systems, ECT, UT penetrant inspections, steam generator repair and cleaning systems, technology for balance of plant, heat exchangers, piping and weld inspections, and turbogenerators.

  17. U.S. Nuclear Power Plants: Continued Life or Replacement After 60? (released in AEO2010)

    Reports and Publications (EIA)

    2010-01-01

    Nuclear power plants generate approximately 20% of U.S. electricity, and the plants in operation today are often seen as attractive assets in the current environment of uncertainty about future fossil fuel prices, high construction costs for new power plants (particularly nuclear plants), and the potential enactment of greenhouse gas regulations. Existing nuclear power plants have low fuel costs and relatively high power output. However, there is uncertainty about how long they will be allowed to continue operating.

  18. Los Alamos National Laboratory Steam Plant Project | National Nuclear

    National Nuclear Security Administration (NNSA)

    Security Administration | (NNSA) Solicitation Los Alamos National Laboratory Steam Plant Project Welcome to the National Nuclear Security Administration's website for the Los Alamos National Laboratory Site (LANL) M&O Energy Performance Saving Contract Competition. LANL is a premier national security research institution, located 35 miles northwest of Santa Fe, New Mexico, on 36 square miles of Department of Energy-owned property. Its mission is to develop and apply science and

  19. Incidents at nuclear power plants caused by the human factor

    SciTech Connect (OSTI)

    Mashin, V. A.

    2012-09-15

    Psychological analysis of the causes of incorrect actions by personnel is discussed as presented in the report 'Methodological guidelines for analyzing the causes of incidents in the operation of nuclear power plants.' The types of incorrect actions and classification of the root causes of errors by personnel are analyzed. Recommendations are made for improvements in the psychological analysis of causes of incorrect actions by personnel.

  20. Human Factors Considerations in New Nuclear Power Plants: Detailed Analysis.

    SciTech Connect (OSTI)

    OHara,J.; Higgins, J.; Brown, W.; Fink, R.

    2008-02-14

    This Nuclear Regulatory Commission (NRC) sponsored study has identified human-performance issues in new and advanced nuclear power plants. To identify the issues, current industry developments and trends were evaluated in the areas of reactor technology, instrumentation and control technology, human-system integration technology, and human factors engineering (HFE) methods and tools. The issues were organized into seven high-level HFE topic areas: Role of Personnel and Automation, Staffing and Training, Normal Operations Management, Disturbance and Emergency Management, Maintenance and Change Management, Plant Design and Construction, and HFE Methods and Tools. The issues where then prioritized into four categories using a 'Phenomena Identification and Ranking Table' methodology based on evaluations provided by 14 independent subject matter experts. The subject matter experts were knowledgeable in a variety of disciplines. Vendors, utilities, research organizations and regulators all participated. Twenty issues were categorized into the top priority category. This Brookhaven National Laboratory (BNL) technical report provides the detailed methodology, issue analysis, and results. A summary of the results of this study can be found in NUREG/CR-6947. The research performed for this project has identified a large number of human-performance issues for new control stations and new nuclear power plant designs. The information gathered in this project can serve as input to the development of a long-term strategy and plan for addressing human performance in these areas through regulatory research. Addressing human-performance issues will provide the technical basis from which regulatory review guidance can be developed to meet these challenges. The availability of this review guidance will help set clear expectations for how the NRC staff will evaluate new designs, reduce regulatory uncertainty, and provide a well-defined path to new nuclear power plant licensing.

  1. Understanding the nature of nuclear power plant risk

    SciTech Connect (OSTI)

    Denning, R. S.

    2012-07-01

    This paper describes the evolution of understanding of severe accident consequences from the non-mechanistic assumptions of WASH-740 to WASH-1400, NUREG-1150, SOARCA and today in the interpretation of the consequences of the accident at Fukushima. As opposed to the general perception, the radiological human health consequences to members of the Japanese public from the Fukushima accident will be small despite meltdowns at three reactors and loss of containment integrity. In contrast, the radiation-related societal impacts present a substantial additional economic burden on top of the monumental task of economic recovery from the nonnuclear aspects of the earthquake and tsunami damage. The Fukushima accident provides additional evidence that we have mis-characterized the risk of nuclear power plant accidents to ourselves and to the public. The human health risks are extremely small even to people living next door to a nuclear power plant. The principal risk associated with a nuclear power plant accident involves societal impacts: relocation of people, loss of land use, loss of contaminated products, decontamination costs and the need for replacement power. Although two of the three probabilistic safety goals of the NRC address societal risk, the associated quantitative health objectives in reality only address individual human health risk. This paper describes the types of analysis that would address compliance with the societal goals. (authors)

  2. Understanding seismic design criteria for Japanese Nuclear Power Plants

    SciTech Connect (OSTI)

    Park, Y.J.; Hofmayer, C.H.; Costello, J.F.

    1995-04-01

    This paper summarizes the results of recent survey studies on the seismic design practice for nuclear power plants in Japan. The seismic design codes and standards for both nuclear as well as non-nuclear structures have been reviewed and summarized. Some key documents for understanding Japanese seismic design criteria are also listed with brief descriptions. The paper highlights the design criteria to determine the seismic demand and component capacity in comparison with U.S. criteria, the background studies which have led to the current Japanese design criteria, and a survey of current research activities. More detailed technical descriptions are presented on the development of Japanese shear wall equations, design requirements for containment structures, and ductility requirements.

  3. Natural Gas Processing Plants in the United States: 2010 Update...

    Gasoline and Diesel Fuel Update (EIA)

    1. Natural Gas Processing Plants and Production Basins, 2009 Figure 1. Natural Gas Processing Plants and Production Basins, 2009 Source: U.S. Energy Information Administration,...

  4. Natural Gas Processing Plants in the United States: 2010 Update...

    Gasoline and Diesel Fuel Update (EIA)

    2. Processing Plant Capacity and Percent of Total U.S. Capacity, 2009 Figure 2. Processing Plant Capacity and Percent of Total U.S. Capacity, 2009...

  5. Natural Gas Processing Plants in the United States: 2010 Update...

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

    Natural Gas Processing Capacity (Million Cubic Feet per Day) Number of Natural Gas Plants Average Plant Capacity (Million Cubic Feet per Day) Change Between 2004 and 2009 State...

  6. Natural Gas Processing Plants in the United States: 2010 Update...

    Gasoline and Diesel Fuel Update (EIA)

    3. Natural Gas Processing Plants Utilization Rates Based on 2008 Flows Figure 3. Natural Gas Processing Plants Utilization Rates Based on 2008 Flows Note: Average utilization rates...

  7. Natural Gas Processing Plants in the United States: 2010 Update...

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

    5. Natural Gas Processing Plants, Production Basins, and Plays in the Rocky Mountain States and California, 2009 Figure 5. Natural Gas Processing Plants, Production Basins, and...

  8. Natural Gas Processing Plants in the United States: 2010 Update...

    Gasoline and Diesel Fuel Update (EIA)

    6. Natural Gas Processing Plants, Production Basins, and Plays in the Midwestern and Eastern States, 2009 Figure 6. Natural Gas Processing Plants, Production Basins, and Plays in...

  9. Next Generation Nuclear Plant Project 2009 Status Report

    SciTech Connect (OSTI)

    Larry Demick; Jim Kinsey; Keith Perry; Dave Petti

    2010-05-01

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

  10. Inventory of Nonutility Electric Power Plants in the United States

    Reports and Publications (EIA)

    2003-01-01

    Final issue of this report. Provides annual aggregate statistics on generating units operated by nonutilities in the United States and the District of Columbia. Provides a 5-year outlook for generating unit additions and changes.

  11. Land-Use Requirements of Modern Wind Power Plants in the United...

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

    4 August 2009 Land-Use Requirements of Modern Wind Power Plants in the United States Paul Denholm, Maureen Hand, Maddalena Jackson, and Sean Ong National Renewable Energy...

  12. 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.

  13. Aging management guideline for commercial nuclear power plants-pumps

    SciTech Connect (OSTI)

    Booker, S.; Katz, D.; Daavettila, N.; Lehnert, D.

    1994-03-01

    This Aging Management Guideline (AMG) describes recommended methods for effective detection and mitigation of age-related degradation mechanisms in BWR and PWR commercial nuclear power plant pumps important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein.

  14. The Meteorological Monitoring program at a former nuclear weapons plant

    SciTech Connect (OSTI)

    Maxwell, D.R.; Bowen, B.M.

    1994-02-01

    The purpose of the Meteorological Monitoring program at Rocky Flats Plant (RFP) is to provide meteorological information for use in assessing the transport, and diffusion, and deposition of effluent actually or potentially released into the atmosphere by plant operations. Achievement of this objective aids in protecting health and safety of the public, employees, and environment, and directly supports Emergency Response programs at RFP. Meteorological information supports the design of environmental monitoring networks for impact assessments, environmental surveillance activities, remediation activities, and emergency responses. As the mission of the plant changes from production of nuclear weapons parts to environmental cleanup and economic development, smaller releases resulting from remediation activities become more likely. These possible releases could result from airborne fugitive dust, evaporation from collection ponds, or grass fires.

  15. Safety and Nonsafety Communications and Interactions in International Nuclear Power Plants

    SciTech Connect (OSTI)

    Kisner, Roger A; Mullens, James Allen; Wilson, Thomas L; Wood, Richard Thomas; Korsah, Kofi; Qualls, A L; Muhlheim, Michael David; Holcomb, David Eugene; Loebl, Andy

    2007-08-01

    Current industry and NRC guidance documents such as IEEE 7-4.3.2, Reg. Guide 1.152, and IEEE 603 do not sufficiently define a level of detail for evaluating interdivisional communications independence. The NRC seeks to establish criteria for safety systems communications that can be uniformly applied in evaluation of a variety of safety system designs. This report focuses strictly on communication issues related to data sent between safety systems and between safety and nonsafety systems. Further, the report does not provide design guidance for communication systems nor present detailed failure modes and effects analysis (FMEA) results for existing designs. This letter report describes communications between safety and nonsafety systems in nuclear power plants outside the United States. A limited study of international nuclear power plants was conducted to ascertain important communication implementations that might have bearing on systems proposed for licensing in the United States. This report provides that following information: 1.communications types and structures used in a representative set of international nuclear power reactors, and 2.communications issues derived from standards and other source documents relevant to safety and nonsafety communications. Topics that are discussed include the following: communication among redundant safety divisions, communications between safety divisions and nonsafety systems, control of safety equipment from a nonsafety workstation, and connection of nonsafety programming, maintenance, and test equipment to redundant safety divisions during operation. Information for this report was obtained through publicly available sources such as published papers and presentations. No proprietary information is represented.

  16. UNITED STATES ATOMIC ENERGY COMMISSION SPECIAL NUCLEAR MATERIAL...

    Office of Legacy Management (LM)

    STATES ATOMIC ENERGY COMMISSION SPECIAL NUCLEAR MATERIAL LlCENSE pp.o-o 43 Licensee 1. ... Date Sepikmber 30, I.962 -6. Special Nuclear:Material SnrichedtoS I under this ...

  17. UNITED STATES NUCLEAR REGULATORY COMMISSION WAWINQTON, 0. C....

    Office of Legacy Management (LM)

    WAWINQTON, 0. C. ZOSSS Hr. Ray Cooperstein Nuclear Environmental Department ,of Energy ... nuclear reactab:ifot the 0.8. Navy under an Atomic I :;. i,: Snergy Commieeion contract. ...

  18. Fast neutron fluence of yonggwang nuclear unit 1 reactor pressure vessel

    SciTech Connect (OSTI)

    Yoo, C.; Km, B.; Chang, K.; Leeand, S.; Park, J.

    2006-07-01

    The Code of Federal Regulations, Title 10, Part 50, Appendix H, requires that the neutron dosimetry be present to monitor the reactor vessel throughout plant life. The Ex-Vessel Neutron Dosimetry System has been installed for Yonggwang Nuclear Unit 1 after complete withdrawal of all six in-vessel surveillance capsules. This system has been installed in the reactor cavity annulus in order to measure the fast neutron spectrum coming out through the reactor pressure vessel. Cycle specific neutron transport calculations were performed to obtain the energy dependent neutron flux throughout the reactor geometry including dosimetry positions. Comparisons between calculations and measurements were performed for the reaction rates of each dosimetry sensors and results show good agreements. (authors)

  19. A Review of Sensor Calibration Monitoring for Calibration Interval Extension in Nuclear Power Plants

    SciTech Connect (OSTI)

    Coble, Jamie B.; Meyer, Ryan M.; Ramuhalli, Pradeep; Bond, Leonard J.; Hashemian, Hash; Shumaker, Brent; Cummins, Dara

    2012-08-31

    Currently in the United States, periodic sensor recalibration is required for all safety-related sensors, typically occurring at every refueling outage, and it has emerged as a critical path item for shortening outage duration in some plants. Online monitoring can be employed to identify those sensors that require calibration, allowing for calibration of only those sensors that need it. International application of calibration monitoring, such as at the Sizewell B plant in United Kingdom, has shown that sensors may operate for eight years, or longer, within calibration tolerances. This issue is expected to also be important as the United States looks to the next generation of reactor designs (such as small modular reactors and advanced concepts), given the anticipated longer refueling cycles, proposed advanced sensors, and digital instrumentation and control systems. The U.S. Nuclear Regulatory Commission (NRC) accepted the general concept of online monitoring for sensor calibration monitoring in 2000, but no U.S. plants have been granted the necessary license amendment to apply it. This report presents a state-of-the-art assessment of online calibration monitoring in the nuclear power industry, including sensors, calibration practice, and online monitoring algorithms. This assessment identifies key research needs and gaps that prohibit integration of the NRC-approved online calibration monitoring system in the U.S. nuclear industry. Several needs are identified, including the quantification of uncertainty in online calibration assessment; accurate determination of calibration acceptance criteria and quantification of the effect of acceptance criteria variability on system performance; and assessment of the feasibility of using virtual sensor estimates to replace identified faulty sensors in order to extend operation to the next convenient maintenance opportunity. Understanding the degradation of sensors and the impact of this degradation on signals is key to

  20. Joint Statement by the United States and Italy on the 2014 Nuclear Security

    National Nuclear Security Administration (NNSA)

    Summit | National Nuclear Security Administration | (NNSA) Joint Statement by the United States and Italy on the 2014 Nuclear Security Summit March 24, 2014 See a fact sheet here. The White House Office of the Press Secretary Italy and the United States of America are pleased to announce that they have jointly completed the removal of approximately 20 kilograms of excess highly enriched uranium (HEU) and separated plutonium from Italy. At the 2012 Nuclear Security Summit, Italy and the

  1. United States-Republic of Korea (ROK) International Nuclear Energy Research

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

    Initiative (INERI) Annual Steering Committee Meeting | Department of Energy States-Republic of Korea (ROK) International Nuclear Energy Research Initiative (INERI) Annual Steering Committee Meeting United States-Republic of Korea (ROK) International Nuclear Energy Research Initiative (INERI) Annual Steering Committee Meeting January 14, 2015 - 9:33am Addthis United States-Republic of Korea (ROK) International Nuclear Energy Research Initiative (INERI) Annual Steering Committee Meeting On

  2. DOE Summit on Improving the Economics of America's Nuclear Power Plants |

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

    Department of Energy Summit on Improving the Economics of America's Nuclear Power Plants DOE Summit on Improving the Economics of America's Nuclear Power Plants May 19, 2016 - 3:10pm Addthis 202-586-9680 DOE News WASHINGTON - Today, the Energy Department convened a summit on Improving the Economics of America's Nuclear Power Plants. Secretary Moniz, Members of Congress, stakeholders, and experts discussed potential solutions to address the unique challenges facing the nuclear industry in the

  3. United States Department of Energy Nuclear Materials Stewardship

    SciTech Connect (OSTI)

    Newton, J. W.

    2002-02-27

    The Department of Energy launched the Nuclear Materials Stewardship Initiative in January 2000 to accelerate the work of achieving integration and cutting long-term costs associated with the management of the Department's nuclear materials, with the principal focus on excess materials. Management of nuclear materials is a fundamental and enduring responsibility that is essential to meeting the Department's national security, nonproliferation, energy, science, and environmental missions into the distant future. The effective management of nuclear materials is important for a set of reasons: (1) some materials are vital to our national defense; (2) the materials pose physical and security risks; (3) managing them is costly; and (4) costs are likely to extend well into the future. The Department currently manages nuclear materials under eight programs, with offices in 36 different locations. Through the Nuclear Materials Stewardship Initiative, progress was during calendar year 20 00 in achieving better coordination and integration of nuclear materials management responsibilities and in evaluating opportunities to further coordinate and integrate cross-program responsibilities for the treatment, storage, and disposition of excess nuclear materials. During CY 2001 the Departmental approach to nuclear materials stewardship changed consistent with the business processes followed by the new administration. This paper reports on the progress of the Nuclear Materials Stewardship Initiative in evaluating and implementing these opportunities, and the remaining challenges in integrating the long-term management of nuclear materials.

  4. Recent Trends in the Adequacy of Nuclear Plant Decommissioning Funding

    SciTech Connect (OSTI)

    Williams, D. G.

    2002-02-26

    Concerned about the potential cost and sufficiency of funds to decommission the nation's nuclear power plants, the Congress asked the U.S. General Accounting Office (GAO) to assess the adequacy, as of December 31, 1997, of electric utilities'; funds to eventually decommission their plants. GAO's report (GAO/RCED-99-75) on this issue addressed three alternative assumption scenarios--baseline (most likely), optimistic, and pessimistic; and was issued in May 1999. This paper updates GAO's baseline assessment of fund adequacy in 1997, and extends the analysis through 2000. In 2000, we estimate that the present value cost to decommission the nation's nuclear plants is about $35 billion; utility fund balances are about $29 billion. Both our two measures of funding adequacy for utilities are on average not only much above ideal levels, but also overall have greatly improved since 1997. However, certain utilities still show less than ideal fund balances and annual contributions. We suggest that the range of these results among the individual utilities is a more important policy measure to assess the adequacy of decommissioning funding than is the funding adequacy for the industry as a whole.

  5. United States and China Mark 10th Anniversary of Peaceful Uses of Nuclear

    National Nuclear Security Administration (NNSA)

    Technology Joint Coordination Meetings | National Nuclear Security Administration | (NNSA) United States and China Mark 10th Anniversary of Peaceful Uses of Nuclear Technology Joint Coordination Meetings May 14, 2015 CHENGDU, CHINA - On May 6 and 7, the Department of Energy's National Nuclear Security Administration (NNSA) Deputy Administrator for Defense Nuclear Nonproliferation Anne Harrington and China National Energy Administration (NEA) Director General Liu Baohua co-chaired the 10th

  6. Natural Gas Processing Plants in the United States: 2010 Update...

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

    4. Natural Gas Processing Plants, Production Basins, and Plays in the Gulf of Mexico States, 2009 Figure 4. Natural Gas Processing Plants, Production Basins, and Plays in the Gulf...

  7. Pantex makes large donation to United Way | National Nuclear...

    National Nuclear Security Administration (NNSA)

    Tuesday, January 14, 2014 - 4:00pm B&W Pantex General Manager John Woolery, center, presents a B&W corporate donation Friday to the United Way of Amarillo and Canyon. United Way ...

  8. (Safety and reliability of nuclear power plant technology)

    SciTech Connect (OSTI)

    Dickson, T.L.

    1990-10-22

    The traveler attended the 16th MPA Seminar on the Safety and Reliability of Plant Technology with Special Emphasis on Nuclear Technology. The objective of the trip was to gather information and data that could prove useful to the US Nuclear Regulatory Commission (USNRC) sponsored Heavy-Section Steel Irradiation (HSSI) and Heavy-Section Steel Technology (HSST) Programs and to present a paper entitled, Effects of Irradiation on Initiation and Crack-Arrest Toughness of Two High-Copper Welds and on Stainless Steel Cladding. This paper summarizes results from the 5th, 6th, and 7th Irradiation Series of experiments performed within the HSSI Program by the Metals and Ceramics Division at Oak Ridge National Laboratory (ORNL).

  9. Reducing Risk for the Next Generation Nuclear Plant

    SciTech Connect (OSTI)

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

    2010-07-01

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

  10. Online Monitoring of Concrete Structures in Nuclear Power Plants: Interim Report

    SciTech Connect (OSTI)

    Mahadevan, Sankaran; Cai, Guowei; Agarwal, Vivek

    2015-03-01

    The existing fleet of nuclear power plants in the United States have initial operating licenses of 40 years, and many of these plants have applied for and received license extensions. As plant structures, systems, and components age, their useful life—considering both structural integrity and performance—is reduced as a result of deterioration of the materials. Assessment and management of aging concrete structures in nuclear plants require a more systematic approach than simple reliance on existing code-based design margins of safety. Structural health monitoring is required to produce actionable information regarding structural integrity that supports operational and maintenance decisions. The online monitoring of concrete structures project conducted under the Advanced Instrumentation, Information, and Control Technologies Pathway of the Light Water Reactor Sustainability program at Idaho National Laboratory is seeking to develop and demonstrate capabilities for concrete structures health monitoring. Through this research project, several national laboratories and Vanderbilt University propose to develop a framework of research activities for the health monitoring of nuclear power plant concrete structures that includes the integration of four elements—damage modeling, monitoring, data analytics, and uncertainty quantification. This report briefly discusses activities in this project during October-December, 2014. The most significant activity during this period was the organizing of a two-day workshop on research needs in online monitoring of concrete structures, hosted by Vanderbilt University in November 2014. Thirty invitees from academia, industry and government participated in the workshop. The presentations and discussions at the workshop surveyed current activities related to concrete structures deterioration modeling and monitoring, and identified the challenges, knowledge gaps, and opportunities for advancing the state of the art; these

  11. Early Site Permit Demonstration Program: Nuclear Power Plant Siting Database

    Energy Science and Technology Software Center (OSTI)

    1994-01-28

    This database is a repository of comprehensive licensing and technical reviews of siting regulatory processes and acceptance criteria for advanced light water reactor (ALWR) nuclear power plants. The program is designed to be used by applicants for an early site permit or combined construction permit/operating license (10CFRR522, Subparts A and C) as input for the development of the application. The database is a complete, menu-driven, self-contained package that can search and sort the supplied datamore » by topic, keyword, or other input. The software is designed for operation on IBM compatible computers with DOS.« less

  12. Float level switch for a nuclear power plant containment vessel

    DOE Patents [OSTI]

    Powell, J.G.

    1993-11-16

    This invention is a float level switch used to sense rise or drop in water level in a containment vessel of a nuclear power plant during a loss of coolant accident. The essential components of the device are a guide tube, a reed switch inside the guide tube, a float containing a magnetic portion that activates a reed switch, and metal-sheathed, ceramic-insulated conductors connecting the reed switch to a monitoring system outside the containment vessel. Special materials and special sealing techniques prevent failure of components and allow the float level switch to be connected to a monitoring system outside the containment vessel. 1 figures.

  13. Float level switch for a nuclear power plant containment vessel

    DOE Patents [OSTI]

    Powell, James G.

    1993-01-01

    This invention is a float level switch used to sense rise or drop in water level in a containment vessel of a nuclear power plant during a loss of coolant accident. The essential components of the device are a guide tube, a reed switch inside the guide tube, a float containing a magnetic portion that activates a reed switch, and metal-sheathed, ceramic-insulated conductors connecting the reed switch to a monitoring system outside the containment vessel. Special materials and special sealing techniques prevent failure of components and allow the float level switch to be connected to a monitoring system outside the containment vessel.

  14. Vitrification of Polyvinyl Chloride Waste from Korean Nuclear Power Plants

    SciTech Connect (OSTI)

    Sheng, Jiawei [Kyoto University (Japan); Choi, Kwansik [Nuclear Environment Technology Institute (Korea, Republic of); Yang, Kyung-Hwa [Nuclear Environment Technology Institute (Korea, Republic of); Lee, Myung-Chan [Nuclear Environment Technology Institute (Korea, Republic of); Song, Myung-Jae [Nuclear Environment Technology Institute (Korea, Republic of)

    2000-02-15

    Vitrification is considered as an economical and safe treatment technology for low-level radioactive waste (LLW) generated from nuclear power plants (NPPs). Korea is in the process of preparing for its first ever vitrification plant to handle LLW from its NPPs. Polyvinyl chloride (PVC) has the largest volume of dry active wastes and is the main waste stream to treat. Glass formulation development for PVC waste is the focus of study. The minimum additive waste stabilization approach has been utilized in vitrification. It was found that glasses can incorporate a high content of PVC ash (up to 50 wt%), which results in a large volume reduction. A glass frit, KEP-A, was developed to vitrify PVC waste after the optimization of waste loading, melt viscosity, melting temperature, and chemical durability. The KEP-A could satisfactorily vitrify PVC with a waste loading of 30 to 50 wt%. The PVC-frit was tolerant of variations in waste composition.

  15. Next Generation Nuclear Plant Resilient Control System Functional Analysis

    SciTech Connect (OSTI)

    Lynne M. Stevens

    2010-07-01

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

  16. Safeguards Guidance for Designers of Commercial Nuclear Facilities – International Safeguards Requirements for Uranium Enrichment Plants

    SciTech Connect (OSTI)

    Philip Casey Durst; Scott DeMuth; Brent McGinnis; Michael Whitaker; James Morgan

    2010-04-01

    For the past two years, the United States National Nuclear Security Administration, Office of International Regimes and Agreements (NA-243), has sponsored the Safeguards-by-Design Project, through which it is hoped new nuclear facilities will be designed and constructed worldwide more amenable to nuclear safeguards. In the course of this project it was recognized that commercial designer/builders of nuclear facilities are not always aware of, or understand, the relevant domestic and international safeguards requirements, especially the latter as implemented by the International Atomic Energy Agency (IAEA). To help commercial designer/builders better understand these requirements, a report was prepared by the Safeguards-by-Design Project Team that articulated and interpreted the international nuclear safeguards requirements for the initial case of uranium enrichment plants. The following paper summarizes the subject report, the specific requirements, where they originate, and the implications for design and construction. It also briefly summarizes the established best design and operating practices that designer/builder/operators have implemented for currently meeting these requirements. In preparing the subject report, it is recognized that the best practices are continually evolving as the designer/builder/operators and IAEA consider even more effective and efficient means for meeting the safeguards requirements and objectives.

  17. Supporting Our Nation's Nuclear Industry

    ScienceCinema (OSTI)

    Lyons, Peter

    2013-05-29

    On the 60th anniversary of the world's first nuclear power plant to produce electricity, Assistant Secretary for Nuclear Energy Peter Lyons discusses the Energy Department's and the Administration's commitment to promoting a nuclear renaissance in the United States.

  18. Economic Analysis of a Nuclear Reactor Powered High-Temperature Electrolysis Hydrogen Production Plant

    SciTech Connect (OSTI)

    E. A. Harvego; M. G. McKellar; M. S. Sohal; J. E. O'Brien; J. S. Herring

    2008-08-01

    A reference design for a commercial-scale high-temperature electrolysis (HTE) plant for hydrogen production was developed to provide a basis for comparing the HTE concept with other hydrogen production concepts. The reference plant design is driven by a high-temperature helium-cooled nuclear reactor coupled to a direct Brayton power cycle. The reference design reactor power is 600 MWt, with a primary system pressure of 7.0 MPa, and reactor inlet and outlet fluid temperatures of 540°C and 900°C, respectively. The electrolysis unit used to produce hydrogen includes 4,009,177 cells with a per-cell active area of 225 cm2. The optimized design for the reference hydrogen production plant operates at a system pressure of 5.0 MPa, and utilizes an air-sweep system to remove the excess oxygen that is evolved on the anode (oxygen) side of the electrolyzer. The inlet air for the air-sweep system is compressed to the system operating pressure of 5.0 MPa in a four-stage compressor with intercooling. The alternating-current, AC, to direct-current, DC, conversion efficiency is 96%. The overall system thermal-to-hydrogen production efficiency (based on the lower heating value of the produced hydrogen) is 47.12% at a hydrogen production rate of 2.356 kg/s. An economic analysis of this plant was performed using the standardized H2A Analysis Methodology developed by the Department of Energy (DOE) Hydrogen Program, and using realistic financial and cost estimating assumptions. The results of the economic analysis demonstrated that the HTE hydrogen production plant driven by a high-temperature helium-cooled nuclear power plant can deliver hydrogen at a competitive cost. A cost of $3.23/kg of hydrogen was calculated assuming an internal rate of return of 10%.

  19. Natural Gas Processing Plants in the United States: 2010 Update...

    Gasoline and Diesel Fuel Update (EIA)

    National Overview Processing Plant Utilization Data collected for 2009 show that the States with the highest total processing capacity are among the States with the highest average...

  20. Sec. Moniz to Georgia, Energy Department Scheduled to Close on Loan Guarantees to Construct New Nuclear Power Plant Reactors

    Broader source: Energy.gov [DOE]

    Project represents first new nuclear reactors to begin construction in the United States in three decades

  1. Pantex kicks off United Way campaign | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration | (NNSA) kicks off United Way campaign Friday, August 29, 2014 - 1:45pm United Way campaign kickoff event Clarence Rashada holds up a sign expressing Pantexans' support during the United Way campaign kickoff event last week as (from left) Kendra Garcia, Katy Felder and Charles Thomas look on. The four are loaned executives from Pantex sent to support the United Way campaign. This year's theme is "Make it Personal." Each year, Pantex employees pledge hundreds of

  2. Nuclear power plant Generic Aging Lessons Learned (GALL). Appendix B

    SciTech Connect (OSTI)

    Kasza, K.E.; Diercks, D.R.; Holland, J.W.; Choi, S.U.

    1996-12-01

    The purpose of this generic aging lessons learned (GALL) review is to provide a systematic review of plant aging information in order to assess materials and component aging issues related to continued operation and license renewal of operating reactors. Literature on mechanical, structural, and thermal-hydraulic components and systems reviewed consisted of 97 Nuclear Plant Aging Research (NPAR) reports, 23 NRC Generic Letters, 154 Information Notices, 29 Licensee Event Reports (LERs), 4 Bulletins, and 9 Nuclear Management and Resources Council Industry Reports (NUMARC IRs) and literature on electrical components and systems reviewed consisted of 66 NPAR reports, 8 NRC Generic Letters, 111 Information Notices, 53 LERs, 1 Bulletin, and 1 NUMARC IR. More than 550 documents were reviewed. The results of these reviews were systematized using a standardized GALL tabular format and standardized definitions of aging-related degradation mechanisms and effects. The tables are included in volume s 1 and 2 of this report. A computerized data base has also been developed for all review tables and can be used to expedite the search for desired information on structures, components, and relevant aging effects. A survey of the GALL tables reveals that all ongoing significant component aging issues are currently being addressed by the regulatory process. However, the aging of what are termed passive components has been highlighted for continued scrutiny. This report consists of Volume 2, which consists of the GALL literature review tables for the NUMARC Industry Reports reviewed for the report.

  3. The NuGas{sup TM} Concept - Combining a Nuclear Power Plant with a Gas-Fired Plant

    SciTech Connect (OSTI)

    Willson, Paul; Smith, Alistair

    2007-07-01

    Nuclear power plants produce low carbon emissions and stable, low cost electricity. Combined cycle gas-fired power plants are cheap and quick to build and have very flexible operation. If you could combine these two technologies, you could have an ideal base-load power plant. (authors)

  4. Challenges in Determining the Isotopic Mixture for the Fukushima Daiichi Nuclear Power Plant

    SciTech Connect (OSTI)

    Shanks, Arthur; Fournier, Sean; Shanks, Sonoya

    2012-05-01

    As part of the United States response to the Fukushima Daiichi Nuclear Power Plant emergency, the National Nuclear Security Administration (NNSA) Consequence Management (CM) Teams were activated with elements deploying to Japan. The NNSA CM teams faced the urgent need for information regarding the potential radiological doses that citizens of might experience. This paper discusses the challenges and lessons learned associated with the analysis of field collected samples and gamma spectra in an attempt to determine the isotopic mixture present on the ground around the Plant. There were several interesting and surprising lessons to be learned from the sample analysis portion of the response. The paper discusses several elements of the response that were unique to the event occurring in Japan, as well as several elements that would have occurred in a U.S. nuclear reactor event. Sections of this paper address details of the specific analytical challenges faced during the efforts to analyze samples and try to understand the overall release source term.

  5. United States Nuclear Tests, July 1945 through September 1992, December 2000

    SciTech Connect (OSTI)

    U.S. Department of Energy, Nevada Operations Office

    2000-12-01

    This document list chronologically and alphabetically by name all nuclear tests and simultaneous detonations conducted by the United States from July 1945 through September 1992. Revision 15, dated December 2000.

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

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

    Next Generation Nuclear Plant: A Report to Congress Next Generation Nuclear Plant: A Report to Congress The U.S. Department of Energy's (DOE's) Next Generation Nuclear Plant (NGNP) project helps address the President's goals for reducing greenhouse gas emissions and enhancing energy security. The NGNP project was formally established by the Energy Policy Act of 2005 (EPAct 2005), designated as Public Law 109-58, 42 USC 16021, to demonstrate the generation of electricity and/or hydrogen with a

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

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

    Energy Additional Input on Next Generation Nuclear Plant DOE Seeks Additional Input on Next Generation Nuclear Plant April 17, 2008 - 10:49am Addthis WASHINGTON, DC -The U.S. Department of Energy (DOE) today announced it is seeking public and industry input on how to best achieve the goals and meet the requirements for the Next Generation Nuclear Plant (NGNP) demonstration project work at DOE's Idaho National Laboratory. DOE today issued a Request for Information and Expressions of Interest

  8. Analysis of Nuclear Power Plant Operating Costs: A 1995 Update, An

    Reports and Publications (EIA)

    1995-01-01

    This report provides an analysis of nuclear power plant operating costs. The Energy Information Administration published three reports on this subject during the period 1988-1995.

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

    SciTech Connect (OSTI)

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

    2005-09-01

    The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Project is envisioned to demonstrate the following: (1) A full-scale prototype VHTR by about 2021; (2) High-temperature Brayton Cycle electric power production at full scale with a focus on economic performance; (3) Nuclear-assisted production of hydrogen (with about 10% of the heat) with a focus on economic performance; and (4) By test, the exceptional safety capabilities of the advanced gas-cooled reactors. Further, the NGNP program will: (1) Obtain a Nuclear Regulatory Commission (NRC) License to construct and operate the NGNP, this process will provide a basis for future performance based, risk-informed licensing; and (2) Support the development, testing, and prototyping of hydrogen infrastructures. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. The NGNP Materials R&D Program includes the following elements: (1) Developing a specific approach, program plan and other project management tools for

  10. INL Director Discusses the Future for Nuclear Energy in the United States

    ScienceCinema (OSTI)

    Grossenbacher, John

    2013-05-28

    Idaho National Laboratory's Director John Grossenbacher explains that the United States should develop its energy policies based on an assessment of the current events at Japan's Fukushima nuclear reactors and the costs and benefits of providing electricity through various energy sources. For more information about INL's nuclear energy research, visit http://www.facebook.com/idahonationallaboratory.

  11. INL Director Discusses the Future for Nuclear Energy in the United States

    SciTech Connect (OSTI)

    Grossenbacher, John

    2011-01-01

    Idaho National Laboratory's Director John Grossenbacher explains that the United States should develop its energy policies based on an assessment of the current events at Japan's Fukushima nuclear reactors and the costs and benefits of providing electricity through various energy sources. For more information about INL's nuclear energy research, visit http://www.facebook.com/idahonationallaboratory.

  12. United States and South Africa Sign Agreement on Cooperation in Nuclear

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

    Energy Research and Development | Department of Energy South Africa Sign Agreement on Cooperation in Nuclear Energy Research and Development United States and South Africa Sign Agreement on Cooperation in Nuclear Energy Research and Development September 16, 2009 - 12:00am Addthis Vienna, Austria - U.S. Secretary of Energy Steven Chu and South African Minister of Energy Dipuo Peters signed a bilateral Agreement on Cooperation in Research and Development of Nuclear Energy on September 14 in

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

    Office of Legacy Management (LM)

    Nuclear Corp - MO 0-03 FUSRAP Considered Sites Site: UNITED NUCLEAR CORP. (MO.0-03) Eliminated from further consideration under FUSRAP Designated Name: Not Designated Alternate Name: Mallinckrodt Chemical Works Mallinckrodt Nuclear Corporation MO.0-03-1 MO.0-03-2 Location: Hematite , Missouri MO.0-03-1 Evaluation Year: Circa 1987 MO.0-03-3 Site Operations: Commercial fuel fabrication operation. Licensed to reclaim unirradiated enriched uranium from scrap generated in fuel fabrication and fuel

  14. Natural Gas Processing Plants in the United States: 2010 Update...

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

    for about 12 percent of total U.S. capacity. As of 2009, there were a total of 4 plants in the State, with the largest one reporting a capacity of 8.5 Bcf per day. Average...

  15. Natural Gas Processing Plants in the United States: 2010 Update...

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

    has in the past accounted for the majority of natural gas production. Processing plants are especially important in this part of the country because of the amount of NGLs in...

  16. Natural Gas Processing Plants in the United States: 2010 Update...

    Gasoline and Diesel Fuel Update (EIA)

    which saw a 65 percent drop in processing capacity. At the same time, the number of plants in Kansas decreased by four. The decrease was likely the result of falling natural gas...

  17. J.K. Spruce power plant, Unit 1, San Antonio, Texas

    SciTech Connect (OSTI)

    Peltier, R.

    2008-10-15

    CPS Energy's J.K. Spruce power plant, Unit 1 was recently recognised by the EUCG Fossil Productivity Committee as the best performer in the large coal plant category over the 2002-2006 evaluation period. The competition was tough, with more than 80 plants in the running, but Unit 1 emerged as the clear winner by earning top points for high plant reliability and very low nonfuel O & M costs. It meets its environmental goals when burning PRB coal in its tangentially fired furnace with recently upgraded low NOx burners, overfire air and a new combustion control system. A baghouse and wet flue gas desulfurization system clean up combustion products. 3 photos.

  18. 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

  19. Inventory of Electric Utility Power Plants in the United States

    Reports and Publications (EIA)

    2002-01-01

    Final issue of this report. Provides detailed statistics on existing generating units operated by electric utilities as of December 31, 2000, and certain summary statistics about new generators planned for operation by electric utilities during the next 5 years.

  20. Ukraine Loads U.S. Nuclear Fuel into Power Plant as Part of DOE-Ukraine

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

    Nuclear Fuel Qualification Program | Department of Energy Ukraine Loads U.S. Nuclear Fuel into Power Plant as Part of DOE-Ukraine Nuclear Fuel Qualification Program Ukraine Loads U.S. Nuclear Fuel into Power Plant as Part of DOE-Ukraine Nuclear Fuel Qualification Program April 9, 2010 - 12:11pm Addthis KYIV, UKRAINE - Officials from the U.S. Department of Energy's (DOE) Office of Nuclear Energy today (April 8, 2010) participated in a ceremony in Ukraine to mark the insertion of

  1. COMPUTERIZATION OF NUCLEAR POWER PLANT EMERGENCY OPERATING PROCEDURES.

    SciTech Connect (OSTI)

    OHARA,J.M.; HIGGINS,J.; STUBLER,W.

    2000-07-30

    Emergency operating procedures (EOPs) in nuclear plants guide operators in handling significant process disturbances. Historically these procedures have been paper-based. More recently, computer-based procedure (CBP) systems have been developed to improve the usability of EOPs. The objective of this study was to establish human factors review guidance for CBP systems based on a technically valid methodology. First, a characterization of CBPs was developed for describing their key design features, including both procedure representation and functionality. Then, the research on CBPs and related areas was reviewed. This information provided the technical basis on which the guidelines were developed. For some aspects of CBPs the technical basis was insufficient to develop guidance; these aspects were identified as issues to be addressed in future research.

  2. MICROBIAL TRANSFORMATIONS OF RADIONUCLIDES RELEASED FROM NUCLEAR FUEL REPROCESSING PLANTS.

    SciTech Connect (OSTI)

    FRANCIS,A.J.

    2006-10-18

    Microorganisms can affect the stability and mobility of the actinides U, Pu, Cm, Am, Np, and the fission products Tc, I, Cs, Sr, released from nuclear fuel reprocessing plants. Under appropriate conditions, microorganisms can alter the chemical speciation, solubility and sorption properties and thus could increase or decrease the concentrations of radionuclides in solution and the bioavailability. Dissolution or immobilization of radionuclides is brought about by direct enzymatic action or indirect non-enzymatic action of microorganisms. Although the physical, chemical, and geochemical processes affecting dissolution, precipitation, and mobilization of radionuclides have been investigated, we have only limited information on the effects of microbial processes. The mechanisms of microbial transformations of the major and minor actinides and the fission products under aerobic and anaerobic conditions in the presence of electron donors and acceptors are reviewed.

  3. Prognostics and Life Beyond 60 for Nuclear Power Plants

    SciTech Connect (OSTI)

    Leonard J. Bond; Pradeep Ramuhalli; Magdy S. Tawfik; Nancy J. Lybeck

    2011-06-01

    Safe, secure, reliable and sustainable energy supply is vital for advanced and industrialized life styles. To meet growing energy demand there is interest in longer term operation (LTO) for the existing nuclear power plant fleet and enhancing capabilities in new build. There is increasing use of condition based maintenance (CBM) for active components and periodic in service inspection (ISI) for passive systems: there is growing interest in deploying on-line monitoring. Opportunities exist to move beyond monitoring and diagnosis based on pattern recognition and anomaly detection to and prognostics with the ability to provide an estimate of remaining useful life (RUL). The adoption of digital I&C systems provides a framework within which added functionality including on-line monitoring can be deployed, and used to maintain and even potentially enhance safety, while at the same time improving planning and reducing both operations and maintenance costs.

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

    SciTech Connect (OSTI)

    Dr. Mark Schanfein; Philip Casey Durst

    2012-07-01

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

  5. TVA's Shawnee Fossil Plant Unit 6 sets new record for continuous operation

    SciTech Connect (OSTI)

    Peltier, R.

    2008-02-15

    Tennessee Valley Authority's Shawnee Fossil Plant Unit 6 recently set a new 1,093 day continuous run record. The 10 top practices at Shawnee for achieving high performance are discussed.

  6. Nuclear Safety Risk Management in Refueling Outage of Qinshan Nuclear Power Plant

    SciTech Connect (OSTI)

    Meijing Wu; Guozhang Shen

    2006-07-01

    The NPP is used to planning maintenance, in-service inspection, surveillance test, fuel handling and design modification in the refueling outage; the operator response capability will be reduced plus some of the plant systems out of service or loss of power at this time. Based on 8 times refueling outage experiences of the Qinshan NPP, this article provide some good practice and lesson learned for the nuclear safety risk management focus at four safety function areas of Residual Heat Removal Capability, Inventory Control, Power availability and Reactivity control. (authors)

  7. Basis for and practical methods of controlling painting activities at the Sequoyah Nuclear Plant

    SciTech Connect (OSTI)

    Campbell, R.R.

    1997-08-01

    Sequoyah Nuclear Plant (SQN) follows the guidance presented in Regulatory Guide (R.G.) 1.52, {open_quotes}Design, Testing, and Maintenance Criteria for Atmospheric Cleanup System Air Filtration and Adsorption System Units of Light-Water-Cooled Nuclear Power Plants{close_quotes} in protecting its charcoal filter trains from the effects of painting and other chemical releases. SQN, as well as other nuclear facilities around the country, have the problem of how to address the issue of protection of Engineered Safety Feature (ESF) filter systems from degradation due to communication with airborne hydrocarbons (i.e., primarily paints and solvents). R.G. 1.52 (and a similar statement from R.G. 1.140) states in part,{open_quotes}Testing should be performed ... following painting, fire, or chemical release in any ventilation zone communicating with the system...,{close_quotes} and requires that a test be performed upon any kind of painting or chemical release. This is considered overly restrictive if the activity is minor and in a location remote from the charcoal filters. Charcoal filters used in air cleaning systems are required to filter out radioactive iodine from an airstream before its release from the plant to the environment. Charcoal filters will age with time because of their ability to adsorb many different types of material. This aging affects the charcoal by lowering its iodine retention efficiency, and therefore the charcoal needs to be protected from the effects of chemicals such as paint fumes. 14 refs., 3 tabs.

  8. State Nuclear Profiles 2010

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

    and net generation, 2010 Millstone Unit 2, Unit 3 2,103 16,750 100.0 Dominion Nuclear Conn ... "Annual Electric Generator Report," and Form EIA-923, "Power Plant Operations Report." ...

  9. Feasibility Study of Hydrogen Production at Existing Nuclear Power Plants

    SciTech Connect (OSTI)

    Stephen Schey

    2009-07-01

    Cooperative Agreement DE-FC07-06ID14788 was executed between the U.S. Department of Energy, Electric Transportation Applications, and Idaho National Laboratory to investigate the economics of producing hydrogen by electrolysis using electricity generated by nuclear power. The work under this agreement is divided into the following four tasks: Task 1 – Produce Data and Analyses Task 2 – Economic Analysis of Large-Scale Alkaline Electrolysis Task 3 – Commercial-Scale Hydrogen Production Task 4 – Disseminate Data and Analyses. Reports exist on the prospect that utility companies may benefit from having the option to produce electricity or produce hydrogen, depending on market conditions for both. This study advances that discussion in the affirmative by providing data and suggesting further areas of study. While some reports have identified issues related to licensing hydrogen plants with nuclear plants, this study provides more specifics and could be a resource guide for further study and clarifications. At the same time, this report identifies other area of risks and uncertainties associated with hydrogen production on this scale. Suggestions for further study in some of these topics, including water availability, are included in the report. The goals and objectives of the original project description have been met. Lack of industry design for proton exchange membrane electrolysis hydrogen production facilities of this magnitude was a roadblock for a significant period. However, recent design breakthroughs have made costing this facility much more accurate. In fact, the new design information on proton exchange membrane electrolyzers scaled to the 1 kg of hydrogen per second electrolyzer reduced the model costs from $500 to $100 million. Task 1 was delayed when the original electrolyzer failed at the end of its economic life. However, additional valuable information was obtained when the new electrolyzer was installed. Products developed during this study

  10. 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

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

    SciTech Connect (OSTI)

    Blaine Grover

    2010-10-01

    The United States Department of Energys Next Generation Nuclear Plant (NGNP) Program will be irradiating six gas reactor graphite creep experiments in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). The ATR has a long history of irradiation testing in support of reactor development and the INL has been designated as the United States Department of Energys lead laboratory for nuclear energy development. The ATR is one of the worlds premiere test reactors for performing long term, high flux, and/or large volume irradiation test programs. These graphite irradiations are being accomplished to support development of the next generation reactors in the United States. The graphite experiments will be irradiated over the next six to eight years to support development of a graphite irradiation performance data base on the new nuclear grade graphites now available for use in high temperature gas reactors. The goals of the irradiation experiments are to obtain irradiation performance data, including irradiation creep, at different temperatures and loading conditions to support design of the Next Generation Nuclear Plant (NGNP) Very High Temperature Gas Reactor, as well as other future gas reactors. The experiments will each consist of a single capsule that will contain six stacks of graphite specimens, with half of the graphite specimens in each stack under a compressive load, while the other half of the specimens will not be subjected to a compressive load during irradiation. The six stacks will have differing compressive loads applied to the top half of each pair of specimen stacks, while a seventh stack will not have a compressive load. The specimens will be irradiated in an inert sweep gas atmosphere with on-line temperature and compressive load monitoring and control. There will also be the capability of sampling the sweep gas effluent to determine if any oxidation or off-gassing of the specimens occurs during initial start-up of the

  12. An overview of the United States Department of Energy plant lifetime improvement program

    SciTech Connect (OSTI)

    Rosinski, S.T.; Clauss, J.M.; Harrison, D.L.

    1993-08-01

    Today, 109 nuclear power plants provide over 20 percent of the electrical energy generated in the US. The operating license of the first of these plants will expire in the year 2000; one third of the operating licenses will expire by 2010 and the remaining plant licenses are scheduled to expire by 2033. The National Energy Strategy assumes that 70 percent of these plants will continue to operate beyond their current license expiration to assist in ensuring an adequate, diverse, and environmentally acceptable energy supply for economic growth. In order to preserve this energy resource in the US three major tasks must be successfully completed: (1) establishment of the regulations, technical standards, and procedures for the preparation and review of a license renewal application; (2) development, verification, and validation of the various technical criteria and bases for needed monitoring, refurbishment, or replacement of plant equipment; and (3) demonstration of the regulatory process. Since 1985, the US Department of Energy (DOE) has been working with the nuclear industry and the US Nuclear Regulatory Commission (NRC) to establish and demonstrate the option to extend the life of nuclear power plants through the renewal of operating licenses. This paper focuses primarily on DOE`s Plant Lifetime Improvement (PLIM) Program efforts to develop the technical criteria and bases for effective aging management and lifetime improvement for continued operation of nuclear power plants. This paper describes current projects to resolve generic technical issues, including degradation of long-lived components, reactor pressure vessel (RPV) embrittlement management approaches, and analytical methodologies to characterize RPV integrity.

  13. United States Showcases Nuclear Emergency Response Capabilities | National

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

    Offshore Wind Speed at 90 m 10-JAN-2011 1.1.1 Wind Speed at 90 m m/s 11.5 - 12.0 11.0 - 11.5 10.5 - 11.0 10.0 - 10.5 9.5 - 10.0 9.0 - 9.5 8.5 - 9.0 8.0 - 8.5 7.5 - 8.0 7.0 - 7.5 6.5 - 7.0 6.0 - 6.5 0.0 - 6.0 mph 25.7 - 26.8 24.6 - 25.7 23.5 - 24.6 22.4 - 23.5 21.3 - 22.4 20.1 - 21.3 19.0 - 20.1 17.9 - 19.0 16.8 - 17.9 15.7 - 16.8 14.5 - 15.7 13.4 - 14.5 0.0 - 13.4 Nuclear Security Administration | (NNSA)

    Showcases Nuclear Emergency Response Capabilities October 17, 2008 AVILA, Spain -

  14. 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.

  15. Generic implications of ATWS events at the Salem Nuclear Power Plant: generic implications. Vol. 1

    SciTech Connect (OSTI)

    Not Available

    1983-04-01

    This report is the first of two volumes. It documents the work of an interoffice, interdisciplinary NRC Task Force established to determine the generic implications of two anticipated transients without scram (ATWS) at the Salem Nuclear Power Plant, Unit 1 on February 22 and 25, 1983. A second report will document the NRC actions to be taken based on the work of the Task Force. The Task Force was established to address three questions: (1) Is there a need for prompt action for similar equipment in other facilities. (2) Are NRC and its licensees learning the sefety-management lessons, and, (3) How should the priority and content of the ATWS rule be adjusted. A number of short-term actions were taken through Bulletins and an Information Notice. Intermediate-term actions to address the generic issues will be addressed in the separate report and implemented through appropriate regulatory mechanisms.

  16. Transient Testing of Nuclear Fuels and Materials in United States

    SciTech Connect (OSTI)

    Daniel M. Wachs

    2012-12-01

    The US Department of Energy (DOE) has been engaged in an effort to develop and qualify next generation LWR fuel with enhanced performance and safety and reduced waste generation since 2010. This program, which has emphasized collaboration between the DOE, U.S. national laboratories and nuclear industry, was refocused from enhanced performance to enhanced accident tolerance following the events at Fukushima in 2011. Accident tolerant fuels have been specifically described as fuels that, in comparison with standard UO2-Zircaloy, can tolerate loss of active cooling in the reactor core for a considerably longer time period (depending on the LWR system and accident scenario) while maintaining or improving the fuel performance during normal operations, operational transients, as well as design-basis and beyond design-basis events. The program maintains an ambitious goal to insert a lead test assembly (LTA) of the new design into a commercial power reactor by 2022 .

  17. 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.

  18. 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.

  19. 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.

  20. Aging assessment of essential HVAC chillers used in nuclear power plants. Phase 1, Volume 1

    SciTech Connect (OSTI)

    Blahnik, D.E.; Klein, R.F.

    1993-09-01

    The Pacific Northwest Laboratory conducted a Phase I aging assessment of chillers used in the essential safety air-conditioning systems of nuclear power plants. Centrifugal chillers in the 75- to 750-ton refrigeration capacity range are the predominant type used. The chillers used, and air-conditioning systems served, vary in design from plant-to-plant. It is crucial to keep chiller internals very clean and to prevent the leakage of water, air, and other contaminants into the refrigerant containment system. Periodic operation on a weekly or monthly basis is necessary to remove moisture and noncondensable gases that gradually build up inside the chiller. This is especially desirable if a chiller is required to operate only as an emergency standby unit. The primary stressors and aging mechanisms that affect chillers include vibration, excessive temperatures and pressures, thermal cycling, chemical attack, and poor quality cooling water. Aging is accelerated by moisture, non-condensable gases (e.g., air), dirt, and other contamination within the refrigerant containment system, excessive start/stop cycling, and operating below the rated capacity. Aging is also accelerated by corrosion and fouling of the condenser and evaporator tubes. The principal cause of chiller failures is lack of adequate monitoring. Lack of performing scheduled maintenance and human errors also contribute to failures.

  1. Nuclear Energy Research Initiative. Risk Informed Assessment of Regulatory and Design Requirements for Future Nuclear Power Plants. Annual Report

    SciTech Connect (OSTI)

    Ritterbusch, S.E.

    2000-08-01

    The overall goal of this research project is to support innovation in new nuclear power plant designs. This project is examining the implications, for future reactors and future safety regulation, of utilizing a new risk-informed regulatory system as a replacement for the current system. This innovation will be made possible through development of a scientific, highly risk-informed approach for the design and regulation of nuclear power plants. This approach will include the development and.lor confirmation of corresponding regulatory requirements and industry standards. The major impediment to long term competitiveness of new nuclear plants in the U.S. is the capital cost component--which may need to be reduced on the order of 35% to 40% for Advanced Light Water Reactors (ALWRs) such as System 80+ and Advanced Boiling Water Reactor (ABWR). The required cost reduction for an ALWR such as AP600 or AP1000 would be expected to be less. Such reductions in capital cost will require a fundamental reevaluation of the industry standards and regulatory bases under which nuclear plants are designed and licensed. Fortunately, there is now an increasing awareness that many of the existing regulatory requirements and industry standards are not significantly contributing to safety and reliability and, therefore, are unnecessarily adding to nuclear plant costs. Not only does this degrade the economic competitiveness of nuclear energy, it results in unnecessary costs to the American electricity consumer. While addressing these concerns, this research project will be coordinated with current efforts of industry and NRC to develop risk-informed, performance-based regulations that affect the operation of the existing nuclear plants; however, this project will go farther by focusing on the design of new plants.

  2. Expert systems applied to two problems in nuclear power plants

    SciTech Connect (OSTI)

    Kim, K.Y.

    1988-01-01

    This dissertation describes two prototype expert systems applied to two problems in nuclear power plants. One problem is spare parts inventory control, and the other one is radionuclide release from containment during severe accident. The expert system for spare parts inventory control can handle spare parts requirements not only in corrective, preventive, or predictive maintenance, but also when failure rates of components or parts are updated by new data. Costs and benefits of spare parts inventory acquisition are evaluated with qualitative attributes such as spare part availability to provide the inventory manager with an improved basis for decision making. The expert system is implemented with Intelligence/Compiler on an IBM-AT. The other expert system for radionuclide release from containment can estimate magnitude, type, location, and time of release of radioactive materials from containment during a severe accident nearly on line, based on the actual measured physical parameters such as temperature and pressure inside the containment. The expert system has a function to check the validation of sensor data. The expert system is implemented with KEE on a Symbolics LISP machine.

  3. Information Foraging in Nuclear Power Plant Control Rooms

    SciTech Connect (OSTI)

    R.L. Boring

    2011-09-01

    nformation foraging theory articulates the role of the human as an 'informavore' that seeks information and follows optimal foraging strategies (i.e., the 'information scent') to find meaningful information. This paper briefly reviews the findings from information foraging theory outside the nuclear domain and then discusses the types of information foraging strategies operators employ for normal and off-normal operations in the control room. For example, operators may employ a predatory 'wolf' strategy of hunting for information in the face of a plant upset. However, during routine operations, the operators may employ a trapping 'spider' strategy of waiting for relevant indicators to appear. This delineation corresponds to information pull and push strategies, respectively. No studies have been conducted to determine explicitly the characteristics of a control room interface that is optimized for both push and pull information foraging strategies, nor has there been empirical work to validate operator performance when transitioning between push and pull strategies. This paper explores examples of control room operators as wolves vs. spiders and con- cludes by proposing a set of research questions to investigate information foraging in control room settings.

  4. Aging assessment of surge protective devices in nuclear power plants

    SciTech Connect (OSTI)

    Davis, J.F.; Subudhi, M.; Carroll, D.P.

    1996-01-01

    An assessment was performed to determine the effects of aging on the performance and availability of surge protective devices (SPDs), used in electrical power and control systems in nuclear power plants. Although SPDs have not been classified as safety-related, they are risk-important because they can minimize the initiating event frequencies associated with loss of offsite power and reactor trips. Conversely, their failure due to age might cause some of those initiating events, e.g., through short circuit failure modes, or by allowing deterioration of the safety-related component(s) they are protecting from overvoltages, perhaps preventing a reactor trip, from an open circuit failure mode. From the data evaluated during 1980--1994, it was found that failures of surge arresters and suppressers by short circuits were neither a significant risk nor safety concern, and there were no failures of surge suppressers preventing a reactor trip. Simulations, using the ElectroMagnetic Transients Program (EMTP) were performed to determine the adequacy of high voltage surge arresters.

  5. Reassessment of selected factors affecting siting of Nuclear Power Plants

    SciTech Connect (OSTI)

    Davis, R.E.; Hanson, A.L.; Mubayi, V.; Nourbakhsh, H.P.

    1997-02-01

    Brookhaven National Laboratory has performed a series of probabilistic consequence assessment calculations for nuclear reactor siting. This study takes into account recent insights into severe accident source terms and examines consequences in a risk based format consistent with the quantitative health objectives (QHOs) of the NRC`s Safety Goal Policy. Simplified severe accident source terms developed in this study are based on the risk insights of NUREG-1150. The results of the study indicate that both the quantity of radioactivity released in a severe accident as well as the likelihood of a release are lower than those predicted in earlier studies. The accident risks using the simplified source terms are examined at a series of generic plant sites, that vary in population distribution, meteorological conditions, and exclusion area boundary distances. Sensitivity calculations are performed to evaluate the effects of emergency protective action assumptions on the risk of prompt fatality and latent cancers fatality, and population relocation. The study finds that based on the new source terms the prompt and latent fatality risks at all generic sites meet the QHOs of the NRC`s Safety Goal Policy by margins ranging from one to more than three orders of magnitude. 4 refs., 17 figs., 24 tabs.

  6. Interaction of science and diplomacy: Latin American, the United States and nuclear energy, 1945-1955

    SciTech Connect (OSTI)

    Cabral, R.

    1986-01-01

    Nuclear programs in Argentina and Brazil can be traced to August 1945 when their scientific communities articulated responses to the atomic bombings of Japan. They culminated in attempts to develop independent nuclear programs, sharply opposed by the United States, during the nationalist governments of Juan Peron and Getulio Vargas. This dissertation, based on primary sources from the three nations, analyzes these programs and the American responses. Latin America entered the nuclear age attempting to control natural resources, to improve scientific establishments, and to appraise Latin American-United States relations. Despite some clear warnings about nuclear dangers, the new form of energy was seen as the solution to industrial problems, poverty, and outside political interference. International opposition, which may have included nuclear threats from the United States, blocked Argentina's first attempt in 1947. After 1948, Peron wanted a nuclear program for cheap energy and prestige. The qualifications of the Brazilian scientists gave more substance to their program. The program originated in August, 1945, but assumed national proportion with the government of Vargas in 1951. Lack of American cooperation forced Vargas to establish a secret program with Germany. American troops intervened taking over the German equipment already completed. The final collapse came about with Vargas' suicide in August, 1954.

  7. 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.

  8. Applying Human Factors Evaluation and Design Guidance to a Nuclear Power Plant Digital Control System

    SciTech Connect (OSTI)

    Thomas Ulrich; Ronald Boring; William Phoenix; Emily Dehority; Tim Whiting; Jonathan Morrell; Rhett Backstrom

    2012-08-01

    The United States (U.S.) nuclear industry, like similar process control industries, has moved toward upgrading its control rooms. The upgraded control rooms typically feature digital control system (DCS) displays embedded in the panels. These displays gather information from the system and represent that information on a single display surface. In this manner, the DCS combines many previously separate analog indicators and controls into a single digital display, whereby the operators can toggle between multiple windows to monitor and control different aspects of the plant. The design of the DCS depends on the function of the system it monitors, but revolves around presenting the information most germane to an operator at any point in time. DCSs require a carefully designed human system interface. This report centers on redesigning existing DCS displays for an example chemical volume control system (CVCS) at a U.S. nuclear power plant. The crucial nature of the CVCS, which controls coolant levels and boration in the primary system, requires a thorough human factors evaluation of its supporting DCS. The initial digital controls being developed for the DCSs tend to directly mimic the former analog controls. There are, however, unique operator interactions with a digital vs. analog interface, and the differences have not always been carefully factored in the translation of an analog interface to a replacement DCS. To ensure safety, efficiency, and usability of the emerging DCSs, a human factors usability evaluation was conducted on a CVCS DCS currently being used and refined at an existing U.S. nuclear power plant. Subject matter experts from process control engineering, software development, and human factors evaluated the DCS displays to document potential usability issues and propose design recommendations. The evaluation yielded 167 potential usability issues with the DCS. These issues should not be considered operator performance problems but rather opportunities

  9. Recommendations to the NRC on human engineering guidelines for nuclear power plant maintainability

    SciTech Connect (OSTI)

    Badalamente, R.V.; Fecht, B.A.; Blahnik, D.E.; Eklund, J.D.; Hartley, C.S.

    1986-03-01

    This document contains human engineering guidelines which can enhance the maintainability of nuclear power plants. The guidelines have been derived from general human engineering design principles, criteria, and data. The guidelines may be applied to existing plants as well as to plants under construction. They apply to nuclear power plant systems, equipment and facilities, as well as to maintenance tools and equipment. The guidelines are grouped into seven categories: accessibility and workspace, physical environment, loads and forces, maintenance facilities, maintenance tools and equipment, operating equipment design, and information needs. Each chapter of the document details specific maintainability problems encountered at nuclear power plants, the safety impact of these problems, and the specific maintainability design guidelines whose application can serve to avoid these problems in new or existing plants.

  10. United States, Russia Sign Agreement to Further Research and Development Collaboration in Nuclear Energy and Security

    Broader source: Energy.gov [DOE]

    U.S. Secretary of Energy Ernest Moniz and Director General of the Russian Federation State Corporation “Rosatom” Sergey Kirienko today signed the Agreement between the Government of the United States of America and the Government of the Russian Federation on Cooperation in Nuclear- and Energy-Related Scientific Research and Development

  11. A Study of Outage Management Practices at Selected U.S. Nuclear Plants

    SciTech Connect (OSTI)

    Lin, James C.

    2002-07-01

    This paper presents insights gained from a study of the outage management practices at a number of U.S. nuclear plants. The objective of the study was to conduct an in-depth review of the current practices of outage management at these selected plants and identify important factors that have contributed to the recent success of their outage performance. Two BWR-4, three BWR-6, and two 3-loop Westinghouse PWR plants were selected for this survey. The results of this study can be used to formulate outage improvement efforts for nuclear plants in other countries. (author)

  12. Proposal for broader United States-Russian transparency of nuclear arms reductions

    SciTech Connect (OSTI)

    Percival, C.M.; Ingle, T.H.; Bieniawski, A.J.

    1995-07-01

    During the January 1994 Summit Presidents Clinton and Yeltsin agreed on the goal of ensuring the ``transparency and irreversibility`` of the nuclear arms reduction process. As a result, negotiations are presently underway between the United States Government and the Russian Federation to confirm the stockpiles of plutonium and highly enriched uranium removed from nuclear weapons. In December 1994 the United States presented a paper to the Russian Federation proposing additional measures to provide broader transparency of nuclear arms reduction. The US Department of Energy is studying the implementation of these broader transparency measures at appropriate DOE facilities. The results of the studies include draft protocols for implementation, assessments of the implementation procedures and the impacts on the facilities and estimates of the cost to implement these measures at various facilities.

  13. Inventory of power plants in the United States 1989. [Contains glossary

    SciTech Connect (OSTI)

    Not Available

    1990-09-21

    This document is prepared annually by the Electric Power Division, Office of Coal, Nuclear, Electric and Alternate Fuels, Energy Information Administration (EIA), US Department of Energy (DOE). The purpose of this publication is to provide year-end statistics about electric generating units in operation and to provide a 10-year outlook of future generating unit additions by electric utilities in the United States (the 50 states and the District of Columbia). Data summarized in this report are useful to a wide audience including Congress, federal and state agencies, the electric utility industry, and the general public. The data presented in this report were assembled and published by the EIA, to fulfill its data collection and dissemination responsibilities as specified in the Federal Energy Administration Act of 1974 (Public Law 93-275) as amended. The report is organized into the following chapters: Summary Statistics; Operable Electric Generating Units; and Projected Electric Generating Unit Additions.

  14. Probabilistic methods in seismic risk assessment for nuclear power plants: proceedings

    SciTech Connect (OSTI)

    Not Available

    1983-01-01

    The state-of-the-art in seismic risk analysis applied to the design and siting of nuclear power plants was addressed in this meeting. Presentations were entered individually into the date base. (ACR)

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

    SciTech Connect (OSTI)

    John Collins

    2009-01-01

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

  16. EM Shares Waste Isolation Pilot Plant Lessons Learned with Nuclear Energy Agency

    Broader source: Energy.gov [DOE]

    PARIS – EM officials shared lessons learned from the 2014 Waste Isolation Pilot Plant underground fire and radiological release with the Nuclear Energy Agency (NEA) Division of Radiological Protection and Radioactive Waste Management in a seminar in Paris recently.

  17. Coupling Ocean Thermal Energy Conversion technology (OTEC) with nuclear power plants

    SciTech Connect (OSTI)

    Goldstein, M.K.; Rezachek, D.; Chen, C.S.

    1981-01-01

    The prospects of utilizing an OTEC Related Bottoming Cycle to recover waste heat generated by a large nuclear (or fossil) power plant are examined. With such improvements, OTEC can become a major energy contributor. 12 refs.

  18. An artificial neutral network fault-diagnostic adviser for a nuclear power plant with error prediction

    SciTech Connect (OSTI)

    Kim, Keehoon

    1992-12-31

    This thesis is part of an ongoing project at Iowa State University to develop ANN bases fault diagnostic systems to detect and classify operational transients at nuclear power plants.

  19. An artificial neutral network fault-diagnostic adviser for a nuclear power plant with error prediction

    SciTech Connect (OSTI)

    Kim, Keehoon.

    1992-01-01

    This thesis is part of an ongoing project at Iowa State University to develop ANN bases fault diagnostic systems to detect and classify operational transients at nuclear power plants.

  20. EIS-0225: Continued Operation of the Pantex Plant and Associated Storage of Nuclear Weapon Components

    Broader source: Energy.gov [DOE]

    This EIS evaluates the potential environemental impact of a proposal to continue operation of the Pantex Plant and associated storage of nuclear weapon components. Alternatives considered include: ...

  1. DC power transmission from the Leningradskaya Nuclear Power Plant to Vyborg

    SciTech Connect (OSTI)

    Koshcheev, L. A.; Shul'ginov, N. G.

    2011-05-15

    DC power transmission from the Leningradskaya Nuclear Power Plant (LAES) to city of Vyborg is proposed. This will provide a comprehensive solution to several important problems in the development and control of the unified power system (EES) of Russia.

  2. Integration of Biorefineries and Nuclear Cogeneration Power Plants - A Preliminary Analysis

    SciTech Connect (OSTI)

    Greene, Sherrell R; Flanagan, George F; Borole, Abhijeet P

    2009-03-01

    Biomass-based ethanol and nuclear power are two viable elements in the path to U.S. energy independence. Numerous studies suggest nuclear power could provide a practical carbon-free heat source alternative for the production of biomass-based ethanol. In order for this coupling to occur, it is necessary to examine the interfacial requirements of both nuclear power plants and bioethanol refineries. This report describes the proposed characteristics of a small cogeneration nuclear power plant, a biochemical process-based cellulosic bioethanol refinery, and a thermochemical process-based cellulosic biorefinery. Systemic and interfacial issues relating to the co-location of either type of bioethanol facility with a nuclear power plant are presented and discussed. Results indicate future co-location efforts will require a new optimized energy strategy focused on overcoming the interfacial challenges identified in the report.

  3. Lessons Learned on University Education Programs of Chemical Engineering Principles for Nuclear Plant Operations - 13588

    SciTech Connect (OSTI)

    Ryu, Jun-hyung

    2013-07-01

    University education aims to supply qualified human resources for industries. In complex large scale engineering systems such as nuclear power plants, the importance of qualified human resources cannot be underestimated. The corresponding education program should involve many topics systematically. Recently a nuclear engineering program has been initiated in Dongguk University, South Korea. The current education program focuses on undergraduate level nuclear engineering students. Our main objective is to provide industries fresh engineers with the understanding on the interconnection of local parts and the entire systems of nuclear power plants and the associated systems. From the experience there is a huge opportunity for chemical engineering disciple in the context of giving macroscopic overview on nuclear power plant and waste treatment management by strengthening the analyzing capability of fundamental situations. (authors)

  4. CONFIRMATORY SURVEY RESULTS FOR PORTIONS OF THE MATERIALS AND EQUIPMENT FROM UNITS 1 AND 2 AT THE HUMBOLDT BAY POWER PLANT, EUREKA, CALIFORNIA

    SciTech Connect (OSTI)

    W.C. Adams

    2011-04-01

    The Pacific Gas & Electric Company (PG&E) operated the Humboldt Bay Power Plant (HBPP) Unit 3 nuclear reactor near Eureka, California under Atomic Energy Commission (AEC) provisional license number DPR-7. HBPP Unit 3 achieved initial criticality in February 1963 and began commercial operations in August 1963. Unit 3 was a natural circulation boiling water reactor with a direct-cycle design. This design eliminated the need for heat transfer loops and large containment structures. Also, the pressure suppression containment design permitted below-ground construction. Stainless steel fuel claddings were used from startup until cladding failures resulted in plant system contamination—zircaloy-clad fuel was used exclusively starting in 1965 eliminating cladding-related contamination. A number of spills and gaseous releases were reported during operations resulting in a range of mitigative activities (see ESI 2008 for details).

  5. Medium-Voltage Cables in Nuclear Plant Applications - State of Industry and Conditioning Monitoring

    SciTech Connect (OSTI)

    J.M. Braun

    2003-10-01

    OAK-B135 This report reviews the types of medium-voltage (MV) cables in use in nuclear power plants and the techniques that are currently available to assess the condition of MV cable systems. The project identified the types of cable systems in nuclear plants and their operating conditions and then assessed the aging and failure mechanisms of these cables and suitable diagnostic test techniques. In addition, ways to alleviate conditions that cause the most severe aging were identified.

  6. Study of the potential uses of the Barnwell Nuclear Fuel Plant (BNFP). Final report

    SciTech Connect (OSTI)

    Not Available

    1980-03-25

    The purpose of this study is to provide an evaluation of possible international and domestic uses for the Barnwell Nuclear Fuel Plant, located in South Carolina, at the conclusion of the International Nuclear Fuel Cycle Evaluation. Four generic categories of use options for the Barnwell plant have been considered: storage of spent LWR fuel; reprocessing of LWR spent fuel; safeguards development and training; and non-use. Chapters are devoted to institutional options and integrated institutional-use options.

  7. Cooling Water Issues and Opportunities at U.S. Nuclear Power Plants,

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

    December 2010 | Department of Energy Cooling Water Issues and Opportunities at U.S. Nuclear Power Plants, December 2010 Cooling Water Issues and Opportunities at U.S. Nuclear Power Plants, December 2010 Energy and water are both essential to sustainable development and economic productivity. Ample supplies of water are essential to energy production, and water management is dependent on ample supplies of energy for water treatment and transportation. The critical nexus between energy and

  8. Risk-informed assessment of regulatory and design requirements for future nuclear power plants. Annual report

    SciTech Connect (OSTI)

    2000-08-01

    OAK B188 Risk-informed assessment of regulatory and design requirements for future nuclear power plants. Annual report. The overall goal of this research project is to support innovation in new nuclear power plant designs. This project is examining the implications, for future reactors and future safety regulation, of utilizing a new risk-informed regulatory system as a replacement for the current system. This innovation will be made possible through development of a scientific, highly risk-formed approach for the design and regulation of nuclear power plants. This approach will include the development and/or confirmation of corresponding regulatory requirements and industry standards. The major impediment to long term competitiveness of new nuclear plants in the U.S. is the capital cost component--which may need to be reduced on the order of 35% to 40% for Advanced Light Water Reactors (ALWRS) such as System 80+ and Advanced Boiling Water Reactor (ABWR). The required cost reduction for an ALWR such as AP600 or AP1000 would be expected to be less. Such reductions in capital cost will require a fundamental reevaluation of the industry standards and regulatory bases under which nuclear plants are designed and licensed. Fortunately, there is now an increasing awareness that many of the existing regulatory requirements and industry standards are not significantly contributing to safety and reliability and, therefore, are unnecessarily adding to nuclear plant costs. Not only does this degrade the economic competitiveness of nuclear energy, it results in unnecessary costs to the American electricity consumer. While addressing these concerns, this research project will be coordinated with current efforts of industry and NRC to develop risk-informed, performance-based regulations that affect the operation of the existing nuclear plants; however, this project will go further by focusing on the design of new plants.

  9. Inventory of power plants in the United States as of January 1, 1998

    SciTech Connect (OSTI)

    1998-12-01

    The Inventory of Power Plants in the United States provides annual statistics on generating units operated by electric utilities in the US (the 50 States and the District of Columbia). Statistics presented in this report reflect the status of generating units as of January 1, 1998. The publication also provides a 10-year outlook for generating unit additions and generating unit changes. This report is prepared annually by the Energy Information Administration (EIA). Data summarized in this report are useful to a wide audience. This is a report of electric utility data; in cases where summary data or nonconfidential data of nonutilities are presented, it is specifically noted as nonutility data. 19 figs., 36 tabs.

  10. 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.

  11. Base-Load and Peak Electricity from a Combined Nuclear Heat and Fossil Combined-Cycle Plant

    SciTech Connect (OSTI)

    Conklin, James C.; Forsberg, Charles W.

    2007-07-01

    A combined-cycle power plant is proposed that uses heat from a high-temperature reactor and fossil fuel to meet base-load and peak electrical demands. The high temperature gas turbine produces shaft power to turn an electric generator. The hot exhaust is then fed to a heat recovery steam generator (HRSG) that provides steam to a steam turbine for added electrical power production. A simplified computational model of the thermal power conversion system was developed in order to parametrically investigate two different steady-state operation conditions: base load nuclear heat only from an Advanced High Temperature Reactor (AHTR), and combined nuclear heat with fossil heat to increase the turbine inlet temperature. These two cases bracket the expected range of power levels, where any intermediate power level can result during electrical load following. The computed results indicate that combined nuclear-fossil systems have the potential to offer both low-cost base-load electricity and lower-cost peak power relative to the existing combination of base-load nuclear plants and separate fossil-fired peak-electricity production units. In addition, electric grid stability, reduced greenhouse gases, and operational flexibility can also result with using the conventional technology presented here for the thermal power conversion system coupled with the AHTR. (authors)

  12. Base-Load and Peak Electricity from a Combined Nuclear Heat and Fossil Combined-Cycle Plant

    SciTech Connect (OSTI)

    Conklin, Jim; Forsberg, Charles W

    2007-01-01

    A combined-cycle power plant is proposed that uses heat from a high-temperature reactor and fossil fuel to meet base-load and peak electrical demands. The high-temperature gas turbine produces shaft power to turn an electric generator. The hot exhaust is then fed to a heat recovery steam generator (HRSG) that provides steam to a steam turbine for added electrical power production. A simplified computational model of the thermal power conversion system was developed in order to parametrically investigate two different steady-state operation conditions: base load nuclear heat only from an Advanced High Temperature Reactor (AHTR), and combined nuclear heat with fossil heat to increase the turbine inlet temperature. These two cases bracket the expected range of power levels, where any intermediate power level can result during electrical load following. The computed results indicate that combined nuclear-fossil systems have the potential to offer both low-cost base-load electricity and lower-cost peak power relative to the existing combination of base-load nuclear plants and separate fossil-fired peak-electricity production units. In addition, electric grid stability, reduced greenhouse gases, and operational flexibility can also result with using the conventional technology presented here for the thermal power conversion system coupled with the AHTR.

  13. New Technologies for Repairing Aging Cables in Nuclear Power Plants

    SciTech Connect (OSTI)

    Simmons, Kevin L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Fifield, Leonard S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Westman, Matthew P. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2013-09-11

    The goal of this project is to demonstrate a proof-of-concept for a technique to repair aging cables that have been subjected to degradation associated with long-term thermal and radiation exposure in nuclear power plants. The physical degradation of the aging cables manifests itself primarily as cracking and increased brittleness of the polymeric electrical insulation. Therefore, the proposed cable-repair concept comprises development of techniques to impart a softening agent within the deteriorated polymer insulation jacket so as to regain the ability of the insulation to stretch without failing and possibly to heal existing cracks in the insulation. Our approach is to use commercially available ethylene-propylene rubber (EPR) as the relevant test material, demonstrate the adsorption of chemical treatments in the EPR and quantify changes in resulting physical and mechanical properties. EPR cable samples have been thermally treated in air to produce specimens corresponding to the full range of cable age-performance points from new (>350% elongation at break) to end-of-life (<50% elongation at break). The current focus is on two chemical treatments selected as candidates for restoring age-related cable elasticity loss: a rubber plasticizer and a reactive silane molecule. EPR specimens of 200, 150, 100, and 50% elongation at break have been soaked in the candidate chemical treatments and the kinetics of chemical uptake, measured by change in mass of the samples, has been determined. Mechanical properties as a function of aging and chemical treatment have been measured including ultimate tensile strength, tensile modulus at 50% strain, elongation at break, and storage modulus. Dimensional changes with treatment and changes in glass transition temperature were also investigated. These ongoing experiments are expected to provide insight into the physical-chemical nature of the effect of thermal degradation on EPR rejuvenation limits and to advance novel methods for

  14. Risk Informed Assessment of Regulatory and Design Requirements for Future Nuclear Power Plants - Final Technical Report

    SciTech Connect (OSTI)

    Ritterbusch, Stanley; Golay, Michael; Duran, Felicia; Galyean, William; Gupta, Abhinav; Dimitrijevic, Vesna; Malsch, Marty

    2003-01-29

    OAK B188 Summary of methods proposed for risk informing the design and regulation of future nuclear power plants. All elements of the historical design and regulation process are preserved, but the methods proposed for new plants use probabilistic risk assessment methods as the primary decision making tool.

  15. Assessement of Codes and Standards Applicable to a Hydrogen Production Plant Coupled to a Nuclear Reactor

    SciTech Connect (OSTI)

    M. J. Russell

    2006-06-01

    This is an assessment of codes and standards applicable to a hydrogen production plant to be coupled to a nuclear reactor. The result of the assessment is a list of codes and standards that are expected to be applicable to the plant during its design and construction.

  16. Dynamic alarm presentation in a nuclear plant control room

    DOE Patents [OSTI]

    Kenneth, Scarola; Jamison, David S.; Manazir, Richard M.; Rescorl, Robert L.; Harmon, Daryl L.

    1994-01-01

    The alarm activation set point and priority for a given, spatially fixed alarm tile can vary depending in part on the mode of plant operation.

  17. Central and Eastern United States (CEUS) Seismic Source Characterization (SSC) for Nuclear Facilities Project

    SciTech Connect (OSTI)

    Kevin J. Coppersmith; Lawrence A. Salomone; Chris W. Fuller; Laura L. Glaser; Kathryn L. Hanson; Ross D. Hartleb; William R. Lettis; Scott C. Lindvall; Stephen M. McDuffie; Robin K. McGuire; Gerry L. Stirewalt; Gabriel R. Toro; Robert R. Youngs; David L. Slayter; Serkan B. Bozkurt; Randolph J. Cumbest; Valentina Montaldo Falero; Roseanne C. Perman' Allison M. Shumway; Frank H. Syms; Martitia P. Tuttle

    2012-01-31

    This report describes a new seismic source characterization (SSC) model for the Central and Eastern United States (CEUS). It will replace the Seismic Hazard Methodology for the Central and Eastern United States, EPRI Report NP-4726 (July 1986) and the Seismic Hazard Characterization of 69 Nuclear Plant Sites East of the Rocky Mountains, Lawrence Livermore National Laboratory Model, (Bernreuter et al., 1989). The objective of the CEUS SSC Project is to develop a new seismic source model for the CEUS using a Senior Seismic Hazard Analysis Committee (SSHAC) Level 3 assessment process. The goal of the SSHAC process is to represent the center, body, and range of technically defensible interpretations of the available data, models, and methods. Input to a probabilistic seismic hazard analysis (PSHA) consists of both seismic source characterization and ground motion characterization. These two components are used to calculate probabilistic hazard results (or seismic hazard curves) at a particular site. This report provides a new seismic source model. Results and Findings The product of this report is a regional CEUS SSC model. This model includes consideration of an updated database, full assessment and incorporation of uncertainties, and the range of diverse technical interpretations from the larger technical community. The SSC model will be widely applicable to the entire CEUS, so this project uses a ground motion model that includes generic variations to allow for a range of representative site conditions (deep soil, shallow soil, hard rock). Hazard and sensitivity calculations were conducted at seven test sites representative of different CEUS hazard environments. Challenges and Objectives The regional CEUS SSC model will be of value to readers who are involved in PSHA work, and who wish to use an updated SSC model. This model is based on a comprehensive and traceable process, in accordance with SSHAC guidelines in NUREG/CR-6372, Recommendations for Probabilistic

  18. Prognostics Health Management and Life Beyond 60 for Nuclear Power Plants

    SciTech Connect (OSTI)

    Ramuhalli, Pradeep; Coble, Jamie B.; Meyer, Ryan M.; Bond, Leonard J.

    2013-12-01

    There is growing interest in longer-term operation of the current US nuclear power plant fleet. This paper will present an overview of prognostic health management (PHM) technologies that could play a role in the safe and effective operation of nuclear power plants during extended life. A case study in prognostics for materials degradation assessment, using laboratory-scale measurements, is briefly discussed, and technical gaps that need to be addressed prior to PHM system deployment for nuclear power life extension are presented.

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

    SciTech Connect (OSTI)

    Redding, J.R.

    1994-12-31

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

  20. Incentive regulation of investor-owned nuclear power plants by public utility regulators. Revision 1

    SciTech Connect (OSTI)

    McKinney, M.D.; Seely, H.E.; Merritt, C.R.; Baker, D.C.

    1995-04-01

    The US Nuclear Regulatory Commission (NRC) periodically surveys the Federal Energy Regulatory Commission (FERC) and state regulatory commissions that regulate utility owners of nuclear power plants. The NRC is interested in identifying states that have established economic or performance incentive programs applicable to nuclear power plants, how the programs are being implemented, and in determining the financial impact of the programs on the utilities. The NRC interest stems from the fact that such programs have the potential to adversely affect the safety of nuclear power plants. The current report is an update of NUREG/CR-5975, Incentive Regulation of Investor-Owned Nuclear Power Plants by Public Utility Regulators, published in January 1993. The information in this report was obtained from interviews conducted with each state regulatory agency that administers an incentive program and each utility that owns at least 10% of an affected nuclear power plant. The agreements, orders, and settlements that form the basis for each incentive program were reviewed as required. The interviews and supporting documentation form the basis for the individual state reports describing the structure and financial impact of each incentive program.

  1. Renewing the licenses of US nuclear plants: An assessment of the socioeconomic impacts

    SciTech Connect (OSTI)

    Schweitzer, M.; Saulsbury, J.W. ); Schexnayder, S.M. )

    1993-01-01

    In recent years, increased national attention has been focused on the potential effects of renewing, or not renewing, the licenses of nuclear power plants as the oldest of them approach the end of the 40-year operating period allowed by their original licenses. As part of a larger study for the US Nuclear Regulatory commission (NRC), the authors conducted an assessment of the potential socioeconomic impacts to those communities throughout the country in which nuclear power plants are located and which, therefore, are most directly affected by renewal of nuclear power plant licenses. This paper focuses on six key issues that are traditionally considered essential in the assessment of social impacts: Population; housing; tax payments; local public services; land use and development; and economic structure.

  2. Secretary Chu's Remarks at Vogtle Nuclear Power Plant -- As Prepared...

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

    60 years ago, scientists in Arco, Idaho successfully used nuclear energy to power four light bulbs. They laid the groundwork for decades of clean electricity and put the U.S. at...

  3. Security by Design in the United States: Fact Sheet | National Nuclear

    National Nuclear Security Administration (NNSA)

    Security Administration | (NNSA) Security by Design in the United States: Fact Sheet March 23, 2012 Since the events of September 11, 2001, security requirements for nuclear facilities have increased primarily due to changes in the Design Basis Threat against which planned facilities are designed and existing physical security systems are tested. As a result, security costs and operational impacts have increased significantly because facilities originally were not designed with intrinsic

  4. Company, for the United States Department of Energy's National Nuclear Security

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

    is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000. Small Business Advocate Sandia National Laboratories 24 th Annual Briefing for Industry 2010 August 18, 2010 Small Business Utilization Department Small Business Program Don Devoti, Manager Small Business Utilization Sandia is a multiprogram laboratory operated by Sandia Corporation, a

  5. Concentration of Actinides in Plant Mounds at Safety Test Nuclear Sites in Nevada

    SciTech Connect (OSTI)

    David S. Shafer; Jenna Gommes

    2008-09-15

    Plant mounds or blow-sand mounds are accumulations of soil particles and plant debris around large shrubs and are common features in deserts in the southwestern United States. Believed to be an important factor in their formation, the shrubs create surface roughness that causes wind-suspended particles to be deposited and resist further suspension. Shrub mounds occur in some plant communities on the Nevada Test Site, the Nevada Test and Training Range (NTTR), and Tonopah Test Range (TTR), including areas of surface soil contamination from past nuclear testing. In the 1970s as part of early studies to understand properties of actinides in the environment, the Nevada Applied Ecology Group (NAEG) examined the accumulation of isotopes of Pu, {sup 241}Am, and U in plant mounds at safety test sites. The NAEG studies found concentrations of these contaminants to be greater in shrub mounds than in the surrounding areas of desert pavement. For example, at Project 57 on the NTTR, it was estimated that 15 percent of the radionuclide inventory of the site was associated with shrub mounds, which accounted for 17 percent of the surface area of the site, a ratio of inventory to area of 0.85. At Clean Slate III at the TTR, 29 percent of the inventory was associated with approximately 32 percent of the site covered by shrub mounds, a ratio of 0.91. While the total inventory of radionuclides in intershrub areas was greater, the ratio of radionuclide inventory to area was 0.40 and 0.38, respectively, at the two sites. The comparison between the shrub mounds and adjacent desert pavement areas was made for only the top 5 cm since radionuclides at safety test sites are concentrated in the top 5 cm of intershrub areas. Not accounting for radionuclides associated with the shrub mounds would cause the inventory of contaminants and potential exposure to be underestimated. As part of its Environmental Restoration Soils Subproject, the U.S. Department of Energy (DOE), National Nuclear

  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

  7. System Evaluation and Economic Analysis of a Nuclear Reactor Powered High-Temperature Electrolysis Hydrogen-Production Plant

    SciTech Connect (OSTI)

    E. A. Harvego; M. G. McKellar; M. S. Sohal; J. E. O'Brien; J. S. Herring

    2010-06-01

    A reference design for a commercial-scale high-temperature electrolysis (HTE) plant for hydrogen production was developed to provide a basis for comparing the HTE concept with other hydrogen production concepts. The reference plant design is driven by a high-temperature helium-cooled nuclear reactor coupled to a direct Brayton power cycle. The reference design reactor power is 600 MWt, with a primary system pressure of 7.0 MPa, and reactor inlet and outlet fluid temperatures of 540°C and 900°C, respectively. The electrolysis unit used to produce hydrogen includes 4,009,177 cells with a per-cell active area of 225 cm2. The optimized design for the reference hydrogen production plant operates at a system pressure of 5.0 MPa, and utilizes an air-sweep system to remove the excess oxygen that is evolved on the anode (oxygen) side of the electrolyzer. The inlet air for the air-sweep system is compressed to the system operating pressure of 5.0 MPa in a four-stage compressor with intercooling. The alternating current (AC) to direct current (DC) conversion efficiency is 96%. The overall system thermal-to-hydrogen production efficiency (based on the lower heating value of the produced hydrogen) is 47.1% at a hydrogen production rate of 2.356 kg/s. An economic analysis of this plant was performed using the standardized H2A Analysis Methodology developed by the Department of Energy (DOE) Hydrogen Program, and using realistic financial and cost estimating assumptions. The results of the economic analysis demonstrated that the HTE hydrogen production plant driven by a high-temperature helium-cooled nuclear power plant can deliver hydrogen at a competitive cost. A cost of $3.23/kg of hydrogen was calculated assuming an internal rate of return of 10%.

  8. A survey of plant practices and experience in HF alkylation units

    SciTech Connect (OSTI)

    Dobis, J.D.; Clarida, D.R.; Richert, J.P.

    1994-12-31

    The T-8-20 Task Group conducted a survey of plant practices and of the performance of materials of construction in HF alkylation units. A primary goal of the survey was to expand the limited body of information on alternative alloy performance in HF alkylation units and to better define the susceptibility of steel to hydrogen induced cracking. Survey results indicate that although the incidence of cracking is reported to be low, hydrogen blistering is commonly found in pressure vessels. Few applications of alternative alloys were reported, but several areas of vulnerability or high corrosion rates are identified. Common design and maintenance practices are reviewed.

  9. Source book for planning nuclear dual-purpose electric/distillation desalination plants

    SciTech Connect (OSTI)

    Reed, S.A.

    1981-02-01

    A source book on nuclear dual-purpose electric/distillation desalination plants was prepared to assist government and other planners in preparing broad evaluations of proposed applications of dual-purpose plants. The document is divided into five major sections. Section 1 presents general discussions relating to the benefits of dual-purpose plants, and spectrum for water-to-power ratios. Section 2 presents information on commercial nuclear plants manufactured by US manufacturers. Section 3 gives information on distillation desalting processes and equipment. Section 4 presents a discussion on feedwater pretreatment and scale control. Section 5 deals with methods for coupling the distillation and electrical generating plants to operate in the dual mode.

  10. Inspection of Nuclear Power Plant Structures - Overview of Methods and Related Applications

    SciTech Connect (OSTI)

    Naus, Dan J

    2009-05-01

    The objectives of this limited study were to provide an overview of the methods that are available for inspection of nuclear power plant reinforced concrete and metallic structures, and to provide an assessment of the status of methods that address inspection of thick, heavily-reinforced concrete and inaccessible areas of the containment metallic pressure boundary. In meeting these objectives a general description of nuclear power plant safety-related structures was provided as well as identification of potential degradation factors, testing and inspection requirements, and operating experience; methods for inspection of nuclear power plant reinforced concrete structures and containment metallic pressure boundaries were identified and described; and applications of nondestructive evaluation methods specifically related to inspection of thick-section reinforced concrete structures and inaccessible portions of containment metallic pressure boundaries were summarized. Recommendations are provided on utilization of test article(s) to further advance nondestructive evaluation methods related to thick-section, heavily-reinforced concrete and inaccessible portions of the metallic pressure boundary representative of nuclear power plant containments. Conduct of a workshop to provide an update on applications and needed developments for nondestructive evaluation of nuclear power plant structures would also be of benefit.

  11. Online Condition Monitoring to Enable Extended Operation of Nuclear Power Plants

    SciTech Connect (OSTI)

    Meyer, Ryan M.; Bond, Leonard J.; Ramuhalli, Pradeep

    2012-03-31

    Safe, secure, and economic operation of nuclear power plants will remain of strategic significance. New and improved monitoring will likely have increased significance in the post-Fukushima world. Prior to Fukushima, many activities were already underway globally to facilitate operation of nuclear power plants beyond their initial licensing periods. Decisions to shut down a nuclear power plant are mostly driven by economic considerations. Online condition monitoring is a means to improve both the safety and economics of extending the operating lifetimes of nuclear power plants, enabling adoption of proactive aging management. With regard to active components (e.g., pumps, valves, motors, etc.), significant experience in other industries has been leveraged to build the science base to support adoption for online condition-based maintenance and proactive aging management in the nuclear industry. Many of the research needs are associated with enabling proactive management of aging in passive components (e.g., pipes, vessels, cables, containment structures, etc.). This paper provides an overview of online condition monitoring for the nuclear power industry with an emphasis on passive components. Following the overview, several technology/knowledge gaps are identified, which require addressing to facilitate widespread online condition monitoring of passive components.

  12. Digital Full-Scope Simulation of a Conventional Nuclear Power Plant Control Room, Phase 2: Installation of a Reconfigurable Simulator to Support Nuclear Plant Sustainability

    SciTech Connect (OSTI)

    Ronald L. Boring; Vivek Agarwal; Kirk Fitzgerald; Jacques Hugo; Bruce Hallbert

    2013-03-01

    The U.S. Department of Energy’s Light Water Reactor Sustainability program has developed a control room simulator in support of control room modernization at nuclear power plants in the U.S. This report highlights the recent completion of this reconfigurable, full-scale, full-scope control room simulator buildout at the Idaho National Laboratory. The simulator is fully reconfigurable, meaning it supports multiple plant models developed by different simulator vendors. The simulator is full-scale, using glasstop virtual panels to display the analog control boards found at current plants. The present installation features 15 glasstop panels, uniquely achieving a complete control room representation. The simulator is also full-scope, meaning it uses the same plant models used for training simulators at actual plants. Unlike in the plant training simulators, the deployment on glasstop panels allows a high degree of customization of the panels, allowing the simulator to be used for research on the design of new digital control systems for control room modernization. This report includes separate sections discussing the glasstop panels, their layout to mimic control rooms at actual plants, technical details on creating a multi-plant and multi-vendor reconfigurable simulator, and current efforts to support control room modernization at U.S. utilities. The glasstop simulator provides an ideal testbed for prototyping and validating new control room concepts. Equally importantly, it is helping create a standardized and vetted human factors engineering process that can be used across the nuclear industry to ensure control room upgrades maintain and even improve current reliability and safety.

  13. Annual radiological environmental operating report: Browns Ferry Nuclear Plant, 1992. Operations Services/Technical Programs

    SciTech Connect (OSTI)

    Not Available

    1993-04-01

    This report describes the environmental radiological monitoring program conducted by TVA in the vicinity of Browns Ferry Nuclear Plant (BFN) in 1992. The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples. Samples are taken from stations in the general area of the plant and from areas not influenced by plant operations. Station locations are selected after careful consideration of the weather patterns and projected radiation doses to the various areas around the plant. Material sampled includes air, water, milk, foods, vegetation, soil, fish, sediment, and direct radiation levels. Results from stations near the plant are compared with concentrations from control stations and with preoperational measurements to determine potential impacts of plant operations. Small amounts of Co-60 and Cs-134 were found in sediment samples downstream from the plant. This activity in stream sediment would result in no measurable increase over background in the dose to the general public.

  14. A Novel, Safe, and Environmentally Friendly Technology for Water Production Through Recovery of Rejected Thermal Energy From Nuclear Power Plants

    SciTech Connect (OSTI)

    Khalil, Yehia F.; Elimelech, Menachem

    2006-07-01

    In this work, we describe a novel design that utilizes seawater and a portion of rejected heat from a nuclear plant's steam cycle to operate a water desalination system using forward osmosis technology. Water produced from this process is of sufficient quality to be readily used to supply plant demands for continuous makeup water. The proposed process minimizes the environmental concerns associated with thermal pollution of public waters and the resulting adverse impact on marine ecology. To demonstrate the technical feasibility of this conceptual design of a water treatment process, we discuss a case study as an example to describe how the proposed design can be implemented in a nuclear power station with a once--through cooling system that discharges rejected heat to an open sound seawater as its ultimate heat sink. In this case study, the station uses a leased (vendor owned and operated) onsite water treatment system that demineralizes and polishes up to 500-gpm of city water (at 100 ppm TDS) to supply high-quality makeup water (< 0.01 ppm TDS) to the plant steam system. The objectives of implementing the new design are three fold: 1) forego current practice of using city water as the source of plant makeup water, thereby reducing the nuclear station's impact on the region's potable water supply by roughly 100 million gallons/year, 2) minimize the adverse impact of discharging rejected heat into the open sound seawater and, hence, protect the marine ecology, and 3) eliminate the reliance on external vendor that owns and operates the onsite water treatment system, thereby saving an annual fixed cost of $600 K plus 6 cents per 1,000 gallons of pure water. The design will also eliminate the need for using two double-path reverse osmosis (RO) units that consume 425 kW/h of electric power to operate two RO pumps (480 V, 281.6 HP, and 317.4 amps). (authors)

  15. Spent Nuclear Fuel

    Gasoline and Diesel Fuel Update (EIA)

    Spent Nuclear Fuel Release date: December 7, 2015 Next release date: Late 2018 Spent nuclear fuel data are collected by the U.S. Energy Information Administration (EIA) for the Department of Energy's Office of Standard Contract Management (Office of the General Counsel) on the Form GC-859, "Nuclear Fuel Data Survey." The data include detailed characteristics of spent nuclear fuel discharged from commercial U.S. nuclear power plants and currently stored at commercial sites in the United

  16. The Transportable Nuclear Plant for Multi Purpose Applications

    SciTech Connect (OSTI)

    Pahladsingh, R.R.

    2002-07-01

    The DOE (Department of Energy - USA) has started the Generation IV initiative for the new generation of nuclear reactors that have to be much better developed for safety, economy and public acceptance. The SGR (Simplified Gas-cooled Reactor) is being proposed as a Generation IV modular nuclear reactor, using graphite pebbles as fuel, whereby an attempt has been made to meet all the DOE requirements [1,2] to be used for future nuclear reactors. Deregulation and liberalization are changing the global energy-markets. At the same time innovative technologies are introduced in the electricity industry; often as a requirement from the upcoming Digital Society. Energy solutions for the future are more seen as a mix of energy-sources for generation-, transmission- and distribution energy-services. The Internet Energy-web based 'Virtual' enterprises are coming up and will gradually change our society. The focus in this paper is on the changing and emerging global energy-markets and how the nuclear industry can anticipate in the coming Digital Society. (authors)

  17. Safeguards Guidance Document for Designers of Commercial Nuclear Facilities: International Nuclear Safeguards Requirements and Practices For Uranium Enrichment Plants

    SciTech Connect (OSTI)

    Robert Bean; Casey Durst

    2009-10-01

    This report is the second in a series of guidelines on international safeguards requirements and practices, prepared expressly for the designers of nuclear facilities. The first document in this series is the description of generic international nuclear safeguards requirements pertaining to all types of facilities. These requirements should be understood and considered at the earliest stages of facility design as part of a new process called “Safeguards-by-Design.” This will help eliminate the costly retrofit of facilities that has occurred in the past to accommodate nuclear safeguards verification activities. The following summarizes the requirements for international nuclear safeguards implementation at enrichment plants, prepared under the Safeguards by Design project, and funded by the U.S. Department of Energy (DOE) National Nuclear Security Administration (NNSA), Office of NA-243. The purpose of this is to provide designers of nuclear facilities around the world with a simplified set of design requirements and the most common practices for meeting them. The foundation for these requirements is the international safeguards agreement between the country and the International Atomic Energy Agency (IAEA), pursuant to the Treaty on the Non-proliferation of Nuclear Weapons (NPT). Relevant safeguards requirements are also cited from the Safeguards Criteria for inspecting enrichment plants, found in the IAEA Safeguards Manual, Part SMC-8. IAEA definitions and terms are based on the IAEA Safeguards Glossary, published in 2002. The most current specification for safeguards measurement accuracy is found in the IAEA document STR-327, “International Target Values 2000 for Measurement Uncertainties in Safeguarding Nuclear Materials,” published in 2001. For this guide to be easier for the designer to use, the requirements have been restated in plainer language per expert interpretation using the source documents noted. The safeguards agreement is fundamentally a

  18. Safeguards training course: Nuclear material safeguards for enrichment plants

    SciTech Connect (OSTI)

    Not Available

    1990-06-01

    The main objective of this course is to provide the course participants with the necessary skills to perform their inspection activities at enrichment plants. As background information, a variety of enrichment technologies will first be characterized and compared followed by a review of basic cascade, gas centrifuge, and gaseous diffusion theory. To focus on gas centrifuge and gaseous diffusion technology, the major components and system of gas centrifuge and gaseous diffusion enrichment plants including their function in routine LEU production will be identified. The objectives of safeguards at an enrichment plant, including those agreed to in the Hexapartite Safeguards Project, will then be described. Discussions will then focus on potential diversion scenarios at both a centrifuge and diffusion enrichment facility and applicable safeguards inspection activities for detecting these scenarios. This report presents a discussion on basic separation and cascade theory, uranium hexafluoride, and detailed separation theory, including gas centrifuge and gaseous diffusion.

  19. Safeguards training course: Nuclear material safeguards for enrichment plants

    SciTech Connect (OSTI)

    Not Available

    1990-06-01

    The main objective of this training course is to provide the course participants with the necessary skills to perform their inspection activities at enrichment plants. As background information, a variety of enrichment technologies will first be characterized and compared followed by a review of basic cascade, gas centrifuge, and gaseous diffusion theory. To focus on gas centrifuge and gaseous diffusion technology, the major components and systems of gas centrifuge and gaseous diffusion enrichment plants including their function in routine LEU production will be identified. The objectives of safeguards at an enrichment plant, including those agreed to in the Hexapartite Safeguards Project, will then be described. Discussion will then focus on potential diversion scenarios at both a centrifuge and diffusion enrichment facility and applicable safeguards inspection activities for detecting these scenarios.

  20. Reducing water freshwater consumption at coal-fired power plants : approaches used outside the United States.

    SciTech Connect (OSTI)

    Elcock, D.

    2011-05-09

    Coal-fired power plants consume huge quantities of water, and in some water-stressed areas, power plants compete with other users for limited supplies. Extensive use of coal to generate electricity is projected to continue for many years. Faced with increasing power demands and questionable future supplies, industries and governments are seeking ways to reduce freshwater consumption at coal-fired power plants. As the United States investigates various freshwater savings approaches (e.g., the use of alternative water sources), other countries are also researching and implementing approaches to address similar - and in many cases, more challenging - water supply and demand issues. Information about these non-U.S. approaches can be used to help direct near- and mid-term water-consumption research and development (R&D) activities in the United States. This report summarizes the research, development, and deployment (RD&D) status of several approaches used for reducing freshwater consumption by coal-fired power plants in other countries, many of which could be applied, or applied more aggressively, at coal-fired power plants in the United States. Information contained in this report is derived from literature and Internet searches, in some cases supplemented by communication with the researchers, authors, or equipment providers. Because there are few technical, peer-reviewed articles on this topic, much of the information in this report comes from the trade press and other non-peer-reviewed references. Reducing freshwater consumption at coal-fired power plants can occur directly or indirectly. Direct approaches are aimed specifically at reducing water consumption, and they include dry cooling, dry bottom ash handling, low-water-consuming emissions-control technologies, water metering and monitoring, reclaiming water from in-plant operations (e.g., recovery of cooling tower water for boiler makeup water, reclaiming water from flue gas desulfurization [FGD] systems), and

  1. Kansas City Plant | National Nuclear Security Administration | (NNSA)

    National Nuclear Security Administration (NNSA)

    Kansas City Plant Kansas City Plant Contract No.: DE-NA0000622 Period of Performance: 10/01/2010 to 09/30/2015 Operated by Honeywell FM&T, LLC Conformed to Modification 0108 dated 07/30/15 To view contracts prior to 2010, click here. BASIC Contract (Official) Modifications (Official) Funding Mods Available Upon Request Conformed Contract (Unofficial) (to Mod 0108 dated 07/30/15) KCPSF33-Executed.pdf (pdf, 743KB) KCP002.pdf (1/5/11) (pdf, 4977KB) KCPSF33-Executed.pdf (pdf, 743KB) KCPSecBH.pdf

  2. Application of PSA to review and define technical specifications for advanced nuclear power plants

    SciTech Connect (OSTI)

    Kim, I.S.; Samanta, P.K.; Reinhart, F.M.; Wohl, M.L.

    1995-11-01

    As part of the design certification process, probabilistic safety assessments (PSAS) are performed at the design stage for each advanced nuclear power plant. Among other usages, these PSAs are important inputs in defining the Technical Specifications (TSs) for these plants. Knowledge gained from their use in improving the TSs for operating nuclear power plants is providing methods and insights for using PSAs at this early stage. Evaluating the safety or the risk significance of the TSs to be defined for an advanced plant encompasses diverse aspects: (a) determining the basic limiting condition for operation (LCO); (b) structuring conditions associated with the LCO; (c) defining completion times (equivalent to allowed outage times in the TS for conventional plants); and, (d) prescribing required actions to be taken within the specified completion times. In this paper, we consider the use of PSA in defining the TSs for an advanced nuclear plant, namely General Electric`s Advanced Boiling Water Reactor (ABWR). Similar approaches are being taken for ABB-CE`s System 80+ and Westinghouse`s AP-600. We discuss the general features of an advanced reactor`s TS, how PSA is being used in reviewing the TSs, and we give an example where the TS submittal was reviewed using a PSA-based analysis to arrive at the requirements for the plant.

  3. Remarks by Secretary Moniz at the Summit on Improving the Economics of America’s Nuclear Power Plants-- As Delivered

    Office of Energy Efficiency and Renewable Energy (EERE)

    Keynote Address by Secretary Moniz at the Department of Energy Summit on Improving the Economics of America’s Nuclear Power Plants

  4. OVERVIEW OF A RECONFIGURABLE SIMULATOR FOR MAIN CONTROL ROOM UPGRADES IN NUCLEAR POWER PLANTS

    SciTech Connect (OSTI)

    Ronald L. Boring

    2012-10-01

    This paper provides background on a reconfigurable control room simulator for nuclear power plants. The main control rooms in current nuclear power plants feature analog technology that is growing obsolete. The need to upgrade control rooms serves the practical need of maintainability as well as the opportunity to implement newer digital technologies with added functionality. There currently exists no dedicated research simulator for use in human factors design and evaluation activities for nuclear power plant modernization in the U.S. The new research simulator discussed in this paper provides a test bed in which operator performance on new control room concepts can be benchmarked against existing control rooms and in which new technologies can be validated for safety and usability prior to deployment.

  5. Department of Energy Releases Conditional Agreement for New Nuclear Power

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

    Plants | Department of Energy Conditional Agreement for New Nuclear Power Plants Department of Energy Releases Conditional Agreement for New Nuclear Power Plants September 25, 2007 - 2:49pm Addthis Marks initial step for sponsors of new nuclear plants to qualify for up to $2 billion in federal risk insurance WASHINGTON, DC - The U.S. Department of Energy (DOE) Secretary Samuel W. Bodman today released a Conditional Agreement for companies building new nuclear power plants in the United

  6. The status of nuclear power plants in the People's Republic of China

    SciTech Connect (OSTI)

    Puckett, J.

    1991-05-01

    China's main energy source is coal, but transportation and environmental problems make that fuel less than desirable. Therefore, the Chinese, as part of an effort toward alternative energy sources, are developing nuclear power plants. In addition to providing a cleaner power source, development of nuclear energy would improve the Chinese economic condition and give the nation greater world status. China's first plants, at Qinshan and Daya Bay, are still incomplete. However, China is working toward completion of those reactors and planning the training and operating procedures needed to operate them. At the same time, it is improving its nuclear fuel exports. As they develop the capability for generating nuclear power, the Chinese seem to be aware of the accompanying quality and safety considerations, which they have declared to be first priorities. 50 refs., 7 figs.

  7. Supplemnental Volume - Independent Oversight Assessment of the Nuclear Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant, January 2012

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

    Supplemental Volume Independent Oversight Assessment of Nuclear Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant January 2012 Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Office of Health, Safety and Security HSS i Independent Oversight Assessment of Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant

  8. State Nuclear Profiles 2010

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

    Yankee Unit 1 620 4,782 100.0 Entergy Nuclear Vermont Yankee 1 Plant 1 Reactor 620 4,782 100.0 Owner Note: Totals may not equal sum of components due to independent rounding. ...

  9. Nuclear criticality safety evaluation of Spray Booth Operations in X-705, Portsmouth Gaseous Diffusion Plant

    SciTech Connect (OSTI)

    Sheaffer, M.K.; Keeton, S.C.

    1993-09-20

    This report evaluates nuclear criticality safety for Spray Booth Operations in the Decontamination and Recovery Facility, X-705, at the Portsmouth Gaseous Diffusion Plant. A general description of current procedures and related hardware/equipment is presented. Control parameters relevant to nuclear criticality safety are explained, and a consolidated listing of administrative controls and safety systems is developed. Based on compliance with DOE Orders and MMES practices, the overall operation is evaluated, and recommendations for enhanced safety are suggested.

  10. Radioactive materials released from nuclear power plants: Annual report, 1985

    SciTech Connect (OSTI)

    Tichler, J.; Norden, K.; Congemi, J.

    1988-01-01

    Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1985 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1985 release data are summarized in tabular form. Data covering specific radionuclides are summarized.

  11. Radioactive materials released from nuclear power plants. Annual report 1978

    SciTech Connect (OSTI)

    Tichler, J.; Benkovitz, C.

    1981-03-01

    Releases of radioactive materials in airborne and liquid effluents from commerical light water reactors during 1978 have been compiled and reported. Data on soild waste shipments as well as selected operating information have been included. This report supplements earlier annual reports by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1978 release data are compared with previous years releases in tabular form. Data covering specific radionuclides are summarized.

  12. Radioactive materials released from nuclear power plants. Annual report, 1980

    SciTech Connect (OSTI)

    Tichler, J.; Benkovitz, C.

    1983-01-01

    Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1980 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1980 release data are summarized in tabular form. Data covering specific radionuclides are summarized.

  13. Radioactive materials released from nuclear power plants: Annual report, 1984

    SciTech Connect (OSTI)

    Tichler, J.; Norden, K.; Congemi, J.

    1987-08-01

    Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1984 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1984 release data are summarized in tabular form. Data covering specific radionuclides are summarized.

  14. An analysis of nuclear power plant operating costs: A 1995 update

    SciTech Connect (OSTI)

    1995-04-21

    Over the years real (inflation-adjusted) O&M cost have begun to level off. The objective of this report is to determine whether the industry and NRC initiatives to control costs have resulted in this moderation in the growth of O&M costs. Because the industry agrees that the control of O&M costs is crucial to the viability of the technology, an examination of the factors causing the moderation in costs is important. A related issue deals with projecting nuclear operating costs into the future. Because of the escalation in nuclear operating costs (and the fall in fossil fuel prices) many State and Federal regulatory commissions are examining the economics of the continued operation of nuclear power plants under their jurisdiction. The economics of the continued operation of a nuclear power plant is typically examined by comparing the cost of the plants continued operation with the cost of obtaining the power from other sources. This assessment requires plant-specific projections of nuclear operating costs. Analysts preparing these projections look at past industry-wide cost trends and consider whether these trends are likely to continue. To determine whether these changes in trends will continue into the future, information about the causal factors influencing costs and the future trends in these factors are needed. An analysis of the factors explaining the moderation in cost growth will also yield important insights into the question of whether these trends will continue.

  15. Community emergency response to nuclear power plant accidents: A selected and partially annotated bibliography

    SciTech Connect (OSTI)

    Youngen, G.

    1988-10-01

    The role of responding to emergencies at nuclear power plants is often considered the responsibility of the personnel onsite. This is true for most, if not all, of the incidents that may happen during the course of the plant`s operating lifetime. There is however, the possibility of a major accident occurring at anytime. Major nuclear accidents at Chernobyl and Three Mile Island have taught their respective countries and communities a significant lesson in local emergency preparedness and response. Through these accidents, the rest of the world can also learn a great deal about planning, preparing and responding to the emergencies unique to nuclear power. This bibliography contains books, journal articles, conference papers and government reports on emergency response to nuclear power plant accidents. It does not contain citations for ``onsite`` response or planning, nor does it cover the areas of radiation releases from transportation accidents. The compiler has attempted to bring together a sampling of the world`s collective written experience on dealing with nuclear reactor accidents on the sate, local and community levels. Since the accidents at Three Mile Island and Chernobyl, that written experience has grown enormously.

  16. Natural Circulation in Water Cooled Nuclear Power Plants Phenomena, models, and methodology for system reliability assessments

    SciTech Connect (OSTI)

    Jose Reyes

    2005-02-14

    In recent years it has been recognized that the application of passive safety systems (i.e., those whose operation takes advantage of natural forces such as convection and gravity), can contribute to simplification and potentially to improved economics of new nuclear power plant designs. In 1991 the IAEA Conference on ''The Safety of Nuclear Power: Strategy for the Future'' noted that for new plants the use of passive safety features is a desirable method of achieving simplification and increasing the reliability of the performance of essential safety functions, and should be used wherever appropriate''.

  17. Guidance for Deployment of Mobile Technologies for Nuclear Power Plant Field Workers

    SciTech Connect (OSTI)

    Heather D. Medema; Ronald K. Farris

    2012-09-01

    This report is a guidance document prepared for the benefit of commercial nuclear power plants (NPPs) supporting organizations and personnel who are considering or undertaking deployment of mobile technology for the purpose of improving human performance and plant status control (PSC) for field workers in an NPP setting. This document especially is directed at NPP business managers, Electric Power Research Institute, Institute of Nuclear Power Operations, and other non-Information Technology personnel. This information is not intended to replace basic project management practices or reiterate these processes, but is to support decision-making, planning, and preparation of a business case.

  18. Economic Analysis of the Reference Design for a Nuclear-Driven High-Temperature-Electrolysis Hydrogen Production Plant

    SciTech Connect (OSTI)

    E. A. Harvego; M. G. McKellar; M. S. Sohal; J. E. O'Brien; J. S. Herring

    2008-01-01

    A reference design for a commercial-scale high-temperature electrolysis (HTE) plant for hydrogen production was developed to provide a basis for comparing the HTE concept with other hydrogen production concepts. The reference plant design is driven by a high-temperature helium-cooled reactor coupled to a direct Brayton power cycle. The reference design reactor power is 600 MWt, with a primary system pressure of 7.0 MPa, and reactor inlet and outlet fluid temperatures of 540°C and 900°C, respectively. The electrolysis unit used to produce hydrogen consists of 4,009,177 cells with a per-cell active area of 225 cm2. A nominal cell area-specific resistance, ASR, value of 0.4 Ohm•cm2 with a current density of 0.25 A/cm2 was used, and isothermal boundary conditions were assumed. The optimized design for the reference hydrogen production plant operates at a system pressure of 5.0 MPa, and utilizes an air-sweep system to remove the excess oxygen that is evolved on the anode side of the electrolyzer. The inlet air for the air-sweep system is compressed to the system operating pressure of 5.0 MPa in a four-stage compressor with intercooling. The alternating current, AC, to direct current, DC, conversion is 96%. The overall system thermal-to-hydrogen production efficiency (based on the low heating value of the produced hydrogen) is 47.12% at a hydrogen production rate of 2.356 kg/s. An economic analysis of the plant was also performed using the H2A Analysis Methodology developed by the Department of Energy (DOE) Hydrogen Program. The results of the economic analysis demonstrated that the HTE hydrogen production plant driven by a high-temperature helium-cooled nuclear power plant can deliver hydrogen at a competitive cost using realistic financial and cost estimating assumptions. A required cost of $3.23 per kg of hydrogen produced was calculated assuming an internal rate of return of 10%. Approximately 73% of this cost ($2.36/kg) is the result of capital costs associated

  19. Aging management guideline for commercial nuclear power plants - tanks and pools

    SciTech Connect (OSTI)

    Blocker, E.; Smith, S.; Philpot, L.; Conley, J.

    1996-02-01

    Continued operation of nuclear power plants for periods that extend beyond their original 40-year license period is a desirable option for many U.S. utilities. U.S. Nuclear Regulatory Commission (NRC) approval of operating license renewals is necessary before continued operation becomes a reality. Effective aging management for plant components is important to reliability and safety, regardless of current plant age or extended life expectations. However, the NRC requires that aging evaluations be performed and the effectiveness of aging management programs be demonstrated for components considered within the scope of license renewal before granting approval for operation beyond 40 years. Both the NRC and the utility want assurance that plant components will be highly reliable during both the current license term and throughout the extended operating period. In addition, effective aging management must be demonstrated to support Maintenance Rule (10 CFR 50.65) activities.

  20. Plant Outage Time Savings Provided by Subcritical Physics Testing at Vogtle Unit 2

    SciTech Connect (OSTI)

    Cupp, Philip [Southern Nuclear Company (United States); Heibel, M.D. [Westinghouse Electric Company, LLC (United States)

    2006-07-01

    The most recent core reload design verification physics testing done at Southern Nuclear Company's (SNC) Vogtle Unit 2, performed prior to initial power operations in operating cycle 12, was successfully completed while the reactor was at least 1% {delta}K/K subcritical. The testing program used was the first application of the Subcritical Physics Testing (SPT) program developed by the Westinghouse Electric Company LLC. The SPT program centers on the application of the Westinghouse Subcritical Rod Worth Measurement (SRWM) methodology that was developed in cooperation with the Vogtle Reactor Engineering staff. The SRWM methodology received U. S. Nuclear Regulatory Commission (NRC) approval in August of 2005. The first application of the SPT program occurred at Vogtle Unit 2 in October of 2005. The results of the core design verification measurements obtained during the SPT program demonstrated excellent agreement with prediction, demonstrating that the predicted core characteristics were in excellent agreement with the actual operating characteristics of the core. This paper presents an overview of the SPT Program used at Vogtle Unit 2 during operating cycle 12, and a discussion of the critical path outage time savings the SPT program is capable of providing. (authors)

  1. Proceedings of the 2006 international congress on advances in nuclear power plants - ICAPP'06

    SciTech Connect (OSTI)

    2006-07-01

    Following the highly successful ICAPP'05 meeting held in Seoul Korea, the 2006 International Congress on Advances in Nuclear Power Plants brought together international experts of the nuclear industry involved in the operation, development, building, regulation and research related to Nuclear Power Plants. The program covers the full spectrum of Nuclear Power Plant issues from design, deployment and construction of plants to research and development of future designs and advanced systems. The program covers lessons learned from power, research and demonstration reactors from over 50 years of experience with operation and maintenance, structures, materials, technical specifications, human factors, system design and reliability. The program by technical track deals with: - 1. Water-Cooled Reactor Programs and Issues Evolutionary designs, innovative, passive, light and heavy water cooled reactors; issues related to meeting medium term utility needs; design and regulatory issues; business, political and economic challenges; infrastructure limitations and improved construction techniques including modularization. - 2. High Temperature Gas Cooled Reactors Design and development issues, components and materials, safety, reliability, economics, demonstration plants and environmental issues, fuel design and reliability, power conversion technology, hydrogen production and other industrial uses; advanced thermal and fast reactors. - 3. Long Term Reactor Programs and Strategies Reactor technology with enhanced fuel cycle features for improved resource utilization, waste characteristics, and power conversion capabilities. Potential reactor designs with longer development times such as, super critical water reactors, liquid metal reactors, gaseous and liquid fuel reactors, Gen IV, INPRO, EUR and other programs. - 4. Operation, Performance and Reliability Management Training, O and M costs, life cycle management, risk based maintenance, operational experiences, performance and

  2. Anti-nuclear weapons activism in the United States and Great Britain: a comparative analysis

    SciTech Connect (OSTI)

    Sussman, G.

    1987-01-01

    This study is a response to the lacuna in empirical research into political activism and the nuclear issue and seeks to ascertain the social and value characteristics, political attitudes, and political behavior of activists in the United States and Great Britain. Consideration is also given to gender differences in light of evidence of an emerging gender gap in these two countries. The study investigates the common forces cited in two sets of literature - post-industrialism and anti-nuclear weapons movements - which provide a framework for analysis. Survey research data is employed to assess cross-national similarities and differences. The findings obtained indicate that while American and British activists exhibit common social and value characteristics, British activists appear more integrated in their political opposition to nuclear weapons compared with their American counterparts. Survey results indicate that the political-action repertoire of these activists is quite diverse, suggesting a new style of politics in advanced industrial democracies. Gender-based analysis reveals two important findings. First, activist American men differ significantly from the other three social groups in their attitudes towards nuclear weapons. Second, activist women in both national settings participate at a level equal to or exceeding that of activist men.

  3. Fossil plant maintenance optimization at FPC`s Crystal River Units 4 & 5

    SciTech Connect (OSTI)

    Cossey, J.; Pflasterer, R.; Colsher, R.; Toomey, G.; Smith, S.; Abbott, P.

    1996-07-01

    Florida Power Corporation recently completed a Fossil Plant Maintenance Optimization project at it`s Crystal River Units 4 and 5 coal fired power plant. The project combined Streamlined Reliability Centered Maintenance (SRCM) techniques with a Predictive Maintenance (PDM) Assessment to analyze eleven of the plants systems that represent the principal contributors to maintenance costs. The plant had an extensive existing maintenance program that included several types of condition monitoring. The Benefit-to-Cost analysis indicates that the annual savings associated with the project recommendations result in a payback period of less than one year. This paper summarizes the types of recommendations that were made and describes the processes used for both the SRCM analysis and the PDM Assessment. The SRCM analysis used proven techniques and software that have been used on other projects, including some sponsored by EPRI. The PDM Assessment process was similar to processes used previously for EPRI and non- EPRI utilities; however, this was the first project where the two processes were modified to take advantage of work performed using the other. All of the recommendations developed by the SRCM analysts were reviewed by the PDM analysts before they were finalized. The structure and flow of the project is also described including how the SRCM and PDM analysts interfaced with the plant staff and how implementation was facilitated. The analysis relied on plant experience related to the operation and maintenance history of the equipment. The recommendations for each system were reviewed by a team consisting of the first-line maintenance supervisors, the maintenance planners, and the plant technical services group. The project recommendations are essentially two-thirds implemented, with many of them implemented before the analysis was completed.

  4. Technical evaluation of the noise and isolation testing of the reactor protection system for the Davis Besse Nuclear Power Station, Unit 1

    SciTech Connect (OSTI)

    Selan, J.C.

    1980-01-01

    This report documents the technical evaluation of the noise and isolation testing of the reactor protection system (RPS) for the Davis Besse Nuclear Power Station, Unit 1. The testing was performed in accordance to Section 4.6.11, Susceptibility, of MIL-N-19900B, and NRC approved plant test methods. Analysis of the test results shows that the reactor protection system did not degrade below acceptable levels when subjected to electromagnetic, electrostatic, isolation and noise level tests, nor was the system's ability to perform its Class 1E protective functions affected.

  5. Technical evaluation report on the monitoring of electric power to the reactor-protection system for the Brunswick Steam Electric Plant, Units 1 and 2

    SciTech Connect (OSTI)

    Selan, J.C.

    1982-04-26

    This report documents the technical evaluation of the monitoring of electric power to the reactor protection system (RPS) at the Brunswick Steam Electric Plant, Units 1 and 2. The evaluation is to determine if the proposed design modification will protect the RPS from abnormal voltage and frequency conditions which could be supplied from the power supplies and will meet certain requirements set forth by the Nuclear Regulatory Commission. The proposed design modifications with time delays verified by GE, will protect the RPS from sustained abnormal voltage and frequency conditions from the supplying sources.

  6. 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.

  7. 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.

  8. Dynamic Operations Wayfinding System (DOWS) for Nuclear Power Plants

    SciTech Connect (OSTI)

    Boring, Ronald Laurids; Ulrich, Thomas Anthony; Lew, Roger Thomas

    2015-08-01

    A novel software tool is proposed to aid reactor operators in respond- ing to upset plant conditions. The purpose of the Dynamic Operations Wayfind- ing System (DOWS) is to diagnose faults, prioritize those faults, identify paths to resolve those faults, and deconflict the optimal path for the operator to fol- low. The objective of DOWS is to take the guesswork out of the best way to combine procedures to resolve compound faults, mitigate low threshold events, or respond to severe accidents. DOWS represents a uniquely flexible and dy- namic computer-based procedure system for operators.

  9. Top U.S. Nuclear Official Commends Industry for Submitting 3rd...

    Office of Environmental Management (EM)

    Commission (NRC) for construction of a new nuclear power plant in the United States. ... "As the third complete license application for a new nuclear power plant submitted in less ...

  10. Extending Sensor Calibration Intervals in Nuclear Power Plants

    SciTech Connect (OSTI)

    Coble, Jamie B.; Meyer, Ryan M.; Ramuhalli, Pradeep; Bond, Leonard J.; Shumaker, Brent; Hashemian, Hash

    2012-11-15

    Currently in the USA, sensor recalibration is required at every refueling outage, and it has emerged as a critical path item for shortening outage duration. International application of calibration monitoring, such as at the Sizewell B plant in UK, has shown that sensors may operate for eight years, or longer, within calibration tolerances. Online monitoring can be employed to identify those sensors which require calibration, allowing for calibration of only those sensors which need it. The US NRC accepted the general concept of online monitoring for sensor calibration monitoring in 2000, but no plants have been granted the necessary license amendment to apply it. This project addresses key issues in advanced recalibration methodologies and provides the science base to enable adoption of best practices for applying online monitoring, resulting in a public domain standardized methodology for sensor calibration interval extension. Research to develop this methodology will focus on three key areas: (1) quantification of uncertainty in modeling techniques used for calibration monitoring, with a particular focus on non-redundant sensor models; (2) accurate determination of acceptance criteria and quantification of the effect of acceptance criteria variability on system performance; and (3) the use of virtual sensor estimates to replace identified faulty sensors to extend operation to the next convenient maintenance opportunity.

  11. Method To Monitor Nuclear Power Plant Risk from Transmission Grid Conditions

    SciTech Connect (OSTI)

    B. Gregg; K Canavan

    2004-10-30

    This report examines a method to monitor and trend the transmission grid in the local vicinity of a nuclear o other generating station. The method addresses the potential for a loss of off-site power following a plant trip or a loss-of-coolant accident.

  12. 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.

  13. Development of Advanced Technologies to Reduce Design, Fabrication and Construction Costs for Future Nuclear Power Plants

    SciTech Connect (OSTI)

    DiNunzio, Camillo A.; Gupta, Abhinav; Golay, Michael; Luk, Vincent; Turk, Rich; Morrow, Charles; Jin, Geum-Taek

    2002-11-30

    This report presents a summation of the third and final year of a three-year investigation into methods and technologies for substantially reducing the capital costs and total schedule for future nuclear plants. In addition, this is the final technical report for the three-year period of studies.

  14. Aerial Radiation Measurements from the Fukushima Dai-ichi Nuclear Power Plant Accident

    SciTech Connect (OSTI)

    Guss, P. P.

    2012-07-16

    This document is a slide show type presentation concerning DOE and Aerial Measuring System (AMS) activities and results with respect to assessing the consequences of the releases from the Fukushima Dai-ichi Nuclear Power Plant. These include ground monitoring and aerial monitoring.

  15. Survey of thermal-hydraulic models of commercial nuclear power plants

    SciTech Connect (OSTI)

    Determan, J.C.; Hendrix, C.E.

    1992-12-01

    A survey of the thermal-hydraulic models of nuclear power plants has been performed to identify the NRC's current analytical capabilities for critical event response. The survey also supports ongoing research for accident management. The results of the survey are presented here. The PC database which records detailed data on each model is described.

  16. Survey of thermal-hydraulic models of commercial nuclear power plants

    SciTech Connect (OSTI)

    Determan, J.C.; Hendrix, C.E.

    1992-12-01

    A survey of the thermal-hydraulic models of nuclear power plants has been performed to identify the NRC`s current analytical capabilities for critical event response. The survey also supports ongoing research for accident management. The results of the survey are presented here. The PC database which records detailed data on each model is described.

  17. Guidance for a large tabletop exercise for a nuclear power plant

    SciTech Connect (OSTI)

    Weinstein, E.D.; Bates, E.F.; Adler, M.V.; Gant, K.S.

    1995-03-01

    Tabletop exercises are held to discuss issues related to the response of organizations to an emergency event. This document describes in task format the planning, conduct, and reporting of lessons learned for a large interagency tabletop. A sample scenario, focus areas, and discussion questions based on a simulated accident at a commercial nuclear power plant are provided.

  18. Initiating Event Rates at U.S. Nuclear Power Plants. 1988 - 2013

    SciTech Connect (OSTI)

    Schroeder, John A.; Bower, Gordon R.

    2014-02-01

    Analyzing initiating event rates is important because it indicates performance among plants and also provides inputs to several U.S. Nuclear Regulatory Commission (NRC) risk-informed regulatory activities. This report presents an analysis of initiating event frequencies at U.S. commercial nuclear power plants since each plant’s low-power license date. The evaluation is based on the operating experience from fiscal year 1988 through 2013 as reported in licensee event reports. Engineers with nuclear power plant experience staff reviewed each event report since the last update to this report for the presence of valid scrams or reactor trips at power. To be included in the study, an event had to meet all of the following criteria: includes an unplanned reactor trip (not a scheduled reactor trip on the daily operations schedule), sequence of events starts when reactor is critical and at or above the point of adding heat, occurs at a U.S. commercial nuclear power plant (excluding Fort St. Vrain and LaCrosse), and is reported by a licensee event report. This report displays occurrence rates (baseline frequencies) for the categories of initiating events that contribute to the NRC’s Industry Trends Program. Sixteen initiating event groupings are trended and displayed. Initiators are plotted separately for initiating events with different occurrence rates for boiling water reactors and pressurized water reactors. p-values are given for the possible presence of a trend over the most recent 10 years.

  19. Prognostics and Health Management in Nuclear Power Plants: A Review of Technologies and Applications

    SciTech Connect (OSTI)

    Coble, Jamie B.; Ramuhalli, Pradeep; Bond, Leonard J.; Hines, Wes; Upadhyaya, Belle

    2012-07-17

    This report reviews the current state of the art of prognostics and health management (PHM) for nuclear power systems and related technology currently applied in field or under development in other technological application areas, as well as key research needs and technical gaps for increased use of PHM in nuclear power systems. The historical approach to monitoring and maintenance in nuclear power plants (NPPs), including the Maintenance Rule for active components and Aging Management Plans for passive components, are reviewed. An outline is given for the technical and economic challenges that make PHM attractive for both legacy plants through Light Water Reactor Sustainability (LWRS) and new plant designs. There is a general introduction to PHM systems for monitoring, fault detection and diagnostics, and prognostics in other, non-nuclear fields. The state of the art for health monitoring in nuclear power systems is reviewed. A discussion of related technologies that support the application of PHM systems in NPPs, including digital instrumentation and control systems, wired and wireless sensor technology, and PHM software architectures is provided. Appropriate codes and standards for PHM are discussed, along with a description of the ongoing work in developing additional necessary standards. Finally, an outline of key research needs and opportunities that must be addressed in order to support the application of PHM in legacy and new NPPs is presented.

  20. Nuclear heat source component design considerations for HTGR process heat reactor plant concept

    SciTech Connect (OSTI)

    McDonald, C.F.; Kapich, D.; King, J.H.; Venkatesh, M.C.

    1982-05-01

    The coupling of a high-temperature gas-cooled reactor (HTGR) and a chemical process facility has the potential for long-term synthetic fuel production (i.e., oil, gasoline, aviation fuel, hydrogen, etc) using coal as the carbon source. Studies are in progress to exploit the high-temperature capability of an advanced HTGR variant for nuclear process heat. The process heat plant discussed in this paper has a 1170-MW(t) reactor as the heat source and the concept is based on indirect reforming, i.e., the high-temperature nuclear thermal energy is transported (via an intermediate heat exchanger (IHX)) to the externally located process plant by a secondary helium transport loop. Emphasis is placed on design considerations for the major nuclear heat source (NHS) components, and discussions are presented for the reactor core, prestressed concrete reactor vessel (PCRV), rotating machinery, and heat exchangers.

  1. Near-term improvements for nuclear power plant control room annunciator systems. [PWR; BWR

    SciTech Connect (OSTI)

    Rankin, W.L.; Duvernoy, E.G.; Ames, K.R.; Morgenstern, M.H.; Eckenrode, R.J.

    1983-04-01

    This report sets forth a basic design philosophy with its associated functional criteria and design principles for present-day, hard-wired annunciator systems in the control rooms of nuclear power plants. It also presents a variety of annunciator design features that are either necessary for or useful to the implementation of the design philosophy. The information contained in this report is synthesized from an extensive literature review, from inspection and analysis of control room annunciator systems in the nuclear industry and in related industries, and from discussions with a variety of individuals who are knowledgeable about annunciator systems, nuclear plant control rooms, or both. This information should help licensees and license applicants in improving their hard-wired, control room annunciator systems as outlined by NUREG-0700.

  2. AMERICAN ELECTRIC POWER'S CONESVILLE POWER PLANT UNIT NO.5 CO2 CAPTURE RETROFIT STUDY

    SciTech Connect (OSTI)

    Carl R. Bozzuto; Nsakala ya Nsakala; Gregory N. Liljedahl; Mark Palkes; John L. Marion

    2001-06-30

    ALSTOM Power Inc.'s Power Plant Laboratories (ALSTOM) has teamed with American Electric Power (AEP), ABB Lummus Global Inc. (ABB), the US Department of Energy National Energy Technology Laboratory (DOE NETL), and the Ohio Coal Development Office (OCDO) to conduct a comprehensive study evaluating the technical feasibility and economics of alternate CO{sub 2} capture and sequestration technologies applied to an existing US coal-fired electric generation power plant. The motivation for this study was to provide input to potential US electric utility actions concerning GHG emissions reduction. If the US decides to reduce CO{sub 2} emissions, action would need to be taken to address existing power plants. Although fuel switching from coal to natural gas may be one scenario, it will not necessarily be a sufficient measure and some form of CO{sub 2} capture for use or disposal may also be required. The output of this CO{sub 2} capture study will enhance the public's understanding of control options and influence decisions and actions by government, regulators, and power plant owners in considering the costs of reducing greenhouse gas CO{sub 2} emissions. The total work breakdown structure is encompassed within three major reports, namely: (1) Literature Survey, (2) AEP's Conesville Unit No.5 Retrofit Study, and (3) Bench-Scale Testing and CFD Evaluation. The report on the literature survey results was issued earlier by Bozzuto, et al. (2000). Reports entitled ''AEP's Conesville Unit No.5 Retrofit Study'' and ''Bench-Scale Testing and CFD Evaluation'' are provided as companion volumes, denoted Volumes I and II, respectively, of the final report. The work performed, results obtained, and conclusions and recommendations derived therefrom are summarized.

  3. Technical considerations in repowering a nuclear plant for fossil fueled operation

    SciTech Connect (OSTI)

    Patti, F.J.

    1996-03-01

    Repowering involves replacement of the reactor by a fossil fuel source of steam. This source can be a conventional fossil fueled boiler or the heat recovery steam generator (HRSG) on a gas turbine exhaust. The existing steam turbine plant is used to the extent possible. Alternative fuels for repowering a nuclear plant are coal, natural gas and oil. In today`s world oil is not usually an alternative. Selection of coal or natural gas is largely a matter of availability of the fuel near the location of the plant. Both the fossil boiler and the HRSG produce steam at higher pressures and temperatures than the throttle conditions for a saturated steam nuclear turbine. It is necessary to match the steam conditions from the new source to the existing turbine as closely as possible. Technical approaches to achieve a match range from using a topping turbine at the front end of the cycle to attemperation of the throttle steam with feedwater. The electrical output from the repowered plant is usually greater than that of the original nuclear fueled design. This requires consideration of the ability to use the excess electricity. Interfacing of the new facility with the existing turbine plant requires consideration of facility layout and design. Site factors must also be considered, especially for a coal fired boiler, since rail and coal handling facilities must be added to a site for which these were not considered. Additional site factors that require consideration are ash handling and disposal.

  4. Next Generation Nuclear Plant Defense-in-Depth Approach

    SciTech Connect (OSTI)

    Edward G. Wallace; Karl N. Fleming; Edward M. Burns

    2009-12-01

    The purpose of this paper is to (1) document the definition of defense-in-depth and the pproach that will be used to assure that its principles are satisfied for the NGNP project and (2) identify the specific questions proposed for preapplication discussions with the NRC. Defense-in-depth is a safety philosophy in which multiple lines of defense and conservative design and evaluation methods are applied to assure the safety of the public. The philosophy is also intended to deliver a design that is tolerant to uncertainties in knowledge of plant behavior, component reliability or operator performance that might compromise safety. This paper includes a review of the regulatory foundation for defense-in-depth, a definition of defense-in-depth that is appropriate for advanced reactor designs based on High Temperature Gas-cooled Reactor (HTGR) technology, and an explanation of how this safety philosophy is achieved in the NGNP.

  5. Knowledge and abilities catalog for nuclear power plant operators: boiling water reactors

    SciTech Connect (OSTI)

    Not Available

    1986-09-01

    The Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Boiling-Water Reactors (BWR) (NUREG-1123) provides the basis for the development of content-valid licensing examinations for reactor operators (ROs) and senior reactor operators (SROs). The examinations developed using the BWR Catalog and Examiners' Handbook for Developing Operator Licensing Examinations (NUREG-1121) will cover those topics listed under Title 10, Code of Federal Regulations, Part 55. The BWR Catalog contains approximately 7000 knowledge and ability (K/A) statements for ROs and SROs at boiling water reactors. Each K/A statement has been rated for its importance to the safe operation of the plant in a manner ensuring personnel and public health and safety. The BWR K/A Catalog is organized into five major sections: Plant-wide Generic Knowledge and Ability Statements, Plant Systems grouped by Safety Function, Emergency and Abnormal Plant Evolutions, Components, and Theory. The BWR Catalog represents a modification of the form and content of the K/A Catalog for Nuclear Power Plant Operators: Pressurized Water Reactors (NUREG-1122). First, categories of knowledge and ability statements have been redefined. Second, the scope of the definition of emergency and abnormal plant evolutions has been revised in line with a symptom-based approach. Third, K/As related to the operational applications of theory have been incorporated into the delineations for both plant systems and emergency and abnormal plant evolutions, while K/As pertaining to theory fundamental to plant operation have been delineated in a separate theory section. Finally, the components section has been revised.

  6. State of the art review of radioactive waste volume reduction techniques for commercial nuclear power plants

    SciTech Connect (OSTI)

    Not Available

    1980-04-01

    A review is made of the state of the art of volume reduction techniques for low level liquid and solid radioactive wastes produced as a result of: (1) operation of commercial nuclear power plants, (2) storage of spent fuel in away-from-reactor facilities, and (3) decontamination/decommissioning of commercial nuclear power plants. The types of wastes and their chemical, physical, and radiological characteristics are identified. Methods used by industry for processing radioactive wastes are reviewed and compared to the new techniques for processing and reducing the volume of radioactive wastes. A detailed system description and report on operating experiences follow for each of the new volume reduction techniques. In addition, descriptions of volume reduction methods presently under development are provided. The Appendix records data collected during site surveys of vendor facilities and operating power plants. A Bibliography is provided for each of the various volume reduction techniques discussed in the report.

  7. Activities in Support of Continuing the Service of Nuclear Power Plant Safety-Related Concrete Structures

    SciTech Connect (OSTI)

    Naus, Dan J

    2014-01-01

    Nuclear power plant (NPP) concrete structures are described. In-service inspection and testing requirements in the U.S. are summarized. The license renewal process in the U.S. is outlined and its current status provided. Operating experience related to performance of the concrete structures is presented. Basic components of a program to manage aging of the concrete structures are identified and described: (1) Degradation mechanisms, damage models, and material performance; (2) Assessment and remediation: i.e., component selection, in- service inspection, non-destructive examinations, and remedial actions; and (3) Estimation of performance at present or some future point in time: i.e., application of structural reliability theory to the design and optimization of in-service inspection/maintenance strategies, and determination of the effects of degradation on plant risk. Finally, areas are noted where additional research would be of benefit to aging management of nuclear power plant concrete structures.

  8. Diversity Strategies for Nuclear Power Plant Instrumentation and Control Systems

    SciTech Connect (OSTI)

    Wood, Richard Thomas; Belles, Randy; Cetiner, Mustafa Sacit; Holcomb, David Eugene; Korsah, Kofi; Loebl, Andy; Mays, Gary T; Muhlheim, Michael David; Mullens, James Allen; Poore III, Willis P; Qualls, A L; Wilson, Thomas L; Waterman, Michael E.

    2010-02-01

    This report presents the technical basis for establishing acceptable mitigating strategies that resolve diversity and defense-in-depth (D3) assessment findings and conform to U.S. Nuclear Regulatory Commission (NRC) requirements. The research approach employed to establish appropriate diversity strategies involves investigation of available documentation on D3 methods and experience from nuclear power and nonnuclear industries, capture of expert knowledge and lessons learned, determination of best practices, and assessment of the nature of common-cause failures (CCFs) and compensating diversity attributes. The research described in this report does not provide guidance on how to determine the need for diversity in a safety system to mitigate the consequences of potential CCFs. Rather, the scope of this report provides guidance to the staff and nuclear industry after a licensee or applicant has performed a D3 assessment per NUREG/CR-6303 and determined that diversity in a safety system is needed for mitigating the consequences of potential CCFs identified in the evaluation of the safety system design features. Succinctly, the purpose of the research described in this report was to answer the question, 'If diversity is required in a safety system to mitigate the consequences of potential CCFs, how much diversity is enough?' The principal results of this research effort have identified and developed diversity strategies, which consist of combinations of diversity attributes and their associated criteria. Technology, which corresponds to design diversity, is chosen as the principal system characteristic by which diversity criteria are grouped to form strategies. The rationale for this classification framework involves consideration of the profound impact that technology-focused design diversity provides. Consequently, the diversity usage classification scheme involves three families of strategies: (1) different technologies, (2) different approaches within the same

  9. Spent Nuclear Fuel

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

    Nuclear & Uranium Glossary FAQS Overview Data Status of U.S. nuclear outages (interactive) Nuclear power plants Uranium & nuclear fuel Spent nuclear fuel All nuclear data ...

  10. A Holistic, rapid-deployment, solution for safe used nuclear fuel management in the United States of America

    SciTech Connect (OSTI)

    Eriksson, L.G.

    2007-07-01

    Recent political initiatives and increased willingness in the United States of America (U.S. or USA) to consider federal storage and recycling of used nuclear fuel (UNF), augmented by expressed private interest in developing 31 new nuclear power plants, strongly suggest that the U.S. is on the brink of a nuclear-energy renaissance. Unfortunately, the related UNF-management and -disposition research, technology, and facility developments have been virtually dormant for 25 years. Fortunately, other countries have pursued safe UNF-management and -disposition solutions during this period that the U.S. now can take advantage of to develop the required UNF-management technologies and facilities in a timely and cost-effective manner. The following criteria/concepts for the timely and cost-effective development of safe and secure nuclear facilities were applied to current and planned UNF-management in the U.S. to formulate a potential, holistic, 'rapid-deployment' UNF-management solution at the Nevada Test Site (NTS), referred to as the Nevada National Nuclear Fuel Management Center (3NFMC): - Locate pending UNF-storage and -recycling facilities on the NTS in the vicinity of the Nation's candidate deep geological disposal system (repository) for UNF and other high level radioactive waste (HLW) at the Yucca Mountain (YM) site; - Locate all main UNF-management facilities underground; and - Use best-available technology to site, design, and construct the pending facilities. Three main challenges to the timely and cost-effective development of the 3NFMC are: (1) Statutory restrictions preventing the UNF-storage and -disposal facilities from being co-located and co-developed by federal and civilian/private parties; (2) Long-standing, scientific, local-political, key-Congressional, and national-ideological opposition to the YM UNF/HLW repository; and (3) The discouraging track record, and the related lack of trust in, and credibility of the organization currently responsible for

  11. Nuclear-power-plant perimeter-intrusion alarm systems

    SciTech Connect (OSTI)

    Halsey, D.J.

    1982-04-01

    Timely intercept of an intruder requires the examination of perimeter barriers and sensors in terms of reliable detection, immediate assessment and prompt response provisions. Perimeter security equipment and operations must at the same time meet the requirements of the Code of Federal Regulations, 10 CFR 73.55 with some attention to the performance and testing figures of Nuclear Regulatory Guide 5.44, Revision 2, May 1980. A baseline system is defined which recommends a general approach to implementing perimeter security elements: barriers, lighting, intrusion detection, alarm assessment. The baseline approach emphasizes cost/effectiveness achieved by detector layering and logic processing of alarm signals to produce reliable alarms and low nuisance alarm rates. A cost benefit of layering along with video assessment is reduction in operating expense. The concept of layering is also shown to minimize testing costs where detectability performance as suggested by Regulatory Guide 5.44 is to be performed. Synthesis of the perimeter intrusion alarm system and limited testing of CCTV and Video Motion Detectors (VMD), were performed at E-Systems, Greenville Division, Greenville, Texas during 1981.

  12. Integrated head package cable carrier for a nuclear power plant

    DOE Patents [OSTI]

    Meuschke, Robert E.; Trombola, Daniel M.

    1995-01-01

    A cabling arrangement is provided for a nuclear reactor located within a containment. Structure inside the containment is characterized by a wall having a near side surrounding the reactor vessel defining a cavity, an operating deck outside the cavity, a sub-space below the deck and on a far side of the wall spaced from the near side, and an operating area above the deck. The arrangement includes a movable frame supporting a plurality of cables extending through the frame, each connectable at a first end to a head package on the reactor vessel and each having a second end located in the sub-space. The frame is movable, with the cables, between a first position during normal operation of the reactor when the cables are connected to the head package, located outside the sub-space proximate the head package, and a second position during refueling when the cables are disconnected from the head package, located in the sub-space. In a preferred embodiment, the frame straddles the top of the wall in a substantially horizontal orientation in the first position, pivots about an end distal from the head package to a substantially vertically oriented intermediate position, and is guided, while remaining about vertically oriented, along a track in the sub-space to the second position.

  13. Proceedings of the 2004 international congress on advances in nuclear power plants - ICAPP'04

    SciTech Connect (OSTI)

    2004-07-01

    The 2004 International Congress on Advances in Nuclear Power Plants (ICAPP'04) provides a forum for the industry to exchange the latest ideas and research findings on nuclear plants from all perspectives. This conference builds on the success of last year's meeting held in Cordoba, Spain, and on the 2002 inaugural meeting held in Hollywood, Florida. Because of the hard work of many volunteers from around the world, ICAPP'04 has been successful in achieving its goal. More than 325 invited and contributed papers/presentations are part of this ICAPP. There are 5 invited plenary sessions and 70 technical sessions with contributed papers. The ICAPP'04 Proceedings contain almost 275 papers prepared by authors from 25 countries covering topics related to advances in nuclear power plant technology. The program by technical track deals with: 1 - Water-Cooled Reactor Programs and Issues (Status of All New Water-Cooled Reactor Programs; Advanced PWRs: Developmental Stage I; Advanced PWRs: Developmental Stage II; Advanced PWRs: Basic Design Stage; Advanced BWRs; Economics, Regulation, Licensing, and Construction; AP1000); 2 - High Temperature Gas Cooled Reactors (Pebble Bed Modular Reactors; Very High Temperature Reactors; HTR Fuels and Materials; Innovative HTRs and Fuel Cycles); 3 - Long Term Reactor Programs and Strategies (Supercritical Pressure Water Reactors; Lead-Alloy Fast Reactors; Sodium and Gas Fast Reactors; Status of Advanced Reactor Programs; Non-classical Reactor Concepts); 4 - Operation, Performance, and Reliability Management (Information Technology Effect on Plant Operation; Operation, Maintenance and Reliability; Improving Performance and Reducing O and M Costs; Plant Modernization and Retrofits); 5 - Plant Safety Assessment and Regulatory Issues (LOCA and non-LOCA Analysis Methodologies; LOCA and non-LOCA Plant Analyses; In-Vessel Retention; Containment Performance and Hydrogen Control; Advances in Severe Accident Analysis; Advances in Severe Accident

  14. WASTE ISOLATION PILOT PLANT (WIPP): THE NATIONS' SOLUTION TO NUCLEAR WASTE STORAGE AND DISPOSAL ISSUES

    SciTech Connect (OSTI)

    Lopez, Tammy Ann

    2014-07-17

    In the southeastern portion of my home state of New Mexico lies the Chihuahauan desert, where a transuranic (TRU), underground disposal site known as the Waste Isolation Pilot Plant (WIPP) occupies 16 square miles. Full operation status began in March 1999, the year I graduated from Los Alamos High School, in Los Alamos, NM, the birthplace of the atomic bomb and one of the nation’s main TRU waste generator sites. During the time of its development and until recently, I did not have a full grasp on the role Los Alamos was playing in regards to WIPP. WIPP is used to store and dispose of TRU waste that has been generated since the 1940s because of nuclear weapons research and testing operations that have occurred in Los Alamos, NM and at other sites throughout the United States (U.S.). TRU waste consists of items that are contaminated with artificial, man-made radioactive elements that have atomic numbers greater than uranium, or are trans-uranic, on the periodic table of elements and it has longevity characteristics that may be hazardous to human health and the environment. Therefore, WIPP has underground rooms that have been carved out of 2,000 square foot thick salt formations approximately 2,150 feet underground so that the TRU waste can be isolated and disposed of. WIPP has operated safely and successfully until this year, when two unrelated events occurred in February 2014. With these events, the safety precautions and measures that have been operating at WIPP for the last 15 years are being revised and improved to ensure that other such events do not occur again.

  15. Annual radiological environmental monitoring report: Watts Bar Nuclear Plant, 1992. Operations Services/Technical Programs

    SciTech Connect (OSTI)

    Not Available

    1993-04-01

    This report describes the preoperational environmental radiological monitoring program conducted by TVA in the vicinity of the Watts Bar Nuclear Plant (WBN) in 1992. The program includes the collection of samples from the environment and the determination of the concentrations of radioactive materials in the samples. Samples are taken from stations in the general area of the plant and from areas that will not be influenced by plant operations. Material sampled includes air, water, milk, foods, vegetation, soil, fish, sediment, and direct radiation levels. During plant operations, results from stations near the plant will be compared with concentrations from control stations and with preoperational measurements to determine potential impacts to the public. Exposures calculated from environmental samples were contributed by naturally occurring radioactive materials, from materials commonly found in the environment as a result of atmospheric fallout, or from the operation of other nuclear facilities in the area. Since WBN has not operated, there has been no contribution of radioactivity from the plant to the environment.

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

    SciTech Connect (OSTI)

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

    2002-07-01

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

  17. Auxiliary feedwater system risk-based inspection guide for the Ginna Nuclear Power Plant

    SciTech Connect (OSTI)

    Pugh, R.; Gore, B.F.; Vo, T.V.; Moffitt, N.E. )

    1991-09-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Ginna was selected as the eighth plant for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the Ginna plant. 23 refs., 1 fig., 1 tab.

  18. Auxiliary feedwater system risk-based inspection guide for the South Texas Project nuclear power plant

    SciTech Connect (OSTI)

    Bumgardner, J.D.; Nickolaus, J.R.; Moffitt, N.E.; Gore, B.F.; Vo, T.V.

    1993-12-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. South Texas Project was selected as a plant for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by the NRC inspectors in preparation of inspection plans addressing AFW risk important components at the South Texas Project plant.

  19. Auxiliary feedwater system risk-based inspection guide for the McGuire nuclear power plant

    SciTech Connect (OSTI)

    Bumgardner, J.D.; Lloyd, R.C.; Moffitt, N.E.; Gore, B.F.; Vo, T.V.

    1994-05-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. McGuire was selected as one of a series of plants for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the McGuire plant.

  20. Auxiliary feedwater system risk-based inspection guide for the Point Beach nuclear power plant

    SciTech Connect (OSTI)

    Lloyd, R C; Moffitt, N E; Gore, B F; Vo, T V; Vehec, T A

    1993-02-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Point Beach was selected as one of a series of plants for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRS. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the Point Beach plant.

  1. Auxiliary feedwater system risk-based inspection guide for the J. M. Farley Nuclear Power Plant

    SciTech Connect (OSTI)

    Vo, T.V.; Pugh, R.; Gore, B.F.; Harrison, D.G. )

    1990-10-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment(PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. J. M. Farley was selected as the second plant for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important at the J. M. Farley plant. 23 refs., 1 fig., 1 tab.

  2. Auxiliary feedwater system risk-based inspection guide for the H. B. Robinson nuclear power plant

    SciTech Connect (OSTI)

    Moffitt, N.E.; Lloyd, R.C.; Gore, B.F.; Vo, T.V.; Garner, L.W.

    1993-08-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. H. B. Robinson was selected as one of a series of plants for study. The product of this effort is a prioritized listing of AFW failures which have occurred at the plant and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the H. B. Robinson plant.

  3. Method of installing a control room console in a nuclear power plant

    DOE Patents [OSTI]

    Scarola, Kenneth; Jamison, David S.; Manazir, Richard M.; Rescorl, Robert L.; Harmon, Daryl L.

    1994-01-01

    An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system (72) which is nuclear qualified for rapid response to changes in plant parameters and a component control system (64) which together provide a discrete monitoring and control capability at a panel (14-22, 26, 28) in the control room (10). A separate data processing system (70), which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs (84) and a large, overhead integrated process status overview board (24). The discrete indicator and alarm system (72) and the data processing system (70) receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board (24) is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof.

  4. COOLING WATER ISSUES AND OPPORTUNITIES AT U.S. NUCLEAR POWER PLANTS

    SciTech Connect (OSTI)

    Gary Vine

    2010-12-01

    This report has been prepared for the Department of Energy, Office of Nuclear Energy (DOE-NE), for the purpose of providing a status report on the challenges and opportunities facing the U.S. commercial nuclear energy industry in the area of plant cooling water supply. The report was prompted in part by recent Second Circuit and Supreme Court decisions regarding cooling water system designs at existing thermo-electric power generating facilities in the U.S. (primarily fossil and nuclear plants). At issue in the courts have been Environmental Protection Agency regulations that define what constitutes “Best Technology Available” for intake structures that withdraw cooling water that is used to transfer and reject heat from the plant’s steam turbine via cooling water systems, while minimizing environmental impacts on aquatic life in nearby water bodies used to supply that cooling water. The report was also prompted by a growing recognition that cooling water availability and societal use conflicts are emerging as strategic energy and environmental issues, and that research and development (R&D) solutions to emerging water shortage issues are needed. In particular, cooling water availability is an important consideration in siting decisions for new nuclear power plants, and is an under-acknowledged issue in evaluating the pros and cons of retrofitting cooling towers at existing nuclear plants. Because of the significant ongoing research on water issues already being performed by industry, the national laboratories and other entities, this report relies heavily on ongoing work. In particular, this report has relied on collaboration with the Electric Power Research Institute (EPRI), including its recent work in the area of EPA regulations governing intake structures in thermoelectric cooling water systems.

  5. Space Nuclear Power Plant Pre-Conceptual Design Report, For Information

    SciTech Connect (OSTI)

    B. Levine

    2006-01-27

    This letter transmits, for information, the Project Prometheus Space Nuclear Power Plant (SNPP) Pre-Conceptual Design Report completed by the Naval Reactors Prime Contractor Team (NRPCT). This report documents the work pertaining to the Reactor Module, which includes integration of the space nuclear reactor with the reactor radiation shield, energy conversion, and instrumentation and control segments. This document also describes integration of the Reactor Module with the Heat Rejection segment, the Power Conditioning and Distribution subsystem (which comprise the SNPP), and the remainder of the Prometheus spaceship.

  6. Application of Entry-Time Processes in Asset Management for Nuclear Power Plants (Final Report)

    SciTech Connect (OSTI)

    Paul Nelson

    2008-01-23

    A mathematical model of entry-time processes was developed, and a computational method for solving that model was verified. This methodology was demonstrated via application to a succession of increasingly more complex subsystems of nuclear power plants. The effort culminated in the application to main generators that constituted the PhD dissertation of Shuwen (Eric) Wang. Dr. Wang is now employed by ABS Consulting, in Anaheim, CA. ABS is a principal provider to the nuclear industry of technical services related to reliability and safety.

  7. Validation of smart sensor technologies for instrument calibration reduction in nuclear power plants

    SciTech Connect (OSTI)

    Hashemian, H M; Mitchell, D W; Petersen, K M; Shell, C S

    1993-01-01

    This report presents the preliminary results of a research and development project on the validation of new techniques for on-line testing of calibration drift of process instrumentation channels in nuclear power plants. These techniques generally involve a computer-based data acquisition and data analysis system to trend the output of a large number of instrument channels and identify the channels that have drifted out of tolerance. This helps limit the calibration effort to those channels which need the calibration, as opposed to the current nuclear industry practice of calibrating essentially all the safety-related instrument channels at every refueling outage.

  8. Nuclear criticality safety evaluation of large cylinder cleaning operations in X-705, Portsmouth Gaseous diffusion Plant

    SciTech Connect (OSTI)

    Sheaffer, M.K.; Keeton, S.C.; Lutz, H.F.

    1995-06-01

    This report evaluates nuclear criticality safety for large cylinder cleaning operations in the Decontamination and Recovery Facility, X-705, at the Portsmouth Gaseous Diffusion Plant. A general description of current cleaning procedures and required hardware/equipment is presented, and documentation for large cylinder cleaning operations is identified and described. Control parameters, design features, administrative controls, and safety systems relevant to nuclear criticality are discussed individually, followed by an overall assessment based on the Double Contingency Principle. Recommendations for enhanced safety are suggested, and issues for increased efficiency are presented.

  9. Technical cooperation on nuclear security between the United States and China : review of the past and opportunities for the future.

    SciTech Connect (OSTI)

    Pregenzer, Arian Leigh

    2011-12-01

    The United States and China are committed to cooperation to address the challenges of the next century. Technical cooperation, building on a long tradition of technical exchange between the two countries, can play an important role. This paper focuses on technical cooperation between the United States and China in the areas of nonproliferation, arms control and other nuclear security topics. It reviews cooperation during the 1990s on nonproliferation and arms control under the U.S.-China Arms Control Exchange, discusses examples of ongoing activities under the Peaceful Uses of Technology Agreement to enhance security of nuclear and radiological material, and suggests opportunities for expanding technical cooperation between the defense nuclear laboratories of both countries to address a broader range of nuclear security topics.

  10. Development of a Flexible Computerized Management Infrastructure for a Commercial Nuclear Power Plant

    SciTech Connect (OSTI)

    Ali, Syed Firasat; Hajek, Brian K.; Usman, Shoaib

    2006-05-01

    The report emphasizes smooth transition from paper-based procedure systems (PBPSs) to computer-based procedure systems (CBPSs) for the existing commercial nuclear power plants in the U.S. The expected advantages and of the transition are mentioned including continued, safe and efficient operation of the plants under their recently acquired or desired extended licenses. The report proposes a three-stage survey to aid in developing a national strategic plan for the transition from PBPSs to CBPSs. It also includes a comprehensive questionnaire that can be readily used for the first stage of the suggested survey.

  11. PROGRESS IN REDUCING THE NUCLEAR THREAT: UNITED STATES PLUTONIUM CONSOLIDATION AND DISPOSITION

    SciTech Connect (OSTI)

    Allender, J.; Koenig, R.; Davies, S.

    2009-06-01

    Following the end of the Cold War, the United States identified 61.5 metric tons (MT) of plutonium and larger quantities of enriched uranium that are permanently excess to use in nuclear weapons programs. The Department of Energy (DOE) also began shutting down, stabilizing, and removing inventories from production facilities that were no longer needed to support weapons programs and non-weapons activities. The storage of 'Category I' nuclear materials at Rocky Flats, Sandia National Laboratories, and several smaller sites has been terminated to reduce costs and safeguards risks. De-inventory continues at the Hanford site and the Lawrence Livermore National Laboratory. Consolidation of inventories works in concert with the permanent disposition of excess inventories, including several tonnes of plutonium that have already been disposed to waste repositories and the preparation for transfers to the planned Mixed Oxide (MOX) Fuel Fabrication Facility (for the bulk of the excess plutonium) and alternative disposition methods for material that cannot be used readily in the MOX fuel cycle. This report describes status of plutonium consolidation and disposition activities and their impacts on continuing operations, particularly at the Savannah River Site.

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

    SciTech Connect (OSTI)

    Bergmann, P.A.

    1982-07-01

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

  13. Auxiliary feedwater system risk-based inspection guide for the Byron and Braidwood nuclear power plants

    SciTech Connect (OSTI)

    Moffitt, N.E.; Gore, B.F.: Vo, T.V. )

    1991-07-01

    In a study sponsored by the US Nuclear Regulatory Commission (NRC), Pacific Northwest Laboratory has developed and applied a methodology for deriving plant-specific risk-based inspection guidance for the auxiliary feedwater (AFW) system at pressurized water reactors that have not undergone probabilistic risk assessment (PRA). This methodology uses existing PRA results and plant operating experience information. Existing PRA-based inspection guidance information recently developed for the NRC for various plants was used to identify generic component failure modes. This information was then combined with plant-specific and industry-wide component information and failure data to identify failure modes and failure mechanisms for the AFW system at the selected plants. Byron and Braidwood were selected for the fourth study in this program. The produce of this effort is a prioritized listing of AFW failures which have occurred at the plants and at other PWRs. This listing is intended for use by NRC inspectors in the preparation of inspection plans addressing AFW risk-important components at the Byron/Braidwood plants. 23 refs., 1 fig., 1 tab.

  14. Devices and methods for managing noncombustible gasses in nuclear power plants

    DOE Patents [OSTI]

    Marquino, Wayne; Moen, Stephan C; Wachowiak, Richard M; Gels, John L; Diaz-Quiroz, Jesus; Burns, Jr., John C

    2014-12-23

    Systems passively eliminate noncondensable gasses from facilities susceptible to damage from combustion of built-up noncondensable gasses, such as H2 and O2 in nuclear power plants, without the need for external power and/or moving parts. Systems include catalyst plates installed in a lower header of the Passive Containment Cooling System (PCCS) condenser, a catalyst packing member, and/or a catalyst coating on an interior surface of a condensation tube of the PCCS condenser or an annular outlet of the PCCS condenser. Structures may have surfaces or hydrophobic elements that inhibit water formation and promote contact with the noncondensable gas. Noncondensable gasses in a nuclear power plant are eliminated by installing and using the systems individually or in combination. An operating pressure of the PCCS condenser may be increased to facilitate recombination of noncondensable gasses therein.

  15. Uncertainty Quantification Techniques for Sensor Calibration Monitoring in Nuclear Power Plants

    SciTech Connect (OSTI)

    Ramuhalli, Pradeep; Lin, Guang; Crawford, Susan L.; Konomi, Bledar A.; Braatz, Brett G.; Coble, Jamie B.; Shumaker, Brent; Hashemian, Hash

    2013-09-01

    This report describes the status of ongoing research towards the development of advanced algorithms for online calibration monitoring. The objective of this research is to develop the next generation of online monitoring technologies for sensor calibration interval extension and signal validation in operating and new reactors. These advances are expected to improve the safety and reliability of current and planned nuclear power systems as a result of higher accuracies and increased reliability of sensors used to monitor key parameters. The focus of this report is on documenting the outcomes of the first phase of R&D under this project, which addressed approaches to uncertainty quantification (UQ) in online monitoring that are data-driven, and can therefore adjust estimates of uncertainty as measurement conditions change. Such data-driven approaches to UQ are necessary to address changing plant conditions, for example, as nuclear power plants experience transients, or as next-generation small modular reactors (SMR) operate in load-following conditions.

  16. A survey of repair practices for nuclear power plant containment metallic pressure boundaries

    SciTech Connect (OSTI)

    Oland, C.B.; Naus, D.J.

    1998-05-01

    The Nuclear Regulatory Commission has initiated a program at the Oak Ridge National Laboratory to provide assistance in their assessment of the effects of potential degradation on the structural integrity and leaktightness of metal containment vessels and steel liners of concrete containments in nuclear power plants. One of the program objectives is to identify repair practices for restoring metallic containment pressure boundary components that have been damaged or degraded in service. This report presents issues associated with inservice condition assessments and continued service evaluations and identifies the rules and requirements for the repair and replacement of nonconforming containment pressure boundary components by welding or metal removal. Discussion topics include base and welding materials, welding procedure and performance qualifications, inspection techniques, testing methods, acceptance criteria, and documentation requirements necessary for making acceptable repairs and replacements so that the plant can be returned to a safe operating condition.

  17. Uncertainty Quantification Techniques for Sensor Calibration Monitoring in Nuclear Power Plants

    SciTech Connect (OSTI)

    Ramuhalli, Pradeep; Lin, Guang; Crawford, Susan L.; Konomi, Bledar A.; Coble, Jamie B.; Shumaker, Brent; Hashemian, Hash

    2014-04-30

    This report describes research towards the development of advanced algorithms for online calibration monitoring. The objective of this research is to develop the next generation of online monitoring technologies for sensor calibration interval extension and signal validation in operating and new reactors. These advances are expected to improve the safety and reliability of current and planned nuclear power systems as a result of higher accuracies and increased reliability of sensors used to monitor key parameters. The focus of this report is on documenting the outcomes of the first phase of R&D under this project, which addressed approaches to uncertainty quantification (UQ) in online monitoring that are data-driven, and can therefore adjust estimates of uncertainty as measurement conditions change. Such data-driven approaches to UQ are necessary to address changing plant conditions, for example, as nuclear power plants experience transients, or as next-generation small modular reactors (SMR) operate in load-following conditions.

  18. Summary and analysis of public comments on NUREG-1317: Regulatory options for nuclear plant license renewal: Final report

    SciTech Connect (OSTI)

    Ligon, D.M.; Seth, S.S.

    1989-03-01

    On August 29, 1988, the US Nuclear Regulatory Commission (NRC) issued an Advance Notice of Proposed Rulemaking on nuclear plant license renewal and solicited public comments on NUREG-1317, ''Regulatory Options for Nuclear Plant License Renewal.'' NUREG-1317 presents a discussion of fifteen topics involving technical, environmental, and procedural issues and poses a set of related questions. As part of its ongoing task for the NRC, The MITRE Corporation has summarized and analyzed the public comments received. Fifty-three written comments were received. Of these, 83 percent were from nuclear industry representatives; the remaining comments represented federal and state agencies, public interest groups, and a private citizen.

  19. Separation Requirements for a Hydrogen Production Plant and High-Temperature Nuclear Reactor

    SciTech Connect (OSTI)

    Curtis Smith; Scott Beck; Bill Galyean

    2005-09-01

    This report provides the methods, models, and results of an evaluation for locating a hydrogen production facility near a nuclear power plant. In order to answer the risk-related questions for this combined nuclear and chemical facility, we utilized standard probabilistic safety assessment methodologies to answer three questions: what can happen, how likely is it, and what are the consequences? As part of answering these questions, we developed a model suitable to determine separation distances for hydrogen process structures and the nuclear plant structures. Our objective of the model-development and analysis is to answer key safety questions related to the placement of one or more hydrogen production plants in the vicinity of a high-temperature nuclear reactor. From a thermal-hydraulic standpoint we would like the two facilities to be quite close. However, safety and regulatory implications force the separation distance to be increased, perhaps substantially. Without answering these safety questions, the likelihood for obtaining a permit to construct and build such as facility in the U.S. would be questionable. The quantitative analysis performed for this report provides us with a scoping mechanism to determine key parameters related to the development of a nuclear-based hydrogen production facility. From our calculations, we estimate that when the separation distance is less than 100m, the core damage frequency is large enough (greater than 1E-6/yr) to become problematic in a risk-informed environment. However, a variety of design modifications, for example blast-deflection barriers, were explored to determine the impact of potential mitigating strategies. We found that these mitigating cases may significantly reduce risk and should be explored as the design for the hydrogen production facility evolves.

  20. DOE Releases Filing Instructions for Federal Risk Insurance for New Nuclear

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

    Power Plants | Department of Energy Filing Instructions for Federal Risk Insurance for New Nuclear Power Plants DOE Releases Filing Instructions for Federal Risk Insurance for New Nuclear Power Plants December 21, 2007 - 4:58pm Addthis Outlines Five Steps for New Nuclear Plant Sponsors to Enter Into a Conditional Agreement for Risk Insurance WASHINGTON, DC - The U.S. Department of Energy (DOE) today released instructions for companies building new nuclear power plants in the United States to

  1. Land-Use Requirements for Solar Power Plants in the United States

    SciTech Connect (OSTI)

    Ong, S.; Campbell, C.; Denholm, P.; Margolis, R.; Heath, G.

    2013-06-01

    This report provides data and analysis of the land use associated with utility-scale ground-mounted solar facilities, defined as installations greater than 1 MW. We begin by discussing standard land-use metrics as established in the life-cycle assessment literature and then discuss their applicability to solar power plants. We present total and direct land-use results for various solar technologies and system configurations, on both a capacity and an electricity-generation basis. The total area corresponds to all land enclosed by the site boundary. The direct area comprises land directly occupied by solar arrays, access roads, substations, service buildings, and other infrastructure. As of the third quarter of 2012, the solar projects we analyze represent 72% of installed and under-construction utility-scale PV and CSP capacity in the United States.

  2. Application of a model-based fault detection system to nuclear plant signals

    SciTech Connect (OSTI)

    Gross, K.C.; Singer, R.M.; Wegerich, S.W.; Herzog, J.P.; VanAlstine, R.; Bockhorst, F.

    1997-05-01

    To assure the continued safe and reliable operation of a nuclear power station, it is essential that accurate online information on the current state of the entire system be available to the operators. Such information is needed to determine the operability of safety and control systems, the condition of active components, the necessity of preventative maintenance, and the status of sensory systems. To this end, ANL has developed a new Multivariate State Estimation Technique (MSET) which utilizes advanced pattern recognition methods to enhance sensor and component operational validation for commercial nuclear reactors. Operational data from the Crystal River-3 (CR-3) nuclear power plant are used to illustrate the high sensitivity, accuracy, and the rapid response time of MSET for annunciation of a variety of signal disturbances.

  3. Data base on dose reduction research projects for nuclear power plants. Volume 5

    SciTech Connect (OSTI)

    Khan, T.A.; Yu, C.K.; Roecklein, A.K.

    1994-05-01

    This is the fifth volume in a series of reports that provide information on dose reduction research and health physics technology or nuclear power plants. The information is taken from two of several databases maintained by Brookhaven National Laboratory`s ALARA Center for the Nuclear Regulatory Commission. The research section of the report covers dose reduction projects that are in the experimental or developmental phase. It includes topics such as steam generator degradation, decontamination, robotics, improvements in reactor materials, and inspection techniques. The section on health physics technology discusses dose reduction efforts that are in place or in the process of being implemented at nuclear power plants. A total of 105 new or updated projects are described. All project abstracts from this report are available to nuclear industry professionals with access to a fax machine through the ACEFAX system or a computer with a modem and the proper communications software through the ACE system. Detailed descriptions of how to access all the databases electronically are in the appendices of the report.

  4. Nuclear pursuits

    SciTech Connect (OSTI)

    Not Available

    1993-05-01

    This table lists quantities of warheads (in stockpile, peak number per year, total number built, number of known test explosions), weapon development milestones (developers of the atomic bomb and hydrogen bomb, date of first operational ICBM, first nuclear-powered naval SSN in service, first MIRVed missile deployed), and testing milestones (first fission test, type of boosted fission weapon, multistage thermonuclear test, number of months from fission bomb to multistage thermonuclear bomb, etc.), and nuclear infrastructure (assembly plants, plutonium production reactors, uranium enrichment plants, etc.). Countries included in the tally are the United States, Soviet Union, Britain, France, and China.

  5. Knowledge and abilities catalog for nuclear power plant operators: Boiling water reactors, Revision 1

    SciTech Connect (OSTI)

    1995-08-01

    The Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Boiling-Water Reactors (BWRs) (NUREG-1123, Revision 1) provides the basis for the development of content-valid licensing examinations for reactor operators (ROs) and senior reactor operators (SROs). The examinations developed using the BWR Catalog along with the Operator Licensing Examiner Standards (NUREG-1021) and the Examiner`s Handbook for Developing Operator Licensing Written Examinations (NUREG/BR-0122), will cover the topics listed under Title 10, Code of Federal Regulations, Part 55 (10 CFR 55). The BWR Catalog contains approximately 7,000 knowledge and ability (K/A) statements for ROs and SROs at BWRs. The catalog is organized into six major sections: Organization of the Catalog, Generic Knowledge and Ability Statements, Plant Systems grouped by Safety Functions, Emergency and Abnormal Plant Evolutions, Components, and Theory. Revision 1 to the BWR Catalog represents a modification in form and content of the original catalog. The K/As were linked to their applicable 10 CFR 55 item numbers. SRO level K/As were identified by 10 CFR 55.43 item numbers. The plant-wide generic and system generic K/As were combined in one section with approximately one hundred new K/As. Component Cooling Water and Instrument Air Systems were added to the Systems Section. Finally, High Containment Hydrogen Concentration and Plant Fire On Site evolutions added to the Emergency and Abnormal Plant Evolutions section.

  6. Integrated deterministic and probabilistic safety analysis for safety assessment of nuclear power plants

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

    Di Maio, Francesco; Zio, Enrico; Smith, Curtis; Rychkov, Valentin

    2015-07-06

    The present special issue contains an overview of the research in the field of Integrated Deterministic and Probabilistic Safety Assessment (IDPSA) of Nuclear Power Plants (NPPs). Traditionally, safety regulation for NPPs design and operation has been based on Deterministic Safety Assessment (DSA) methods to verify criteria that assure plant safety in a number of postulated Design Basis Accident (DBA) scenarios. Referring to such criteria, it is also possible to identify those plant Structures, Systems, and Components (SSCs) and activities that are most important for safety within those postulated scenarios. Then, the design, operation, and maintenance of these “safety-related” SSCs andmore » activities are controlled through regulatory requirements and supported by Probabilistic Safety Assessment (PSA).« less

  7. Aging Management Guideline for commercial nuclear power plants: Power and distribution transformers

    SciTech Connect (OSTI)

    Toman, G.; Gazdzinski, R.

    1994-05-01

    This Aging Management Guideline (AMG) provides recommended methods for effective detection and mitigation of age-related degradation mechanisms in power and distribution transformers important to license renewal in commercial nuclear power plants. The intent of this AMG to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner which allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein.

  8. Aging Management Guideline for commercial nuclear power plants: Motor control centers; Final report

    SciTech Connect (OSTI)

    Toman, G.; Gazdzinski, R.; O`Hearn, E.

    1994-02-01

    This Aging Management Guideline (AMG) provides recommended methods for effective detection and mitigation of age-related degradation mechanisms in Boiling Water Reactor (BWR) and Pressurized Water Reactor (PWR) commercial nuclear power plant motor control centers important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein.

  9. Aging management guideline for commercial nuclear power plants-stationary batteries. Final report

    SciTech Connect (OSTI)

    Berg, R.; Shao, J.; Krencicki, G.; Giachetti, R.

    1994-03-01

    The Aging Management Guideline (AMG) describes recommended methods for effective detection and mitigation of age-related degradation mechanisms in BWR and PWR commercial nuclear power plant stationary batteries important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein.

  10. Aging Management Guideline for commercial nuclear power plants: Electrical switchgear. Final report

    SciTech Connect (OSTI)

    Toman, G.; Gazdzinski, R.; Schuler, K.

    1993-07-01

    This Aging Management Guideline (AMG) provides recommended methods for effective detection and mitigation of age-related degradation mechanisms in BWR and PWR commercial nuclear power plant electrical switchgear important to license renewal. The latent of this AMG to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner which allows personnel responsible for performance analysis and maintenance, to compare their plant-specific aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein.

  11. Integrated deterministic and probabilistic safety analysis for safety assessment of nuclear power plants

    SciTech Connect (OSTI)

    Di Maio, Francesco; Zio, Enrico; Smith, Curtis; Rychkov, Valentin

    2015-07-06

    The present special issue contains an overview of the research in the field of Integrated Deterministic and Probabilistic Safety Assessment (IDPSA) of Nuclear Power Plants (NPPs). Traditionally, safety regulation for NPPs design and operation has been based on Deterministic Safety Assessment (DSA) methods to verify criteria that assure plant safety in a number of postulated Design Basis Accident (DBA) scenarios. Referring to such criteria, it is also possible to identify those plant Structures, Systems, and Components (SSCs) and activities that are most important for safety within those postulated scenarios. Then, the design, operation, and maintenance of these “safety-related” SSCs and activities are controlled through regulatory requirements and supported by Probabilistic Safety Assessment (PSA).

  12. Abnormal event identification in nuclear power plants using a neural network and knowledge processing

    SciTech Connect (OSTI)

    Ohga, Yukiharu; Seki, Hiroshi (Hitachi, Ltd. Energy Research Lab., Ibarakiken (Japan))

    1993-02-01

    The combination of a neural network and knowledge processing have been used to identify abnormal events that cause a reactor to scram in a nuclear power plant. The neural network recognizes the abnormal event from the change pattern of analog data for state variables, and this result is confirmed from digital data using a knowledge base of plant status when each event occurs. The event identification method is tested using test data based on simulated results of a transient analysis program for boiling water reactors. It is confirmed that a neural network can identify an event in which it has been trained even when the plant conditions, such as fuel burnup, differ from those used in the training and when the analog data contain white noise. The network does not mistakenly identify the nontrained event as a trained one. The method is feasible for event identification, and knowledge processing improves the reliability of the identification.

  13. Combustion systems and power plants incorporating parallel carbon dioxide capture and sweep-based membrane separation units to remove carbon dioxide from combustion gases

    DOE Patents [OSTI]

    Wijmans, Johannes G.; Merkel, Timothy C; Baker, Richard W.

    2011-10-11

    Disclosed herein are combustion systems and power plants that incorporate sweep-based membrane separation units to remove carbon dioxide from combustion gases. In its most basic embodiment, the invention is a combustion system that includes three discrete units: a combustion unit, a carbon dioxide capture unit, and a sweep-based membrane separation unit. In a preferred embodiment, the invention is a power plant including a combustion unit, a power generation system, a carbon dioxide capture unit, and a sweep-based membrane separation unit. In both of these embodiments, the carbon dioxide capture unit and the sweep-based membrane separation unit are configured to be operated in parallel, by which we mean that each unit is adapted to receive exhaust gases from the combustion unit without such gases first passing through the other unit.

  14. United States and Czech Republic Join Together to Announce Bilateral Nuclear Energy Research and Development Efforts

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy recently joined with the Rež Nuclear Research Institute, the U.S. Embassy in Prague, Texas A&M and the Czech Nuclear Education Network (CENEN) to announce a series of bilateral nuclear research and development programs that will help to advance safe and secure nuclear energy technologies in both countries.

  15. Control room modernization at Finnish nuclear power plants - Two projects compared

    SciTech Connect (OSTI)

    Laarni, J.; Norros, L.

    2006-07-01

    The modernization of automation systems and human-machine interfaces is a current issue at both of the two nuclear power plants (i.e., Fortum's Loviisa plant and TVO's Olkiluoto plant) in Finland. Since the plants have been launched in the 1970's or 1980's, technology is in part old-fashioned and needs to be renewed. At Olkiluoto upgrades of the turbine operator systems have already been conducted; at Loviisa the first phase of the modernization project has just started. Basically, there is a question of the complete digitalization of the information streams at the two plants, and transition from a conventional hard-wired or hybrid control room to a screen-based one. The new human-machine interfaces will comprise new technology, such as PC workstations, soft control, touch screens and large-screen overall displays. The modernization of human-system interfaces is carried out in a stepwise manner at both plants. At both plants the main driver has not been the need to renew the user interfaces of the control room, but the need to upgrade the automation systems. In part because of this, there is a lack of a systematic top-down approach in which different aspects of human factors (HF) engineering are considered in relationship to higher level goals. Our aim here is to give an overview description of the control room modernization projects at the two plants and provide a preliminary evaluation of their progress to date. The projects are also compared, for example, in terms of duration, scope and phasing, and who is responsible for the realization of the project. In addition, we also compare experiences from the Finnish projects to experiences from similar projects abroad. The main part of the data used in this study is based on designers' and project members' interviews. (authors)

  16. NARAC Modeling During the Response to the Fukushima Dai-ichi Nuclear Power Plant Emergency

    SciTech Connect (OSTI)

    Sugiyama, G; Nasstrom, J S; Probanz, B; Foster, K T; Simpson, M; Vogt, P; Aluzzi, F; Dillon, M; Homann, S

    2012-02-14

    This paper summarizes the activities of the National Atmospheric Release Advisory Center (NARAC) during the Fukushima Dai-ichi nuclear power plant crisis. NARAC provided a wide range of products and analyses as part of its support including: (1) Daily Japanese weather forecasts and hypothetical release (generic source term) dispersion predictions to provide situational awareness and inform planning for U.S. measurement data collection and field operations; (2) Estimates of potential dose in Japan for hypothetical scenarios developed by the Nuclear Regulatory Commission (NRC) to inform federal government considerations of possible actions that might be needed to protect U.S. citizens in Japan; (3) Estimates of possible plume arrival times and dose for U.S. locations; and (4) Plume model refinement and source estimation based on meteorological analyses and available field data. The Department of Energy/National Nuclear Security Administration (DOE/NNSA) deployed personnel to Japan and stood up 'home team' assets across the DOE complex to aid in assessing the consequences of the releases from the Fukushima Dai-ichi Nuclear Power Plant. The DOE Nuclear Incident Team (NIT) coordinated response activities, while DOE personnel provided predictive modeling, air and ground monitoring, sample collection, laboratory analysis, and data assessment and interpretation. DOE deployed the Aerial Measuring System (AMS), Radiological Assistance Program (RAP) personnel, and the Consequence Management Response Team (CMRT) to Japan. DOE/NNSA home team assets included the Consequence Management Home Team (CMHT); National Atmospheric Release Advisory Center (NARAC); Radiation Emergency Assistance Center/Training Site (REAC/TS); and Radiological Triage. NARAC was activated by the DOE/NNSA on March 11, shortly after the Tohoku earthquake and tsunami occurred. The center remained on active operations through late May when DOE ended its deployment to Japan. Over 32 NARAC staff members

  17. THORP Thermal Oxide Reprocessing Plant | Open Energy Information

    Open Energy Info (EERE)

    Plant) Place: Cumbria, England, United Kingdom Zip: CA20 1PG Product: England-based nuclear fuel reprocessing plant. Coordinates: 54.63044, -2.89984 Show Map Loading map......

  18. Feasibility study for Zaporozhye Nuclear Power Plant spent fuel dry storage facility in Ukraine. Export trade information

    SciTech Connect (OSTI)

    1995-12-01

    This document reports the results of a Feasibility Study sponsored by a TDA grant to Zaporozhye Nuclear Power Plant (ZNPP) in Ukraine to study the construction of storage facilities for spent nuclear fuel. It provides pertinent information to U.S. companies interested in marketing spent fuel storage technology and related business to countries of the former Soviet Union or Eastern Europe.

  19. Investigation of Containment Flooding Strategy for Mark-III Nuclear Power Plant with MAAP4

    SciTech Connect (OSTI)

    Su Weinian; Wang, S.-J.; Chiang, S.-C

    2005-06-15

    Containment flooding is an important strategy for severe accident management of a conventional boiling water reactor (BWR) system. The purpose of this work is to investigate the containment flooding strategy of the Mark-III system after a reactor pressure vessel (RPV) breach. The Kuosheng Power Plant is a typical BWR-6 nuclear power plant (NPP) with Mark-III containment. The Severe Accident Management Guideline (SAMG) of the Kuosheng NPP has been developed based on the BWR Owners Group (BWROG) Emergency Procedure and Severe Accident Guidelines, Rev. 2. Therefore, the Kuosheng NPP is selected as the plant for study, and the MAAP4 code is chosen as the tool for analysis. A postulated specific station blackout sequence for the Kuosheng NPP is cited as a reference case for this analysis. Because of the design features of Mark-III containment, the debris in the reactor cavity may not be submerged after an RPV breach when one follows the containment flooding strategy as suggested in the BWROG generic guideline, and the containment integrity could be challenged eventually. A more specific containment flooding strategy with drywell venting after an RPV breach is investigated, and a more stable plant condition is achieved with this strategy. Accordingly, the containment flooding strategy after an RPV breach will be modified for the Kuosheng SAMG, and these results are applicable to typical Mark-III plants with drywell vent path.

  20. Environmental Problems Associated With Decommissioning The Chernobyl Nuclear Power Plant Cooling Pond

    SciTech Connect (OSTI)

    Farfan, E. B.; Jannik, G. T.; Marra, J. C.; Oskolkov, B. Ya.; Bondarkov, M. D.; Gaschak, S. P.; Maksymenko, A. M.; Maksymenko, V. M.; Martynenko, V. I.

    2009-11-09

    Decommissioning of nuclear power plants and other nuclear fuel cycle facilities has been an imperative issue lately. There exist significant experience and generally accepted recommendations on remediation of lands with residual radioactive contamination; however, there are hardly any such recommendations on remediation of cooling ponds that, in most cases, are fairly large water reservoirs. The literature only describes remediation of minor reservoirs containing radioactive silt (a complete closure followed by preservation) or small water reservoirs resulting in reestablishing natural water flows. Problems associated with remediation of river reservoirs resulting in flooding of vast agricultural areas also have been described. In addition, the severity of environmental and economic problems related to the remedial activities is shown to exceed any potential benefits of these activities. One of the large, highly contaminated water reservoirs that require either remediation or closure is Karachay Lake near the MAYAK Production Association in the Chelyabinsk Region of Russia where liquid radioactive waste had been deep well injected for a long period of time. Backfilling of Karachay Lake is currently in progress. It should be noted that secondary environmental problems associated with its closure are considered to be of less importance since sustaining Karachay Lake would have presented a much higher radiological risk. Another well-known highly contaminated water reservoir is the Chernobyl Nuclear Power Plant (ChNPP) Cooling Pond, decommissioning of which is planned for the near future. This study summarizes the environmental problems associated with the ChNPP Cooling Pond decommissioning.

  1. ENVIRONMENTAL PROBLEMS ASSOCIATED WITH DECOMMISSIONING THE CHERNOBYL NUCLEAR POWER PLANT COOLING POND

    SciTech Connect (OSTI)

    Farfan, E.

    2009-09-30

    Decommissioning of nuclear power plants and other nuclear fuel cycle facilities has been an imperative issue lately. There exist significant experience and generally accepted recommendations on remediation of lands with residual radioactive contamination; however, there are hardly any such recommendations on remediation of cooling ponds that, in most cases, are fairly large water reservoirs. The literature only describes remediation of minor reservoirs containing radioactive silt (a complete closure followed by preservation) or small water reservoirs resulting in reestablishing natural water flows. Problems associated with remediation of river reservoirs resulting in flooding of vast agricultural areas also have been described. In addition, the severity of environmental and economic problems related to the remedial activities is shown to exceed any potential benefits of these activities. One of the large, highly contaminated water reservoirs that require either remediation or closure is Karachay Lake near the MAYAK Production Association in the Chelyabinsk Region of Russia where liquid radioactive waste had been deep well injected for a long period of time. Backfilling of Karachay Lake is currently in progress. It should be noted that secondary environmental problems associated with its closure are considered to be of less importance since sustaining Karachay Lake would have presented a much higher radiological risk. Another well-known highly contaminated water reservoir is the Chernobyl Nuclear Power Plant (ChNPP) Cooling Pond, decommissioning of which is planned for the near future. This study summarizes the environmental problems associated with the ChNPP Cooling Pond decommissioning.

  2. 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.

  3. Testing, licensing, and code requirements for seismic isolation systems (for nuclear power plants)

    SciTech Connect (OSTI)

    Seidensticker, R.W.

    1987-01-01

    The use of seismic isolation as an earthquake hazard mitigation strategy for nuclear reactor power plants is rapidly receiving interest throughout the world. Seismic isolation has already been used on at least two French PWR plants, was to have been used for plants to be built in Iran, and is under serious consideration for advanced LMR plants (in the US, UK, France, and Japan). In addition, there is a growing use of seismic isolation throughout the world for other critical facilities such as hospitals, emergency facilities, buildings with very high-cost equipment (e.g., computers) and as a strategy to reduce loss of life and expensive equipment in earthquakes. Such a design approach is in complete contrast to the conventional seismic design strategy in which the structure and components are provided with sufficient strength and ductility to resist the earthquake forces and to prevent structural collapses or failure. The use of seismic isolation for nuclear plants can, therefore, be expected to be a significant licensing issue. For isolation, the licensing process must shift away in large measure from the superstructure and concentrate on the behavior of the seismic isolation system. This paper is not intended to promote the advantages of seismic isolation system, but to explore in some detail those technical issues which must be satisfactorily addressed to achieve full licensability of the use of seismic isolation as a viable, attractive and economical alternative to current traditional design approaches. Special problems and topics associated with testing and codes and standards development are addressed. A positive program for approach or strategy to secure licensing is presented.

  4. Waste management units - Savannah River Site

    SciTech Connect (OSTI)

    Not Available

    1989-10-01

    This report is a compilation of worksheets from the waste management units of Savannah River Plant. Information is presented on the following: Solid Waste Management Units having received hazardous waste or hazardous constituents with a known release to the environment; Solid Waste Management Units having received hazardous waste or hazardous constituents with no known release to the environment; Solid Waste Management Units having received no hazardous waste or hazardous constituents; Waste Management Units having received source; and special nuclear, or byproduct material only.

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

    SciTech Connect (OSTI)

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

    2007-04-05

    The Next Generation Nuclear Plant (NGNP), which is an advanced high temperature gas reactor (HTGR) concept with emphasis on production of both electricity and hydrogen, involves helium as the coolant and a closed-cycle gas turbine for power generation with a core outlet/gas turbine inlet temperature of 900-1000 C. In the indirect cycle system, an intermediate heat exchanger is used to transfer the heat from primary helium from the core to the secondary fluid, which can be helium, nitrogen/helium mixture, or a molten salt. The system concept for the vary high temperature reactor (VHTR) can be a reactor based on the prismatic block of the GT-MHR developed by a consortium led by General Atomics in the U.S. or based on the PBMR design developed by ESKOM of South Africa and British Nuclear Fuels of U.K. This report has made a preliminary assessment on the issues pertaining to the intermediate heat exchanger (IHX) for the NGNP. Two IHX designs namely, shell and tube and compact heat exchangers were considered in the assessment. Printed circuit heat exchanger, among various compact heat exchanger (HX) designs, was selected for the analysis. Irrespective of the design, the material considerations for the construction of the HX are essentially similar, except may be in the fabrication of the units. As a result, we have reviewed in detail the available information on material property data relevant for the construction of HX and made a preliminary assessment of several relevant factors to make a judicious selection of the material for the IHX. The assessment included four primary candidate alloys namely, Alloy 617 (UNS N06617), Alloy 230 (UNS N06230), Alloy 800H (UNS N08810), and Alloy X (UNS N06002) for the IHX. Some of the factors addressed in this report are the tensile, creep, fatigue, creep fatigue, toughness properties for the candidate alloys, thermal aging effects on the mechanical properties, American Society of Mechanical Engineers (ASME) Code compliance

  6. Prognostic and health management of active assets in nuclear power plants

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

    Agarwal, Vivek; Lybeck, Nancy; Pham, Binh T.; Rusaw, Richard; Bickford, Randall

    2015-06-04

    This study presents the development of diagnostic and prognostic capabilities for active assets in nuclear power plants (NPPs). The research was performed under the Advanced Instrumentation, Information, and Control Technologies Pathway of the Light Water Reactor Sustainability Program. Idaho National Laboratory researched, developed, implemented, and demonstrated diagnostic and prognostic models for generator step-up transformers (GSUs). The Fleet-Wide Prognostic and Health Management (FW-PHM) Suite software developed by the Electric Power Research Institute was used to perform diagnosis and prognosis. As part of the research activity, Idaho National Laboratory implemented 22 GSU diagnostic models in the Asset Fault Signature Database and twomore » wellestablished GSU prognostic models for the paper winding insulation in the Remaining Useful Life Database of the FW-PHM Suite. The implemented models along with a simulated fault data stream were used to evaluate the diagnostic and prognostic capabilities of the FW-PHM Suite. Knowledge of the operating condition of plant asset gained from diagnosis and prognosis is critical for the safe, productive, and economical long-term operation of the current fleet of NPPs. This research addresses some of the gaps in the current state of technology development and enables effective application of diagnostics and prognostics to nuclear plant assets.« less

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

    SciTech Connect (OSTI)

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

    2007-09-01

    DOE has selected the High Temperature Gas-cooled Reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production. It will have an outlet gas temperature in the range of 950°C and a plant design service life of 60 years. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed reactor and use low-enriched uranium, TRISO-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. Some of the general and administrative aspects of the R&D Plan include: • Expand American Society of Mechanical Engineers (ASME) Codes and American Society for Testing and Materials (ASTM) Standards in support of the NGNP Materials R&D Program. • Define and develop inspection needs and the procedures for those inspections. • Support selected university materials related R&D activities that would be of direct benefit to the NGNP Project. • Support international materials related collaboration activities through the DOE sponsored Generation IV International Forum (GIF) Materials and Components (M&C) Project Management Board (PMB). • Support document review activities through the Materials Review Committee (MRC) or other suitable forum.

  8. Protection of Nuclear Plants Against Vehicular Bombs Via Full Spectrum Risk Assessment

    SciTech Connect (OSTI)

    Campagna, M. S.; Sawruk, W.

    2003-02-25

    A more urgent need now exists since 9/11 to protect vital assets at nuclear plants from physical security threats. Any approach to successful defense must result in the best possible risk profile , while also performing this defense against credible threats within the context of limited personnel and materiel resources. Engineered solutions need to be well thought out, and take advantage of each plant's available organic strengths and opportunities. A robust, well trained/equipped highly motivated protective force will help reduce concerns where there are weaknesses making the plant vulnerable to threats. A thorough risk assessment takes into account the proper combination of both deterministic and probabilistic application of resources as a most advantageous approach; this is postulated to be development of integrated protection methods and plans, which blend solid engineering design with the highest caliber of protection forces. By setting a clear and ambitious objective to shield the nuclear assets with this type of dynamic full spectrum defense in depth, the risk of harm-breach or likelihood of any opponent's threat being realized should be reduced to the lowest practicable levels.

  9. A method to select human-system interfaces for nuclear power plants

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

    Hugo, Jacques Victor; Gertman, David Ira

    2015-10-19

    The new generation of nuclear power plants (NPPs) will likely make use of state-of-the-art technologies in many areas of the plant. The analysis, design, and selection of advanced human–system interfaces (HSIs) constitute an important part of power plant engineering. Designers need to consider the new capabilities afforded by these technologies in the context of current regulations and new operational concepts, which is why they need a more rigorous method by which to plan the introduction of advanced HSIs in NPP work areas. Much of current human factors research stops at the user interface and fails to provide a definitive processmore » for integration of end user devices with instrumentation and control (I&C) and operational concepts. The current lack of a clear definition of HSI technology, including the process for integration, makes characterization and implementation of new and advanced HSIs difficult. This paper describes how new design concepts in the nuclear industry can be analyzed and how HSI technologies associated with new industrial processes might be considered. Furthermore, it also describes a basis for an understanding of human as well as technology characteristics that could be incorporated into a prioritization scheme for technology selection and deployment plans.« less

  10. Prognostic and health management of active assets in nuclear power plants

    SciTech Connect (OSTI)

    Agarwal, Vivek; Lybeck, Nancy; Pham, Binh T.; Rusaw, Richard; Bickford, Randall

    2015-06-04

    This study presents the development of diagnostic and prognostic capabilities for active assets in nuclear power plants (NPPs). The research was performed under the Advanced Instrumentation, Information, and Control Technologies Pathway of the Light Water Reactor Sustainability Program. Idaho National Laboratory researched, developed, implemented, and demonstrated diagnostic and prognostic models for generator step-up transformers (GSUs). The Fleet-Wide Prognostic and Health Management (FW-PHM) Suite software developed by the Electric Power Research Institute was used to perform diagnosis and prognosis. As part of the research activity, Idaho National Laboratory implemented 22 GSU diagnostic models in the Asset Fault Signature Database and two wellestablished GSU prognostic models for the paper winding insulation in the Remaining Useful Life Database of the FW-PHM Suite. The implemented models along with a simulated fault data stream were used to evaluate the diagnostic and prognostic capabilities of the FW-PHM Suite. Knowledge of the operating condition of plant asset gained from diagnosis and prognosis is critical for the safe, productive, and economical long-term operation of the current fleet of NPPs. This research addresses some of the gaps in the current state of technology development and enables effective application of diagnostics and prognostics to nuclear plant assets.

  11. A method to select human-system interfaces for nuclear power plants

    SciTech Connect (OSTI)

    Hugo, Jacques Victor; Gertman, David Ira

    2015-10-19

    The new generation of nuclear power plants (NPPs) will likely make use of state-of-the-art technologies in many areas of the plant. The analysis, design, and selection of advanced human–system interfaces (HSIs) constitute an important part of power plant engineering. Designers need to consider the new capabilities afforded by these technologies in the context of current regulations and new operational concepts, which is why they need a more rigorous method by which to plan the introduction of advanced HSIs in NPP work areas. Much of current human factors research stops at the user interface and fails to provide a definitive process for integration of end user devices with instrumentation and control (I&C) and operational concepts. The current lack of a clear definition of HSI technology, including the process for integration, makes characterization and implementation of new and advanced HSIs difficult. This paper describes how new design concepts in the nuclear industry can be analyzed and how HSI technologies associated with new industrial processes might be considered. Furthermore, it also describes a basis for an understanding of human as well as technology characteristics that could be incorporated into a prioritization scheme for technology selection and deployment plans.

  12. Service experience, structural integrity, severe accidents, and erosion in nuclear and fossil plants. PVP-Volume 303

    SciTech Connect (OSTI)

    Paterson, S.R.; Bamford, W.H; Geraets, L.H.; Okazaki, M.; Cipolla, R.C.; Cowfer, C.D.; Means, K.H.

    1995-12-01

    The objective of this symposium was to disseminate information on service degradation and its prevention. Papers have been divided into the following topical sections: Service experience in nuclear plants; DOE high-level waste tank structural integrity panel--Summary reports; Severe accidents; Service experience in operating fossil power plants; and Erosion. Papers have been processed separately for inclusion on the data base.

  13. Nuclear power plant containment metallic pressure boundary materials and plans for collecting and presenting their properties

    SciTech Connect (OSTI)

    Oland, C.B.

    1995-04-01

    A program is being conducted at the Oak Ridge National Laboratory (ORNL to assist the Nuclear Regulatory Commission (NRC)) in their assessment of the effects of degradation (primarily corrosion) on the structural capacity and leaktight integrity of metal containments and steel liners of reinforced concrete structures in nuclear power plants. One of the program objectives is to characterize and quantify manifestations of corrosion on the properties of steels used to construct containment pressure boundary components. This report describes a plan for use in collecting and presenting data and information on ferrous alloys permitted for use in construction of pressure retaining components in concrete and metal containments. Discussions about various degradation mechanisms that could potentially affect the mechanical properties of these materials are also included. Conclusions and recommendations presented in this report will be used to guide the collection of data and information that will be used to prepare a material properties data base for containment steels.

  14. An overview of digital I and C system reliability analysis in nuclear power plants

    SciTech Connect (OSTI)

    Lu, L.

    2006-07-01

    The transition from analog to digital technology has occurred in industry as a whole. This has left those who still use analog systems in a tough situation because the suppliers are decreasing the amount of service and spare parts that they have on hand for analog systems. Therefore, the transition from analog to digital for the Instrumentation and Control systems in nuclear power plants is of no exception. Since safety is of paramount importance for nuclear industry, the reliability and safety of digital systems should be demonstrated in a systematic manner before they are being adopted. For the simplest digital systems, the hardware reliability and software reliability are two fundamental components for digital system reliability analysis. This paper provides a literature survey on the work that has been performed in this field. (authors)

  15. Application of the R6 failure assessment diagram to UK nuclear plant assessments

    SciTech Connect (OSTI)

    Green, D.; Daniels, B.D.; Ainsworth, R.A.

    1996-12-01

    The Failure Assessment Diagram (FAD) approach to fracture assessment has been used extensively in the UK nuclear power industry over many years. More recently the approach has been extended to account for creep strain which may occur at elevated temperature. Applications of the technique have concerned the demonstration of large critical defect size and leak-before-break arguments. This paper considers some of these applications, both with and without creep strain. The method and necessary input data are briefly reviewed and the results of the applications are discussed. The benefits derived from the approach are highlighted. It is concluded that the creep modified route provides an expedient extension to the well established (FAD) approach and has contributed significantly to nuclear plant safety justifications.

  16. United States and Czech Republic Join Together to Announce Bilateral Nuclear Energy Research and Development Efforts

    Broader source: Energy.gov [DOE]

    PRAGUE, Czech Republic — The U.S. Department of Energy recently joined with the Řež Nuclear Research Institute, the U.S. Embassy in Prague, Texas A&M and the Czech Nuclear Education Network ...

  17. United States-Russia Joint Statement on the Results of the Nuclear...

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

    Group meeting that took place on December 6-7, 2010. The Working Group meeting strengthened cooperation between the U.S. and Russia on civil nuclear energy and nuclear security. ...

  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. Independent Oversight Assessment of the Nuclear Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant, January 2012

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

    of Health, Safety and Security HSS Independent Oversight Assessment of Nuclear Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant January 2012 Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Enforcement and Oversight Abbreviations Used in this Report i Executive Summary iii Recommendations xi 1.0 Introduction 1 1.1 Background 2 1.2 Scope and Methodology 6 2.0 Current Safety

  20. 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).