National Library of Energy BETA

Sample records for operating nuclear power

  1. Institute of Nuclear Power Operations annual report, 1993

    SciTech Connect (OSTI)

    1993-12-31

    This annual report highlights the activities of the Institute of Nuclear Power Operations. The topics of the report include the president and chairmen`s joint message, overview of programs serving as the foundation for most of its activities, performance indicators for the US nuclear utility industry, and INPO`s 1993 financial reports and rosters. INPO has four technical cornerstone programs that serve as the foundation for most of its activities. (1) Evaluations of nuclear power plants operated by member utilities are conducted on a regularly scheduled basis. (2) INPO supports its member utilities in their work to achieve and maintain accreditation of training programs. (3) Events analysis programs identify and communicate lessons learned from plant events so utilities can take action to prevent similar events at their plants. (4) INPO helps members improve in nuclear operations areas through assistance programs and other activities that continually evolve to meet the changing needs of the nuclear industry.

  2. 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).

  3. U.S. Forward Operating Base Applications of Nuclear Power

    SciTech Connect (OSTI)

    Griffith, George W.

    2015-01-01

    This paper provides a high level overview of current nuclear power technology and the potential use of nuclear power at military bases. The size, power ranges, and applicability of nuclear power units for military base power are reviewed. Previous and current reactor projects are described to further define the potential for nuclear power for military power.

  4. Nuclear Power 2010 Program: Combined Construction and Operating...

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

    Power 2010 (NP 2010) Construction and Operating LicenseDesign Certification (COLDC) Demonstration program together with the financial incentives provided by the Energy Policy Act...

  5. 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.

  6. 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.

  7. 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.

  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. Nuclear Power 2010 Program: Combined Construction and Operating License & Design Certification Demonstration Projects Lessons Learned Report

    Broader source: Energy.gov [DOE]

    The Nuclear Power 2010 (NP 2010) Construction and Operating License/Design Certification (COL/DC) Demonstration program together with the financial incentives provided by the Energy Policy Act of 2005 are the two primary reasons why a number of license applications for new nuclear construction are before the NRC today, and why the first new nuclear plants in over 30 years are under construction in the United States.

  10. 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.

  11. 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.

  12. Sustainable Forward Operating Base Nuclear Power Evaluation (Relationship Mapping System) Users’ Manual

    SciTech Connect (OSTI)

    Not Listed

    2012-01-01

    The Sustainable Forward Operating Base (FOB) Nuclear Power Evaluation was developed by the Idaho National Laboratory Systems Engineering Department to support the Defense Advanced Research Projects Agency (DARPA) in assessing and demonstrating the viability of deploying small-scale reactors in support of military operations in theatre. This document provides a brief explanation of how to access and use the Sustainable FOB Nuclear Power Evaluation utility to view assessment results as input into developing and integrating the program elements needed to create a successful demonstration.

  13. 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.

  14. 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.

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

    SciTech Connect (OSTI)

    Sackschewsky, Michael R.

    2004-01-15

    The Endangered Species Act (ESA) of 1973 requires that federal agencies ensure that any action authorized, funded, or carried out under their jurisdiction is not likely to jeopardize the continued existence of any threatened or endangered (T&E) species or result in the destruction or adverse modification of critical habitats for such species. The issuance and maintenance of a federal license, such as a construction permit or operating license issued by the U.S. Nuclear Regulatory Commission (NRC) for a commercial nuclear power generating facility is a federal action under the jurisdiction of a federal agency, and is therefore subject to the provisions of the ESA. The Office of Nuclear Reactor Regulation (NRR) staff have performed appropriate assessments of potential impacts to threatened or endangered species, and consulted with appropriate agencies with regard to protection of such species in authorizing the construction, operation, and relicensing of nuclear power generating facilities. However, the assessments and consultations concerning many facilities were performed during the 1970's or early 1980's, and have not been re-evaluated in detail or updated since those initial evaluations. A review of potential Endangered Species Act issues at licensed nuclear power facilities was completed in 1997. In that review 484 different ESA-listed species were identified as potentially occurring near one or more of the 75 facility sites that were examined. An update of the previous T&E species evaluation at this time is desired because, during the intervening 6 years: nearly 200 species have been added to the ESA list, critical habitats have been designated for many of the listed species, and significantly more information is available online, allowing for more efficient high-level evaluations of potential species presence near sites and the potential operation impacts. The updated evaluation included searching the NRC's ADAMS database to find any documents related to T&E species take, consultations, and evaluations of potential effects of operation on T&E species. This search recovered a total of approximately 100 documents from 13 sites. Sites that were in the relicensing or decommissioning processes were excluded from the ADAMS search. In general the ADAMS search did not reveal any serious deficiencies or compliance problems. The most notable finds were reports of takes of green sea turtles at Diablo Canyon. While these events were reported to both the NRC and to NOAA Fisheries, no record of interaction between the two federal agencies was found. Species potentially present at each site were determined via querying the Geographical, Environmental, and Siting Information System (GEn&SIS) database developed for the NRC by Lawrence Livermore National Laboratory. The results of these queries were compared against the 1997 review, and in the cases of sites that were in the relicensing process, with the results of those site specific evaluations. A total of 452 T&E species were identified as potentially occurring near one or more of the operating commercial nuclear power generating plants. Information about each of these species was gathered to support an assessment of the probability of occurrence at each of the reactor sites. Based on the assessments of which species are potentially affected at each site, and the information gathered through the ADAMS search, each site was assigned a priority value for follow-up evaluations. The priority listing did not include any sites that had entered the relicensing process, those where the licensee has indicated that they intend to enter the relicensing process before the end of 2005, or those that have entered the decommissioning process. Of the 39 remaining sites, those that were identified as the highest priority for follow-on evaluations are: Diablo Canyon, San Onofre, Crystal River, Harris, and Vogtle, followed by South Texas, Palo Verde, Salem, and Cooper.

  16. 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.

  17. OECD/NEA study on the economics of the long-term operation of nuclear power plants

    SciTech Connect (OSTI)

    Lokhov, A.; Cameron, R.

    2012-07-01

    The OECD Nuclear Energy Agency (NEA) established the Ad hoc expert group on the Economics of Long-term Operation (LTO) of Nuclear Power Plants. The primary aim of this group is to collect and analyse technical and economic data on the upgrade and lifetime extension experience in OECD countries, and to assess the likely applications for future extensions. This paper describes the key elements of the methodology of economic assessment of LTO and initial findings for selected NEA member countries. (authors)

  18. EIS-0373: Proposed Consolidation of Nuclear Operations Related to the Production of Radioisotope Power Systems

    Broader source: Energy.gov [DOE]

    NOTE: EIS-0373 has been cancelled. This EIS evaluates the environmental impacts of consolidating nuclear activities related to production of radioisotope power systems (RPS) for space and national security missions at a single DOE site: the preferred alternative is the Materials and Fuels Complex at Idaho National Laboratory.

  19. Nuclear Operations | National Nuclear Security Administration

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

    Nuclear Operations The SFO Nuclear Operations office is responsible for direction, day-to-day oversight and contract administration activities regarding safe nuclear operations in ...

  20. Report to the US Nuclear Regulatory Commission on analysis and evaluation of operational data - 1987: Power reactors

    SciTech Connect (OSTI)

    1988-10-01

    This annual report of the US Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data (AEOD) is devoted to the activities performed during 1987. The report is published in two volumes. NUREG-1272, Vol. 2, No. 1, covers Power Reactors and presents an overview of the operating experience of the nuclear power industry, with comments regarding the trends of some key performance measures. The report also includes the principal findings and issues identified in AEOD studies over the past year, and summarizes information from Licensee Event Reports, the NRC's Operations Center, and Diagnostic Evaluations. NUREG-1272, Vol. 2, No. 2, covers Nonreactors and presents a review of the nonreactors events and misadministration reports that were reported in 1987 and a brief synopsis of AEOD studies published in 1987. Each volume contains a list of the AEOD Reports issued for 1980-1987.

  1. Development and operativity of a real-time radiological monitoring network centered on the nuclear power plant of Almaraz (Spain)

    SciTech Connect (OSTI)

    Baeza, A.; Miro, C.; Puerto, J.A. del; Rio, M. del; Ortiz, F.; Paniagua, J.M.

    1993-12-01

    This work presents the hardware and software characteristics of the environmental surveillance radiological network that has been installed around the nuclear power station of Almaraz (Spain). A description is given of the program RADLINE which allows radiological data to be logged in real time, and a study is made of the operativity of the network and the methodology followed in establishing the radiological pre-alert and alert levels.

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

    SciTech Connect (OSTI)

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

    1983-01-01

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

  3. Aging and service wear of air-operated valves used in safety-related systems at nuclear power plants

    SciTech Connect (OSTI)

    Cox, D.F.; McElhaney, K.L.; Staunton, R.H.

    1995-05-01

    Air-operated valves (AOVs) are used in a variety of safety-related applications at nuclear power plants. They are often used where rapid stroke times are required or precise control of the valve obturator is required. They can be designed to operate automatically upon loss of power, which is often desirable when selecting components for response to design basis conditions. The purpose of this report is to examine the reported failures of AOVs and determine whether there are identifiable trends in the failures related to predictable causes. This report examines the specific components that comprise a typical AOV, how those components fail, when they fail, and how such failures are discovered. It also examines whether current testing frequencies and methods are effective in predicting such failures.

  4. HOMOGENEOUS NUCLEAR POWER REACTOR

    DOE Patents [OSTI]

    King, L.D.P.

    1959-09-01

    A homogeneous nuclear power reactor utilizing forced circulation of the liquid fuel is described. The reactor does not require fuel handling outside of the reactor vessel during any normal operation including complete shutdown to room temperature, the reactor being selfregulating under extreme operating conditions and controlled by the thermal expansion of the liquid fuel. The liquid fuel utilized is a uranium, phosphoric acid, and water solution which requires no gus exhaust system or independent gas recombining system, thereby eliminating the handling of radioiytic gas.

  5. Knowledge and abilities catalog for nuclear power plant operators: Pressurized water reactors. Revision 1

    SciTech Connect (OSTI)

    1995-08-01

    This document provides the basis for the development of content-valid licensing examinations for reactor operators and senior reactor operators. The examinations developed using the PWR catalog will cover those topics listed under Title 10, (ode of Federal Regulations Part 55. The PWR catalog contains approximately 5100 knowledge and ability (K/A) statements for reactor operators and senior reactor operators. The catalog is organized into six major sections: Catalog Organization; Generic Knowledge and Abilities; Plant Systems; Emergency and Abnormal Plant Evolutions; Components and Theory.

  6. 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.

  7. 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.

  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 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

  9. Nuclear Power & Engineering

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

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

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

    SciTech Connect (OSTI)

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

    1992-08-01

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

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

    SciTech Connect (OSTI)

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

    1992-01-01

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

  12. Deputy Secretary Poneman Delivers Remarks on Nuclear Power at...

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

    Daniel Poneman spoke at the Tokyo American Center today about nuclear power after Fukushima. ... to power generation and operational safety at civil nuclear plants, to deep ...

  13. QUARTERLY NUCLEAR POWER DEPLOYMENT SUMMARY JULY 2015

    Energy Savers [EERE]

    to grant the Director of Nuclear Reactor Regulation authority to issue a full power operating license to ... Submitted Docketed Issued Safety 3 Environ. 4 Issued Southern ...

  14. Powering the Nuclear Navy | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Powering the Nuclear Navy The Naval Nuclear Propulsion Program provides militarily effective nuclear propulsion plants and ensures their safe, reliable and long-lived operation. NNSA's Naval Reactors Program provides the design, development and operational support required to provide militarily effective nuclear propulsion plants and ensure their safe, reliable and long-lived operation. Learn More USS George H.W. Bush conducts flight operations Concern for the Environment Protection of People

  15. Nuclear Power in Space

    DOE R&D Accomplishments [OSTI]

    1994-01-01

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

  16. Commercial nuclear power 1990

    SciTech Connect (OSTI)

    Not Available

    1990-09-28

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

  17. Blue Ribbon Commission, Yucca Mountain Closure, Court Actions - Future of Decommissioned Reactors, Operating Reactors and Nuclear Power - 13249

    SciTech Connect (OSTI)

    Devgun, Jas S.

    2013-07-01

    Issues related to back-end of the nuclear fuel cycle continue to be difficult for the commercial nuclear power industry and for the decision makers at the national and international level. In the US, the 1982 NWPA required DOE to develop geological repositories for SNF and HLW but in spite of extensive site characterization efforts and over ten billion dollars spent, a repository opening is nowhere in sight. There has been constant litigation against the DOE by the nuclear utilities for breach of the 'standard contract' they signed with the DOE under the NWPA. The SNF inventory continues to rise both in the US and globally and the nuclear industry has turned to dry storage facilities at reactor locations. In US, the Blue Ribbon Commission on America's Nuclear Future issued its report in January 2012 and among other items, it recommends a new, consent-based approach to siting of facilities, prompt efforts to develop one or more geologic disposal facilities, and prompt efforts to develop one or more consolidated storage facilities. In addition, the March 2011 Fukushima Daiichi accident had a severe impact on the future growth of nuclear power. The nuclear industry is focusing on mitigation strategies for beyond design basis events and in the US, the industry is in the process of implementing the recommendations from NRC's Near Term Task Force. (authors)

  18. 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)

  19. Massachusetts Nuclear Profile - Pilgrim Nuclear Power Station

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

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

  20. 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.

  1. Pennsylvania Nuclear Profile - Power Plants

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

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

  2. operations | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure ...

  3. Requirements for Computer Based-Procedures for Nuclear Power Plant Field Operators Results from a Qualitative Study

    SciTech Connect (OSTI)

    Katya Le Blanc; Johanna Oxstrand

    2012-05-01

    Although computer-based procedures (CBPs) have been investigated as a way to enhance operator performance on procedural tasks in the nuclear industry for almost thirty years, they are not currently widely deployed at United States utilities. One of the barriers to the wide scale deployment of CBPs is the lack of operational experience with CBPs that could serve as a sound basis for justifying the use of CBPs for nuclear utilities. Utilities are hesitant to adopt CBPs because of concern over potential costs of implementation, and concern over regulatory approval. Regulators require a sound technical basis for the use of any procedure at the utilities; without operating experience to support the use CBPs, it is difficult to establish such a technical basis. In an effort to begin the process of developing a technical basis for CBPs, researchers at Idaho National Laboratory are partnering with industry to explore CBPs with the objective of defining requirements for CBPs and developing an industry-wide vision and path forward for the use of CBPs. This paper describes the results from a qualitative study aimed at defining requirements for CBPs to be used by field operators and maintenance technicians.

  4. Impact of fuel cladding failure events on occupational radiation exposures at nuclear power plants. Case study: PWR during routine operations

    SciTech Connect (OSTI)

    Moeller, M.P.; Martin, G.F.; Haggard, D.L.

    1986-01-01

    The purpose of this report is to present data in support of evaluating the impact of fuel cladding failure events on occupational radiation exposure. To determine quantitatively whether fuel cladding failure contributes significantly to occupational radiation exposure, radiation exposure measurements were taken at comparable locations in two mirror-image pressurized-water reactors (PWRs) and their common auxiliary building. One reactor, Unit B, was experiencing degraded fuel characterized as 0.125% fuel pin-hole leakers and was operating at approximately 55% of the reactor's licensed maximum core power, while the other reactor, Unit A, was operating under normal conditions with less than 0.01% fuel pin-hole leakers at 100% of the reactor's licensed maximum core power. Measurements consisted of gamma spectral analyses, radiation exposure rates and airborne radionuclide concentrations. In addition, data from primary coolant sample results for the previous 20 months on both reactor coolant systems were analyzed. The results of the measurements and coolant sample analyses suggest that a 3560-megawatt-thermal (1100 MWe) PWR operating at full power with 0.125% failed fuel can experience an increase of 540% in radiation exposure rates as compared to a PWR operating with normal fuel. In specific plant areas, the degraded fuel may elevate radiation exposure rates even more.

  5. Labor and nuclear power

    SciTech Connect (OSTI)

    Logan, R.; Nelkin, D.

    1980-03-01

    The AFL-CIO is officially pro-nuclear, but tensions within unions are taking issue over ideological differences. The Labor movement, having looked to nuclear power development as an economic necessity to avoid unemployment, has opposed efforts to delay construction or close plants. As many as 42% of union members or relatives of members, however, were found to oppose new power plants, some actively working against specific construction projects. The United Mine Workers and Teamsters actively challenged the nuclear industry while the auto workers have been ambivalent. The differences between union orientation reflects the history of unionism in the US and explains the emergence of social unionism with its emphasis on safety and working conditions as well as economic benefits. Business union orientation trends to prevail during periods of prosperity; social unions during recessions. The labor unions and the environmentalists are examined in this conext and found to be hopeful. 35 references. (DCK)

  6. Powering the Nuclear Navy | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Programs Powering the Nuclear Navy The Naval Nuclear Propulsion Program provides militarily effective nuclear propulsion plants and ensures their safe, reliable and long-lived operation. This mission requires the combination of fully trained U.S. Navy men and women with ships that excel in endurance, stealth, speed, and independence from supply chains. The Naval Nuclear Propulsion Program provides militarily effective nuclear propulsion plants and ensures their safe, reliable and long-lived

  7. 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 ...

  8. 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 ...

  9. Topics in nuclear power

    SciTech Connect (OSTI)

    Budnitz, Robert J.

    2015-03-30

    The 101 nuclear plants operating in the US today are far safer than they were 20-30 years ago. For example, there's been about a 100-fold reduction in the occurrence of 'significant events' since the late 1970s. Although the youngest of currently operating US plants was designed in the 1970s, all have been significantly modified over the years. Key contributors to the safety gains are a vigilant culture, much improved equipment reliability, greatly improved training of operators and maintenance workers, worldwide sharing of experience, and the effective use of probabilistic risk assessment. Several manufacturers have submitted high quality new designs for large reactors to the U.S. Nuclear Regulatory Commission (NRC) for design approval, and several companies are vigorously working on designs for smaller, modular reactors. Although the Fukushima reactor accident in March 2011 in Japan has been an almost unmitigated disaster for the local population due to their being displaced from their homes and workplaces and also due to the land contamination, its 'lessons learned' have been important for the broader nuclear industry, and will surely result in safer nuclear plants worldwide - indeed, have already done so, with more safety improvements to come.

  10. 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).

  11. Overview paper on nuclear power

    SciTech Connect (OSTI)

    Spiewak, I.; Cope, D.F.

    1980-09-01

    This paper was prepared as an input to ORNL's Strategic Planning Activity, ORNL National Energy Perspective (ONEP). It is intended to provide historical background on nuclear power, an analysis of the mission of nuclear power, a discussion of the issues, the technology choices, and the suggestion of a strategy for encouraging further growth of nuclear power.

  12. Global warming and nuclear power

    SciTech Connect (OSTI)

    Wood, L., LLNL

    1998-07-10

    Nuclear fission power reactors represent a potential solution to many aspects of global change possibly induced by inputting of either particulate or carbon or sulfur oxides into the Earth`s atmosphere. Of proven technological feasibility, they presently produce high-grade heat for large-scale electricity generation, space heating and industrial process-energizing around the world, without emitting greenhouse gases or atmospheric particulates; importantly, electricity production costs from the best nuclear plants presently are closely comparable with those of the best fossil-fired plants. However, a substantial number of issues currently stand between nuclear power and widespread substitution for large stationary fossil fuel-fired systems. These include perceptual ones regarding both long-term and acute operational safety, plant decommissioning, fuel reprocessing, radwaste disposal, fissile materials diversion to military purposes and - perhaps most seriously- readily quantifiable concerns regarding long-term fuel supply and total unit electrical energy cost. We sketch a road-map for proceeding from the present situation toward a nuclear power-intensive world, addressing along the way each of the concerns which presently impede widespread nuclear substitution for fossil fuels, particularly for coal in the most populous and rapidly developing portions of the world, e.g., China and India. This `design to societal specifications` approach to large-scale nuclear fission power systems may lead to energy sources meeting essentially all stationary demands for high-temperature heat. Such advanced options offer a human population of ten billion the electricity supply levels currently enjoyed by Americans for 10,000 years. Nuclear power systems tailored to local needs-and-interests and having a common advanced technology base could reduce present-day world-wide C0{sub 2} emissions by two-fold, if universally employed. By application to small mobile demands, a second two-fold reduction might be attained. Even the first such halving of carbon intensivity of stationary-source energy production world-wide might permit continued slow power-demand growth in the highly developed countries and rapid development of the other 80% of the world, both without active governmental suppression of fossil fuel usage - while also stabilizing carbon input-rates into the Earth`s atmosphere. The second two-fold reduction might obviate most global warming concerns.

  13. Nuclear Power 2010 Program Dominion Virginia Power Cooperative Project U.S. Department of Energy Cooperative Agreement DE-FC07-05ID14635 Construction and Operating License Demonstration Project Final Report

    SciTech Connect (OSTI)

    Eugene S. Grecheck David P. Batalo

    2010-11-30

    This report serves to summarize the major activities completed as part of Virginia Electric and Power Company's North Anna construction and operating license demonstration project with DOE. Project successes, lessons learned, and suggestions for improvement are discussed. Objectives of the North Anna COL project included preparation and submittal of a COLA to the USNRC incorporating ESBWR technology for a third unit a the North Anna Power Station site, support for the NRC review process and mandatory hearing, obtaining NRC approval of the COLA and issuance of a COL, and development of a business case necessary to support a decision on building a new nuclear power plant at the North Anna site.

  14. Operations | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Operations NNSA's Emergency Response Operations program acts as the headquarters command and control, functioning as the coordinating focal point for all deployed assets during a nuclear or radiological incident. It also acts as support to any national special security events, special events, the Department of Defense; the Department of State during operations outside the continental United States and local, state, or federal law enforcement. The Operations Program coordinates the following

  15. 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

  16. Management of National Nuclear Power Programs for assured safety

    SciTech Connect (OSTI)

    Connolly, T.J.

    1985-01-01

    Topics discussed in this report include: nuclear utility organization; before the Florida Public Service Commission in re: St. Lucie Unit No. 2 cost recovery; nuclear reliability improvement and safety operations; nuclear utility management; training of nuclear facility personnel; US experience in key areas of nuclear safety; the US Nuclear Regulatory Commission - function and process; regulatory considerations of the risk of nuclear power plants; overview of the processes of reliability and risk management; management significance of risk analysis; international and domestic institutional issues for peaceful nuclear uses; the role of the Institute of Nuclear Power Operations (INPO); and nuclear safety activities of the International Atomic Energy Agency (IAEA).

  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. Nuclear reactor characteristics and operational history

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

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

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

    Office of Scientific and Technical Information (OSTI)

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

  20. Competitive economics of nuclear power

    SciTech Connect (OSTI)

    Hellman, R.

    1981-03-02

    Some 12 components of a valid study of the competitive economics of a newly ordered nuclear power plant are identified and explicated. These are then used to adjust the original cost projections of four authoritative studies of nuclear and coal power economics.

  1. Safety of Nuclear Explosive Operations

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2001-08-07

    This directive establishes responsibilities and requirements to ensure the safety of routine and planned nuclear explosive operations and associated activities and facilities. Cancels DOE O 452.2A and DOE G 452.2A-1A. Canceled by DOE O 452.2C.

  2. Public opinion factors regarding nuclear power

    SciTech Connect (OSTI)

    Benson, B.

    1991-12-31

    This paper is an effort to identify, as comprehensively as possible, public concerns about nuclear power, and to assess, where possible, the relative importance of these concerns as they relate to government regulation of and policy towards nuclear power. It is based on some two dozen in-depth interviews with key communicators representing the nuclear power industry, the environmental community, and government, as well as on the parallel efforts in our research project: (1) review of federal court case law, (2) a selective examination of the Nuclear Regulatory Commission (NRC) administrative process, and (3) the preceding George Mason University research project in this series. The paper synthesizes our findings about public attitudes towards nuclear power as expressed through federal court case law, NRC administrative law, public opinion surveys, and direct personal interviews. In so doing, we describe the public opinion environment in which the nuclear regulatory process must operate. Our premise is that public opinion ultimately underlies the approaches government agencies take towards regulating nuclear power, and that, to the degree that the nuclear power industry`s practices are aligned with public opinion, a more favorable regulatory climate is possible.

  3. Public opinion factors regarding nuclear power

    SciTech Connect (OSTI)

    Benson, B.

    1991-01-01

    This paper is an effort to identify, as comprehensively as possible, public concerns about nuclear power, and to assess, where possible, the relative importance of these concerns as they relate to government regulation of and policy towards nuclear power. It is based on some two dozen in-depth interviews with key communicators representing the nuclear power industry, the environmental community, and government, as well as on the parallel efforts in our research project: (1) review of federal court case law, (2) a selective examination of the Nuclear Regulatory Commission (NRC) administrative process, and (3) the preceding George Mason University research project in this series. The paper synthesizes our findings about public attitudes towards nuclear power as expressed through federal court case law, NRC administrative law, public opinion surveys, and direct personal interviews. In so doing, we describe the public opinion environment in which the nuclear regulatory process must operate. Our premise is that public opinion ultimately underlies the approaches government agencies take towards regulating nuclear power, and that, to the degree that the nuclear power industry's practices are aligned with public opinion, a more favorable regulatory climate is possible.

  4. Nuclear energy is an important source of power, supplying 20

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

    energy is an important source of power, supplying 20 percent of the nation's electricity. More than 100 nuclear power plants are operating in the U.S., and countries around the world are implementing nuclear power as a carbon-free alternative to fossil fuels. We can maximize the climate and energy security benefits provided by responsible global nuclear energy expansion by developing options to increase the energy extracted from nuclear fuel, improve waste management, and strengthen nuclear

  5. The American nuclear power industry. A handbook

    SciTech Connect (OSTI)

    Pearman, W.A.; Starr, P.

    1984-01-01

    This book presents an overview of the history and current organization of the American nuclear power industry. Part I focuses on development of the industry, including the number, capacity, and type of plants in commercial operation as well as those under construction. Part II examines the safety, environmental, antitrust, and licensing issues involved in the use of nuclear power. Part III presents case studies of selected plants, such as Three Mile Island and Seabrook, to illustrate some of the issues discussed. The book also contains a listing of the Nuclear Regulatory Commission libraries and a subject index.

  6. 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

  7. 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

  8. Siemens Nuclear Power GmbH AREVA Nuclear Power | Open Energy...

    Open Energy Info (EERE)

    Nuclear Power GmbH AREVA Nuclear Power Jump to: navigation, search Name: Siemens Nuclear Power GmbH (AREVA Nuclear Power) Place: Erlangen, Germany Zip: 91058 Sector: Services...

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

    SciTech Connect (OSTI)

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

    1991-06-01

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

  10. Nuclear Facility Operations | Department of Energy

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

    Nuclear Facility Operations INL is a science-based, applied engineering national laboratory dedicated to meeting the nation's environmental, energy, nuclear technology, and ...

  11. 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.

  12. Nuclear power reactor instrumentation systems handbook. Volume...

    Office of Scientific and Technical Information (OSTI)

    Nuclear power reactor instrumentation systems handbook. Volume 1 Citation Details In-Document Search Title: Nuclear power reactor instrumentation systems handbook. Volume 1 You ...

  13. operations center | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Operations Center The Office of Emergency Operations Support maintains situational awareness of the nation's energy infrastructure and nuclear weapons complex and facilitates...

  14. Wave-operated power plant

    SciTech Connect (OSTI)

    Ghesquiere, H.

    1980-08-12

    This wave-operated power plant comprises a perforated caisson breakwater in which propellers, or turbines, are mounted in the perforations or openings and drives hydraulic pumps connected thereto, which in turn drives a hydraulic motor coupled to an electric generator. One-way flap valves are mounted in the openings. Some of said flap valves allow the rushing waves to enter the caisson, while the other flap valves allow the water to flow out of the caisson.

  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. 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

  17. 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

  18. Virginia Nuclear Profile - Power Plants

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

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

  19. 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

  20. Safer nuclear power

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

    The more recent Fukushima disaster was similar to the TMI event, in that each was a loss-of-coolant accident (LOCA), which is essentially a plumbing problem: plant operators are ...

  1. 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.

  2. 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

  3. Hallam Nuclear Power Facility, NE

    Energy Savers [EERE]

    Hallam Nuclear Power Facility, NE 1969 1998 2. Piqua Nuclear Power Facility, OH 1969 1998 3. Bayo Canyon, NM 1982 1998 4. Kellex/Pierpont, NJ 1982 1998 5. University of California, CA 1982 1998 6. Acid/Pueblo Canyons, NM 1984 1999 7. Chupadera Mesa, NM 1984 1999 8. Canonsburg, PA 1986 1999 9.Shiprock, NM 1987 2000 10. Middlesex Municipal Landfill, NJ 1987 2000 11. Niagara Falls Storage Site Vicinity Properties, NY 1987 2001 12. Salt Lake City, UT 1989 2001 13. Spook, WY 1989 2001 14. National

  4. 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

  5. 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

  6. 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

  7. 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

  8. 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

  9. 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

  10. Kansas Nuclear Profile - Power Plants

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

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

  11. Vermont Nuclear Profile - Power Plants

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

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

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

  13. METHOD OF OPERATING NUCLEAR REACTORS

    DOE Patents [OSTI]

    Untermyer, S.

    1958-10-14

    A method is presented for obtaining enhanced utilization of natural uranium in heavy water moderated nuclear reactors by charging the reactor with an equal number of fuel elements formed of natural uranium and of fuel elements formed of uranium depleted in U/sup 235/ to the extent that the combination will just support a chain reaction. The reactor is operated until the rate of burnup of plutonium equals its rate of production, the fuel elements are processed to recover plutonium, the depleted uranium is discarded, and the remaining uranium is formed into fuel elements. These fuel elements are charged into a reactor along with an equal number of fuel elements formed of uranium depleted in U/sup 235/ to the extent that the combination will just support a chain reaction, and reuse of the uranium is continued as aforesaid until it wlll no longer support a chain reaction when combined with an equal quantity of natural uranium.

  14. Operations | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    focal point for all deployed assets during a nuclear or radiological incident. ... missions: SearchSurge - Detecting nuclear or radiological materials during a ...

  15. 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

  16. 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"

  17. Nuclear power high technology colloquium: proceedings

    SciTech Connect (OSTI)

    Not Available

    1984-12-10

    Reports presenting information on technology advancements in the nuclear industry and nuclear power plant functions have been abstracted and are available on the energy data base.

  18. Quarterly Nuclear Power Deployment Scorecard - January 2013 ...

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

    January 2013 Quarterly Nuclear Power Deployment Scorecard - January 2013 News Updates On ... been docketed, ten of which (totaling 16 nuclear reactors) remain under active NRC review. ...

  19. Emergency Operations Training Academy | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration Emergency Operations Training Academy Emergency Operations Training Academy The Office of Emergency Operations, NA-40-The Emergency Operations Training Academy (EOTA) EOTA provides training and education to enhance the readiness of personnel in the radiological-nuclear emergency operations community. For more information or to contact us, visit the EOTA website at

  20. 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

  1. 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

  2. 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

  3. 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

  4. 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

  5. Washington Nuclear Profile - Power Plants

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

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

  6. Nuclear Safety Research and Development Program Operating Plan...

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

    Program Operating Plan Nuclear Safety Research and Development Program Operating Plan July 5, 2012 Nuclear Safety Research and Development Program Operating Plan This operating ...

  7. Supervisory Physical Scientist (Power Operations)

    Broader source: Energy.gov [DOE]

    This position is located in Duty Scheduling (PGSD), Generation Scheduling (PGS), Power Services (P), Bonneville Power Administration. Duty Scheduling provides 24-hour coverage of the real-time...

  8. QUARTERLY NUCLEAR POWER DEPLOYMENT SUMMARY APRIL 2016

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

    Summer 2016. The NRC has issued combined licenses to Nuclear Innovation North America (NINA), STP Nuclear Operating Company, NINA Texas 3 LLC, NINA Texas 4 LLC, and the ...

  9. QUARTERLY NUCLEAR POWER DEPLOYMENT SUMMARY APRIL 2014

    Office of Environmental Management (EM)

    Power Company and Oglethorpe Power Company for the construction of two new nuclear reactors at the Alvin W. ... Submitted Docketed Issued Safety 3 Environ. 4 Issued Southern ...

  10. Nuclear Power: High Hopes, Unfulfilled Promise (Conference) ...

    Office of Scientific and Technical Information (OSTI)

    Power: High Hopes, Unfulfilled Promise Citation Details In-Document Search Title: Nuclear Power: High Hopes, Unfulfilled Promise You are accessing a document from the Department ...

  11. Electric Power Produced from Nuclear Reactor | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration Electric Power Produced from Nuclear Reactor Electric Power Produced from Nuclear Reactor Arco, ID The Experimental Breeder Reactor No. 1 located at the National Reactor Testing Station near Arco, Idaho, produces the first electric power from a nuclear reactor

  12. 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.

  13. Experiments ✚ Simulations = Better Nuclear Power Research

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

    Experiments + Simulations Better Nuclear Power Research Experiments Simulations ... An international collaboration of physicists is working to improve the safety and ...

  14. Role of nuclear power in the Philippine power development program

    SciTech Connect (OSTI)

    Aleta, C.R.

    1994-12-31

    The reintroduction of nuclear power in the Philippines is favored by several factors such as: the inclusion of nuclear energy in the energy sector of the science and technology agenda for national development (STAND); the Large gap between electricity demand and available local supply for the medium-term power development plan; the relatively lower health risks in nuclear power fuel cycle systems compared to the already acceptable power systems; the lower environmental impacts of nuclear power systems compared to fossil fuelled systems and the availability of a regulatory framework and trained personnel who could form a core for implementing a nuclear power program. The electricity supply gap of 9600 MW for the period 1993-2005 could be partly supplied by nuclear power. The findings of a recent study are described, as well as the issues that have to be addressed in the reintroduction of nuclear power.

  15. Korea Hydro and Nuclear Power Company, Ltd Training

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

    Korea Hydro and Nuclear Power Co., Ltd. (KHNP), a large electric company based in the Republic of Korea, operates 20 nuclear power plants and has 8 more planned or under construction. The Korean government has given KHNP responsibility for permanent disposal of nuclear waste. The company has turned to Sandia' s Defense Waste Management Programs in Carlsbad, NM to lead an educational project for its staff on repository sciences based on Sandia's well- known expertise in the field. Sandia has

  16. A probabilistic evaluation of the safety of Babcock and Wilcox nuclear reactor power plants with emphasis on historically observed operational events

    SciTech Connect (OSTI)

    Hsu, C.J.; Youngblood, R.W.; Fitzpatrick, R.G.; Amico, P.J.

    1989-03-01

    This report summarizes a study performed by Brookhaven National Laboratory for the Office of Nuclear Reactor Regulation, Division of Engineering and System Technology (A/D for Systems), US Nuclear Regulatory Commission. This study was requested by the NRC to assist their staff in assessing the risk significance of features of the Babcock and Wilcox (B and W) reactor plant design in the light of recent operational events. This study focuses on a critical review of submissions from the B and W Owners Group (BWOG) and as an independent assessment of the risk significance of ''Category C'' events at each operating B and W reactor. Category C events are those in which system conditions reach limits which require significant safety system and timely operator response to mitigate. A precursor study for each of the major B and W historical Category C events also was carried out. In addition, selected PRAs for B and W reactor plants and plants with other pressurized water reactor (PWR) designs were reviewed to appraise their handling of Category C events, thereby establishing a comparison between the risk profiles of B and W reactor plants and those of other PWR designs. The effectiveness of BWOG recommendations set forth in Appendix J of the BWOG SPIP (Safety and Performance Improvement Program) report (BAW-1919) also was evaluated. 49 refs., 21 figs., 52 tabs.

  17. Emergency Operations Training Academy | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration Response / Training Emergency Operations Training Academy Rotating image showing pictures of Classroom, Online and Hands on trainings The Office of Emergency Operations, NA-40-The Emergency Operations Training Academy (EOTA) EOTA provides training and education to enhance the readiness of personnel in the radiological-nuclear emergency operations community. For more information or to contact us, visit the EOTA website at: http://eota.energy.gov/ Vision The Emergency Operations

  18. Continuity of Operations at Bonneville Power Administration,...

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

    In the event of a major disruption to its nonnal operations, Bonneville must be prepared to continue its essential functions, particularly its power scheduling, tralsmission ...

  19. Operations Center | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Response Operations Center The Office of Emergency Operations Support maintains situational awareness of the nation's energy infrastructure and nuclear weapons complex and facilitates management of national emergency events via a secure nationwide communications network. The Operations Center provides an integrated, scalable, mobile and/or virtual response capability to enable NNSA to successfully conduct routine and emergency operations through the leverage of mission critical resources in

  20. NNSA Streamlines Operations | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Streamlines Operations NNSA Streamlines Operations Washington, DC he National Nuclear Security Administration (NNSA) implemented a new organizational structure that eliminates a layer of management and seeks to achieve a 20 percent reduction in federal personnel by the end of Fiscal Year 2004. Three operations offices-at Oakland, Las Vegas, and Albuquerque-were eliminated, and site offices that oversee contractor operations now report directly to headquarters

  1. Table 2. Nuclear power plant data

    Gasoline and Diesel Fuel Update (EIA)

    Revised: February 3, 2016 (revision) Next release date: Late 2018 Table 2. Nuclear power ... (year) Actual retirement (year) Arkansas Nuclear 1 AR PWR B&W 177 1974 2034 Arkansas ...

  2. QUARTERLY NUCLEAR POWER DEPLOYMENT SUMMARY JANUARY 2015

    Energy Savers [EERE]

    The Vermont Yankee nuclear energy facility has closed. ... closure. Georgia Power has notified the Securities ... Submitted Docketed Issued Safety 3 Environ. 4 Issued ...

  3. QUARTERLY NUCLEAR POWER DEPLOYMENT SUMMARY JULY 2014

    Energy Savers [EERE]

    The NRC Atomic Safety and Licensing Board (ASLB) has ruled that Toshiba's participation in Nuclear Innovation North ... - Ph. B Completed Florida Power and Light Turkey Point FL ...

  4. Anhui Wuhu Nuclear Power Co | Open Energy Information

    Open Energy Info (EERE)

    Wuhu Nuclear Power Co Jump to: navigation, search Name: Anhui Wuhu Nuclear Power Co. Place: Shenzhen, Guangdong Province, China Zip: 518031 Product: JV between Guangdong Nuclear...

  5. Digital computer operation of a nuclear reactor

    DOE Patents [OSTI]

    Colley, Robert W.

    1984-01-01

    A method is described for the safe operation of a complex system such as a nuclear reactor using a digital computer. The computer is supplied with a data base containing a list of the safe state of the reactor and a list of operating instructions for achieving a safe state when the actual state of the reactor does not correspond to a listed safe state, the computer selects operating instructions to return the reactor to a safe state.

  6. Digital computer operation of a nuclear reactor

    DOE Patents [OSTI]

    Colley, R.W.

    1982-06-29

    A method is described for the safe operation of a complex system such as a nuclear reactor using a digital computer. The computer is supplied with a data base containing a list of the safe state of the reactor and a list of operating instructions for achieving a safe state when the actual state of the reactor does not correspond to a listed safe state, the computer selects operating instructions to return the reactor to a safe state.

  7. Wolf Creek Nuclear Operating Corporation | Open Energy Information

    Open Energy Info (EERE)

    Wolf Creek Nuclear Operating Corporation Jump to: navigation, search Name: Wolf Creek Nuclear Operating Corporation Place: Burlington, Kansas Zip: 66839-0411 Product: Wolf Creek...

  8. Operation of Grand Gulf Nuclear Station, Units 1 and 2, Dockets Nos. 50-416 and 50-417: Mississippi Power and Light Company, Middle South Energy, Inc. , South Mississippi Electric Power Association. Final environmental statement

    SciTech Connect (OSTI)

    Not Available

    1981-09-01

    The information in this Final Environmental Statement is the second assessment of the environmental impacts associated with the construction and operation of the Grand Gulf Nuclear Station, Units 1 and 2, located on the Mississippi River in Claiborne County, Mississippi. The Draft Environmental Statement was issued in May 1981. The first assessment was the Final Environmental Statement related to construction, which was issued in August 1973 prior to issuance of the Grand Gulf Nuclear Station construction permits. In September 1981 Grand Gulf Unit 1 was 92% complete and Unit 2 was 22% complete. Fuel loading for Unit 1 is scheduled for December 1981. The present assessment is the result of the NRC staff review of the activities associated with the proposed operation of the Station, and includes the staff responses to comments on the Draft Environmental Statement.

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

    SciTech Connect (OSTI)

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

    2015-02-23

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

  10. Integrating Nuclear Energy to Oilfield Operations – Two Case Studies

    SciTech Connect (OSTI)

    Eric P. Robertson; Lee O. Nelson; Michael G. McKellar; Anastasia M. Gandrik; Mike W. Patterson

    2011-11-01

    Fossil fuel resources that require large energy inputs for extraction, such as the Canadian oil sands and the Green River oil shale resource in the western USA, could benefit from the use of nuclear power instead of power generated by natural gas combustion. This paper discusses the technical and economic aspects of integrating nuclear energy with oil sands operations and the development of oil shale resources. A high temperature gas reactor (HTGR) that produces heat in the form of high pressure steam (no electricity production) was selected as the nuclear power source for both fossil fuel resources. Both cases were based on 50,000 bbl/day output. The oil sands case was a steam-assisted, gravity-drainage (SAGD) operation located in the Canadian oil sands belt. The oil shale development was an in-situ oil shale retorting operation located in western Colorado, USA. The technical feasibility of the integrating nuclear power was assessed. The economic feasibility of each case was evaluated using a discounted cash flow, rate of return analysis. Integrating an HTGR to both the SAGD oil sands operation and the oil shale development was found to be technically feasible for both cases. In the oil sands case, integrating an HTGR eliminated natural gas combustion and associated CO2 emissions, although there were still some emissions associated with imported electrical power. In the in situ oil shale case, integrating an HTGR reduced CO2 emissions by 88% and increased natural gas production by 100%. Economic viabilities of both nuclear integrated cases were poorer than the non-nuclear-integrated cases when CO2 emissions were not taxed. However, taxing the CO2 emissions had a significant effect on the economics of the non-nuclear base cases, bringing them in line with the economics of the nuclear-integrated cases. As we move toward limiting CO2 emissions, integrating non-CO2-emitting energy sources to the development of energy-intense fossil fuel resources is becoming increasingly important. This paper attempts to reduce the barriers that have traditionally separated fossil fuel development and application of nuclear power and to promote serious discussion of ideas about hybrid energy systems.

  11. 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.

  12. EISPC White Paper on “State Approaches to Retention of Nuclear Power Plants” Now Available

    Broader source: Energy.gov [DOE]

    The Eastern Interconnection States’ Planning Collaborative (EISPC) has released a white paper on “State Approaches to Retention of Nuclear Power Plants” that examines operational, economic, and...

  13. Naturalistic Decision Making For Power System Operators

    SciTech Connect (OSTI)

    Greitzer, Frank L.; Podmore, Robin; Robinson, Marck; Ey, Pamela

    2009-06-23

    Abstract: Motivation -- As indicated by the Blackout of 2003, the North American interconnected electric system is vulnerable to cascading outages and widespread blackouts. Investigations of large scale outages often attribute the causes to the three Ts: Trees, Training and Tools. A systematic approach has been developed to document and understand the mental processes that an expert power system operator uses when making critical decisions. The approach has been developed and refined as part of a capability demonstration of a high-fidelity real-time power system simulator under normal and emergency conditions. To examine naturalistic decision making (NDM) processes, transcripts of operator-to-operator conversations are analyzed to reveal and assess NDM-based performance criteria. Findings/Design -- The results of the study indicate that we can map the Situation Awareness Level of the operators at each point in the scenario. We can also identify clearly what mental models and mental simulations are being performed at different points in the scenario. As a result of this research we expect that we can identify improved training methods and improved analytical and visualization tools for power system operators. Originality/Value -- The research applies for the first time, the concepts of Recognition Primed Decision Making, Situation Awareness Levels and Cognitive Task Analysis to training of electric power system operators. Take away message -- The NDM approach provides an ideal framework for systematic training management and mitigation to accelerate learning in team-based training scenarios with high-fidelity power grid simulators.

  14. and Operations | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Operations NNSA's Asset Management Program Completes First Pilot The National Nuclear Security Administration (NNSA) today announced completion of a $520k pilot to replace a roof, as well as heating, ventilation and cooling (HVAC) system for the Core Library and Data Center at Mercury, Nevada (http://nevada.usgs.gov/mercury/). The library was established

  15. 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.

  16. Workshop on nuclear power growth and nonproliferation

    SciTech Connect (OSTI)

    Pilat, Joseph F

    2010-01-01

    It is widely viewed that an expansion of nuclear power would have positive energy, economic and environmental benefits for the world. However, there are concerns about the economic competitiveness, safety and proliferation and terrorism risks of nuclear power. The prospects for a dramatic growth in nuclear power will depend on the ability of governments and industry to address these concerns, including the effectiveness of, and the resources devoted to, plans to develop and implement technologies and approaches that strengthen nonproliferation, nuclear materials accountability and nuclear security. In his Prague speech, President Obama stated: 'we should build a new framework for civil nuclear cooperation, including an international fuel bank, so that countries can access peaceful power without increasing the risks of proliferation. That must be the right of every nation that renounces nuclear weapons, especially developing countries embarking on peaceful programs. And no approach will succeed if it's based on the denial of rights to nations that play by the rules. We must harness the power of nuclear energy on behalf of our efforts to combat climate change, and to advance peace opportunity for all people.' How can the President's vision, which will rekindle a vigorous public debate over the future of nuclear power and its relation to proliferation, be realized? What critical issues will frame the reemerging debate? What policies must be put into place to address these issues? Will US policy be marked more by continuity or change? To address these and other questions, the Los Alamos National Laboratory in cooperation with the Woodrow Wilson International Center for Scholars will host a workshop on the future of nuclear power and nonproliferation.

  17. Hazard Analysis Reports for Nuclear Explosive Operations

    Energy Savers [EERE]

    NA-STD-3016-2006 May 2006 DOE LIMITED STANDARD HAZARD ANALYSIS REPORTS FOR NUCLEAR EXPLOSIVE OPERATIONS U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE ii Available on the Department of Energy Technical Standards Program web site at http://www.eh.doe.gov/techstds/ DOE-NA-STD-3016-2006 iii FORWARD This Department of Energy (DOE)/National Nuclear Security Administration (NNSA)

  18. Electronic Position Sensor for Power Operated Accessory

    DOE Patents [OSTI]

    Haag, Ronald H.; Chia, Michael I.

    2005-05-31

    An electronic position sensor for use with a power operated vehicle accessory, such as a power liftgate. The position sensor includes an elongated resistive circuit that is mounted such that it is stationary and extends along the path of a track portion of the power operated accessory. The position sensor further includes a contact nub mounted to a link member that moves within the track portion such that the contact nub is slidingly biased against the elongated circuit. As the link member moves under the force of a motor-driven output gear, the contact nub slides along the surface of the resistive circuit, thereby affecting the overall resistance of the circuit. The position sensor uses the overall resistance to provide an electronic position signal to an ECU, wherein the signal is indicative of the absolute position of the power operated accessory. Accordingly, the electronic position sensor is capable of providing an electronic signal that enables the ECU to track the absolute position of the power operated accessory.

  19. Integrated approach to economical, reliable, safe nuclear power production

    SciTech Connect (OSTI)

    Not Available

    1982-06-01

    An Integrated Approach to Economical, Reliable, Safe Nuclear Power Production is the latest evolution of a concept which originated with the Defense-in-Depth philosophy of the nuclear industry. As Defense-in-Depth provided a framework for viewing physical barriers and equipment redundancy, the Integrated Approach gives a framework for viewing nuclear power production in terms of functions and institutions. In the Integrated Approach, four plant Goals are defined (Normal Operation, Core and Plant Protection, Containment Integrity and Emergency Preparedness) with the attendant Functional and Institutional Classifications that support them. The Integrated Approach provides a systematic perspective that combines the economic objective of reliable power production with the safety objective of consistent, controlled plant operation.

  20. QUARTERLY NUCLEAR POWER DEPLOYMENT SUMMARY JANUARY 2014

    Energy Savers [EERE]

    ... 1 Reference COL Application (R-COL) 4 Safety Review: R-COL Ph 1 Issue RAIs Ph 2 ... comment Ph 4 Final EIS QUARTERLY NUCLEAR POWER DEPLOYMENT SUMMARY JANUARY 2014 Updates ...

  1. QUARTERLY NUCLEAR POWER DEPLOYMENT SUMMARY OCTOBER 2014

    Energy Savers [EERE]

    Submitted Docketed Issued Safety 3 Environ. 4 Issued Southern Nuclear Vogtle GA AP1000 2 033108 05... B Completed Florida Power and Light Turkey Point FL AP1000 2 63009 9...

  2. QUARTERLY NUCLEAR POWER DEPLOYMENT SUMMARY APRIL 2015

    Office of Environmental Management (EM)

    ... 2 Reference COL Application (R-COL) 3 Safety Review: R-COL Ph 1 Issue RAIs Ph 2 ... comment Ph 4 Final EIS QUARTERLY NUCLEAR POWER DEPLOYMENT SUMMARY APRIL 2015 Updates ...

  3. Smart Grid - Transforming Power System Operations

    SciTech Connect (OSTI)

    Widergren, Steven E.; Kirkham, Harold

    2010-04-28

    AbstractElectric power systems are entering a new realm of operations. Large amounts of variable generation tax our ability to reliably operate the system. Couple this with a greater reliance on the electricity network to serve consumer demand that is likely to rise significantly even as we drive for greater efficiency. Trade-offs between energy and environmental needs will be constantly negotiated, while a reliable supply of electricity needs even greater assurance in a world where threats of disruption have risen. Smart grid capabilities are being proposed to help address the challenges confronting system operations. This paper reviews the impact of smart grid functionality on transforming power system operations. It explores models for distributed energy resources (DER generation, storage, and load) that are appearing on the system. It reviews the evolving nature of electricity markets to deal with this complexity and a change of emphasis on signals from these markets to affect power system control. Smart grid capabilities will also impact reliable operations, while cyber security issues must be addressed as a culture change that influences all system design, implementation, and maintenance. Lastly, the paper explores significant questions for further research and the need for a simulation environment that supports such investigation and informs deployments to mitigate operational issues as they arise.

  4. Experiments ✚ Simulations = Better Nuclear Power Research

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

    Experiments + Simulations = Better Nuclear Power Research Experiments ✚ Simulations = Better Nuclear Power Research Atomic Level Simulations Enhance Characterization of Radiation Damage July 31, 2015 Contact: Kathy Kincade, +1 510 495 2124, kkincade@lbl.gov Radiation Damage PNNL In a study featured on the cover of a Journal of Materials Research focus issue, an international research collaboration used molecular dynamics simulations run at NERSC to identify atomic-level details of early-stage

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

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

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

  6. Economic Conditions and Factors Affecting New Nuclear Power Deployment...

    Office of Scientific and Technical Information (OSTI)

    Economic Conditions and Factors Affecting New Nuclear Power Deployment Citation Details In-Document Search Title: Economic Conditions and Factors Affecting New Nuclear Power ...

  7. DOE - Office of Legacy Management -- Piqua Nuclear Power Facility...

    Office of Legacy Management (LM)

    Piqua Nuclear Power Facility - OH 08 FUSRAP Considered Sites Site: Piqua Nuclear Power Facility (OH.08 ) Designated Name: Alternate Name: Location: Evaluation Year: Site ...

  8. Renewing America's Nuclear Power Partnership for Energy Security...

    Office of Environmental Management (EM)

    Renewing America's Nuclear Power Partnership for Energy Security and Economic Growth Renewing America's Nuclear Power Partnership for Energy Security and Economic Growth October 8,...

  9. China Guangdong Nuclear Power Holding Co Ltd CGNPC | Open Energy...

    Open Energy Info (EERE)

    Nuclear Power Holding Co Ltd CGNPC Jump to: navigation, search Name: China Guangdong Nuclear Power Holding Co Ltd (CGNPC) Place: Shenzhen, Guangdong Province, China Zip: 518031...

  10. Pyroelectric Energy Scavenging Techniques for Self-Powered Nuclear...

    Office of Scientific and Technical Information (OSTI)

    Self-Powered Nuclear Reactor Wireless Sensor Networks Citation Details In-Document Search Title: Pyroelectric Energy Scavenging Techniques for Self-Powered Nuclear Reactor ...

  11. Multiple-Reheat Brayton Cycles for Nuclear Power Conversion with...

    Office of Scientific and Technical Information (OSTI)

    Brayton Cycles for Nuclear Power Conversion with Molten Coolants Citation Details In-Document Search Title: Multiple-Reheat Brayton Cycles for Nuclear Power Conversion with ...

  12. Renewing America's Nuclear Power Partnership for Energy Security...

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

    Renewing America's Nuclear Power Partnership for Energy Security and Economic Growth Renewing America's Nuclear Power Partnership for Energy Security and Economic Growth October 8, ...

  13. 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.

  14. Water Use in the Development and Operation of Geothermal Power...

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

    Operation of Geothermal Power Plants Water Use in the Development and Operation of Geothermal Power Plants This report summarizes what is currently known about the life cycle water ...

  15. Sichuan Provincial Hydro Power Investment Operation Group Co...

    Open Energy Info (EERE)

    Hydro Power Investment Operation Group Co ltd Jump to: navigation, search Name: Sichuan Provincial Hydro Power Investment & Operation (Group) Co. ltd Place: Chengdu City, Sichuan...

  16. Solving the power flow equations: a monotone operator approach...

    Office of Scientific and Technical Information (OSTI)

    The AC power flow equations underlie all operational aspects of power systems. They are solved routinely in operational practice using the Newton-Raphson method and its variants. ...

  17. Solving the power flow equations: a monotone operator approach...

    Office of Scientific and Technical Information (OSTI)

    Technical Report: Solving the power flow equations: a monotone operator approach Citation Details In-Document Search Title: Solving the power flow equations: a monotone operator ...

  18. Water Use in the Development and Operations of Geothermal Power...

    Energy Savers [EERE]

    Water Use in the Development and Operations of Geothermal Power Plants Water Use in the Development and Operations of Geothermal Power Plants This report summarizes what is ...

  19. Water Use in the Development and Operations of Geothermal Power...

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

    Water Use in the Development and Operations of Geothermal Power Plants Water Use in the Development and Operations of Geothermal Power Plants This report summarizes what is...

  20. New Jersey Nuclear Profile - Power Plants

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

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

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

    SciTech Connect (OSTI)

    McConnell, M. W.

    2012-07-01

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

  2. Climate Change, Nuclear Power and Nuclear Proliferation: Magnitude Matters

    SciTech Connect (OSTI)

    Robert J. Goldston

    2010-03-03

    Integrated energy, environment and economics modeling suggests electrical energy use will increase from 2.4 TWe today to 12 TWe in 2100. It will be challenging to provide 40% of this electrical power from combustion with carbon sequestration, as it will be challenging to provide 30% from renewable energy sources. Thus nuclear power may be needed to provide ~30% by 2100. Calculations of the associated stocks and flows of uranium, plutonium and minor actinides indicate that the proliferation risks at mid-century, using current light-water reactor technology, are daunting. There are institutional arrangements that may be able to provide an acceptable level of risk mitigation, but they will be difficult to implement. If a transition is begun to fast-spectrum reactors at mid-century, without a dramatic change in the proliferation risks of such systems, at the end of the century proliferation risks are much greater, and more resistant to mitigation. The risks of nuclear power should be compared with the risks of the estimated 0.64oC long-term global surface-average temperature rise predicted if nuclear power were replaced with coal-fired power plants without carbon sequestration. Fusion energy, if developed, would provide a source of nuclear power with much lower proliferation risks than fission.

  3. The Fukushima Nuclear Event and its Implications for Nuclear Power

    SciTech Connect (OSTI)

    Golay, Michael

    2011-07-06

    The combined strong earthquake and super tsunami of 12 March 2011 at the Fukushima nuclear power plant imposed the most severe challenges ever experienced at such a facility. Information regarding the plant response and status remains uncertain, but it is clear that severe damage has been sustained, that the plant staff have responded creatively and that the offsite implications are unlikely to be seriously threatening to the health, if not the prosperity, of the surrounding population. Re-examination of the regulatory constraints of nuclear power will occur worldwide, and some changes are likely, particularly concerning reliance upon active systems for achieving critical safety functions and concerning treatments of used reactor fuel. Whether worldwide expansion of the nuclear power economy will be slowed in the long run is perhaps unlikely and worth discussion.

  4. Identifying and bounding uncertainties in nuclear reactor thermal power calculations

    SciTech Connect (OSTI)

    Phillips, J.; Hauser, E.; Estrada, H.

    2012-07-01

    Determination of the thermal power generated in the reactor core of a nuclear power plant is a critical element in the safe and economic operation of the plant. Direct measurement of the reactor core thermal power is made using neutron flux instrumentation; however, this instrumentation requires frequent calibration due to changes in the measured flux caused by fuel burn-up, flux pattern changes, and instrumentation drift. To calibrate the nuclear instruments, steam plant calorimetry, a process of performing a heat balance around the nuclear steam supply system, is used. There are four basic elements involved in the calculation of thermal power based on steam plant calorimetry: The mass flow of the feedwater from the power conversion system, the specific enthalpy of that feedwater, the specific enthalpy of the steam delivered to the power conversion system, and other cycle gains and losses. Of these elements, the accuracy of the feedwater mass flow and the feedwater enthalpy, as determined from its temperature and pressure, are typically the largest contributors to the calorimetric calculation uncertainty. Historically, plants have been required to include a margin of 2% in the calculation of the reactor thermal power for the licensed maximum plant output to account for instrumentation uncertainty. The margin is intended to ensure a cushion between operating power and the power for which safety analyses are performed. Use of approved chordal ultrasonic transit-time technology to make the feedwater flow and temperature measurements (in place of traditional differential-pressure- based instruments and resistance temperature detectors [RTDs]) allows for nuclear plant thermal power calculations accurate to 0.3%-0.4% of plant rated power. This improvement in measurement accuracy has allowed many plant operators in the U.S. and around the world to increase plant power output through Measurement Uncertainty Recapture (MUR) up-rates of up to 1.7% of rated power, while also decreasing the probability of significant over-power events. This paper will examine the basic elements involved in calculation of thermal power using ultrasonic transit-time technology and will discuss the criteria for bounding uncertainties associated with each element in order to achieve reactor thermal power calculations to within 0.3% to 0.4%. (authors)

  5. Inertial Fusion Power Plant Concept of Operations and Maintenance

    SciTech Connect (OSTI)

    Anklam, T.; Knutson, B.; Dunne, A. M.; Kasper, J.; Sheehan, T.; Lang, D.; Roberts, V.; Mau, D.

    2015-01-15

    Parsons and LLNL scientists and engineers performed design and engineering work for power plant pre-conceptual designs based on the anticipated laser fusion demonstrations at the National Ignition Facility (NIF). Work included identifying concepts of operations and maintenance (O&M) and associated requirements relevant to fusion power plant systems analysis. A laser fusion power plant would incorporate a large process and power conversion facility with a laser system and fusion engine serving as the heat source, based in part on some of the systems and technologies advanced at NIF. Process operations would be similar in scope to those used in chemical, oil refinery, and nuclear waste processing facilities, while power conversion operations would be similar to those used in commercial thermal power plants. While some aspects of the tritium fuel cycle can be based on existing technologies, many aspects of a laser fusion power plant presents several important and unique O&M requirements that demand new solutions. For example, onsite recovery of tritium; unique remote material handling systems for use in areas with high radiation, radioactive materials, or high temperatures; a five-year fusion engine target chamber replacement cycle with other annual and multi-year cycles anticipated for major maintenance of other systems, structures, and components (SSC); and unique SSC for fusion target waste recycling streams. This paper describes fusion power plant O&M concepts and requirements, how O&M requirements could be met in design, and how basic organizational and planning issues can be addressed for a safe, reliable, economic, and feasible fusion power plant.

  6. Modeling Power System Operation with Intermittent Resources

    SciTech Connect (OSTI)

    Marinovici, Maria C.; Kirkham, Harold; Glass, Kevin A.; Carlsen, Leif C.

    2013-02-27

    Electricity generating companies and power system operators face the need to minimize total fuel cost or maximize total profit over a given time period. These issues become optimization problems subject to a large number of constraints that must be satisfied simultaneously. The grid updates due to smart-grid technologies plus the penetration of intermittent re- sources in electrical grid introduce additional complexity to the optimization problem. The Renewable Integration Model (RIM) is a computer model of interconnected power system. It is intended to provide insight and advice on complex power systems management, as well as answers to integration of renewable energy questions. This paper describes RIM basic design concept, solution method, and the initial suite of modules that it supports.

  7. Distribution of Wind Power Forecasting Errors from Operational Systems (Presentation)

    SciTech Connect (OSTI)

    Hodge, B. M.; Ela, E.; Milligan, M.

    2011-10-01

    This presentation offers new data and statistical analysis of wind power forecasting errors in operational systems.

  8. 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

  9. An Approach to Autonomous Control for Space Nuclear Power Systems

    SciTech Connect (OSTI)

    Wood, Richard Thomas; Upadhyaya, Belle R.

    2011-01-01

    Under Project Prometheus, the National Aeronautics and Space Administration (NASA) investigated deep space missions that would utilize space nuclear power systems (SNPSs) to provide energy for propulsion and spacecraft power. The initial study involved the Jupiter Icy Moons Orbiter (JIMO), which was proposed to conduct in-depth studies of three Jovian moons. Current radioisotope thermoelectric generator (RTG) and solar power systems cannot meet expected mission power demands, which include propulsion, scientific instrument packages, and communications. Historically, RTGs have provided long-lived, highly reliable, low-power-level systems. Solar power systems can provide much greater levels of power, but power density levels decrease dramatically at {approx} 1.5 astronomical units (AU) and beyond. Alternatively, an SNPS can supply high-sustained power for space applications that is both reliable and mass efficient. Terrestrial nuclear reactors employ varying degrees of human control and decision-making for operations and benefit from periodic human interaction for maintenance. In contrast, the control system of an SNPS must be able to provide continuous operatio for the mission duration with limited immediate human interaction and no opportunity for hardware maintenance or sensor calibration. In effect, the SNPS control system must be able to independently operate the power plant while maintaining power production even when subject to off-normal events and component failure. This capability is critical because it will not be possible to rely upon continuous, immediate human interaction for control due to communications delays and periods of planetary occlusion. In addition, uncertainties, rare events, and component degradation combine with the aforementioned inaccessibility and unattended operation to pose unique challenges that an SNPS control system must accommodate. Autonomous control is needed to address these challenges and optimize the reactor control design.

  10. Effect of Fuel Type on the Attainable Power of the Encapsulated Nuclear

    Office of Scientific and Technical Information (OSTI)

    Heat Source Reactor (Conference) | SciTech Connect Conference: Effect of Fuel Type on the Attainable Power of the Encapsulated Nuclear Heat Source Reactor Citation Details In-Document Search Title: Effect of Fuel Type on the Attainable Power of the Encapsulated Nuclear Heat Source Reactor The Encapsulated Nuclear Heat Source (ENHS) is a small liquid metal cooled fast reactor that features uniform composition core, at least 20 effective full power years of operation without refueling, nearly

  11. Rocketdyne Propulsion & Power DOE Operations Annual Site Environmental Report 1996

    SciTech Connect (OSTI)

    Tuttle, R. J.

    1997-11-10

    This annual report discusses environmental monitoring at two manufacturing and test operations sites operated in the Los Angeles area by Rocketdyne Propulsion & Power of Boeing North American. Inc. (formerly Rockwell International Corporation). These are identified as the Santa Susana Field Laboratory (SSFL and the De Soto site. The sites have been used for manufacturing; R&D, engineering, and testing in a broad range of technical fields, primarily rocket engine propulsion and nuclear reactor technology. The De Soto site essentially comprises office space and light industry with no remaining radiological operations, and has little potential impact on the environment. The SSFL site, because of its large size (2.668 acres), warrants comprehensive monitoring to ensure protection of the environment.

  12. Underground collocation of nuclear power plant reactors and repository to facilitate the post-renaissance expansion of nuclear power

    SciTech Connect (OSTI)

    Myers, Carl W; Elkins, Ned Z

    2008-01-01

    Underground collocation of nuclear power reactors and the nuclear waste management facilities supporting those reactors, termed an underground nuclear park (UNP), appears to have several advantages compared to the conventional approach to siting reactors and waste management facilities. These advantages include the potential to lower reactor capital and operating cost, lower nuclear waste management cost, and increase margins of physical security and safety. Envirorunental impacts related to worker health, facility accidents, waste transportation, and sabotage and terrorism appear to be lower for UNPs compared to the current approach. In-place decommissioning ofUNP reactors appears to have cost, safety, envirorunental and waste disposal advantages. The UNP approach has the potential to lead to greater public acceptance for the deployment of new power reactors. Use of the UNP during the post-nuclear renaissance time frame has the potential to enable a greater expansion of U.S. nuclear power generation than might otherwise result. Technical and economic aspects of the UNP concept need more study to determine the viability of the concept.

  13. QUARTERLY NUCLEAR POWER DEPLOYMENT SUMMARY OCTOBER 2013 News...

    Office of Environmental Management (EM)

    close its single unit Vermont Yankee nuclear power plant in late 2014; sustained low ... IN PROGRESS Submitted Docketed Issued Safety 4 Environ. 5 Issued Southern Nuclear ...

  14. Quarterly Nuclear Power Deployment Scorecard - April 2013 | Department...

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

    April 2013 Quarterly Nuclear Power Deployment Scorecard - April 2013 News Updates On ... been docketed, ten of which (totaling 16 nuclear reactors) remain under active NRC review. ...

  15. Water Use in the Development and Operations of Geothermal Power...

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

    Power Plants Water Use in the Development and Operations of Geothermal Power Plants This report summarizes what is currently known about the life cycle water requirements of ...

  16. 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)

  17. 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.

  18. 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.

  19. Coal and nuclear power: Illinois' energy future

    SciTech Connect (OSTI)

    Not Available

    1982-01-01

    This conference was sponsored by the Energy Resources Center, University of Illinois at Chicago; the US Department of Energy; the Illinois Energy Resources Commission; and the Illinois Department of Energy and Natural Resources. The theme for the conference, Coal and Nuclear Power: Illinois' Energy Future, was based on two major observations: (1) Illinois has the largest reserves of bituminous coal of any state and is surpassed in total reserves only by North Dakota, and Montana; and (2) Illinois has made a heavy commitment to the use of nuclear power as a source of electrical power generation. Currently, nuclear power represents 30% of the electrical energy produced in the State. The primary objective of the 1982 conference was to review these two energy sources in view of the current energy policy of the Reagan Administration, and to examine the impact these policies have on the Midwest energy scene. The conference dealt with issues unique to Illinois as well as those facing the entire nation. A separate abstract was prepared for each of the 30 individual presentations.

  20. 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

  1. 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"

  2. New Hampshire Nuclear Profile - Power Plants

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

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

  3. Transactions of the fifth symposium on space nuclear power systems

    SciTech Connect (OSTI)

    El-Genk, M.S.; Hoover, M.D.

    1988-01-01

    This paper contains the presented papers at the fourth symposium on space nuclear power systems. Topics of these paper include: space nuclear missions and applications, reactors and shielding, nuclear electric and nuclear propulsion, high-temperature materials, instrumentation and control, energy conversion and storage, space nuclear fuels, thermal management, nuclear safety, simulation and modeling, and multimegawatt system concepts. (LSP)

  4. Transactions of the fourth symposium on space nuclear power systems

    SciTech Connect (OSTI)

    El-Genk, M.S.; Hoover, M.D.

    1987-01-01

    This paper contains the presented papers at the fourth symposium on space nuclear power systems. Topics of these papers include: space nuclear missions and applications, reactors and shielding, nuclear electric and nuclear propulsion, refractory alloys and high-temperature materials, instrumentation and control, energy conversion and storage, space nuclear fuels, thermal management, nuclear safety, simulation and modeling, and multimegawatt system concepts. (LSP)

  5. Carbon pricing, nuclear power and electricity markets

    SciTech Connect (OSTI)

    Cameron, R.; Keppler, J. H.

    2012-07-01

    In 2010, the NEA in conjunction with the International Energy Agency produced an analysis of the Projected Costs of Electricity for almost 200 power plants, covering nuclear, fossil fuel and renewable electricity generation. That analysis used lifetime costs to consider the merits of each technology. However, the lifetime cost analysis is less applicable in liberalised markets and does not look specifically at the viewpoint of the private investor. A follow-up NEA assessment of the competitiveness of nuclear energy against coal- and gas-fired generation under carbon pricing has considered just this question. The economic competition in electricity markets is today between nuclear energy and gas-fired power generation, with coal-fired power generation not being competitive as soon as even modest carbon pricing is introduced. Whether nuclear energy or natural gas comes out ahead in their competition depends on a number of assumptions, which, while all entirely reasonable, yield very different outcomes. The analysis in this study has been developed on the basis of daily data from European power markets over the last five-year period. Three different methodologies, a Profit Analysis looking at historic returns over the past five years, an Investment Analysis projecting the conditions of the past five years over the lifetime of plants and a Carbon Tax Analysis (differentiating the Investment Analysis for different carbon prices) look at the issue of competitiveness from different angles. They show that the competitiveness of nuclear energy depends on a number of variables which in different configurations determine whether electricity produced from nuclear power or from CCGTs generates higher profits for its investors. These are overnight costs, financing costs, gas prices, carbon prices, profit margins (or mark-ups), the amount of coal with carbon capture and electricity prices. This paper will present the outcomes of the analysis in the context of a liberalised electricity market, looking at the impact of the seven key variables and provide conclusions on the portfolio that a utility would be advised to maintain, given the need to limit risks but also to move to low carbon power generation. Such portfolio diversification would not only limit financial investor risk, but also a number of non-financial risks (climate change, security of supply, accidents). (authors)

  6. 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.

  7. Climate Change, Nuclear Power and Nuclear Proliferation: Magnitude Matters

    SciTech Connect (OSTI)

    Robert J. Goldston

    2011-04-28

    Integrated energy, environment and economics modeling suggests that worldwide electrical energy use will increase from 2.4 TWe today to ~12 TWe in 2100. It will be challenging to provide 40% of this electrical power from combustion with carbon sequestration, as it will be challenging to provide 30% from renewable energy sources derived from natural energy flows. Thus nuclear power may be needed to provide ~30%, 3600 GWe, by 2100. Calculations of the associated stocks and flows of uranium, plutonium and minor actinides indicate that the proliferation risks at mid-century, using current light-water reactor technology, are daunting. There are institutional arrangements that may be able to provide an acceptable level of risk mitigation, but they will be difficult to implement. If a transition is begun to fast-spectrum reactors at mid-century, without a dramatic change in the proliferation risks of such systems, at the end of the century global nuclear proliferation risks are much greater, and more resistant to mitigation. Fusion energy, if successfully demonstrated to be economically competitive, would provide a source of nuclear power with much lower proliferation risks than fission.

  8. L & O Power Co-operative | Open Energy Information

    Open Energy Info (EERE)

    O Power Co-operative Jump to: navigation, search Name: L & O Power Co-operative Place: Iowa Phone Number: 712-472-2556 Website: www.landopowercoop.com Outage Hotline:...

  9. Nuclear reactor characteristics and operational history

    Gasoline and Diesel Fuel Update (EIA)

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

  10. China Guangdong Nuclear Power Company | Open Energy Information

    Open Energy Info (EERE)

    Power Company Jump to: navigation, search Name: China Guangdong Nuclear Power Company Place: Guangzhou, China Coordinates: 23.129075, 113.264423 Show Map Loading map......

  11. Bettis and Knolls Atomic Power Laboratories | National Nuclear...

    National Nuclear Security Administration (NNSA)

    and Knolls Atomic Power Laboratories | National Nuclear Security Administration Facebook ... Department Bettis and Knolls Atomic Power Laboratories Bettis and Knolls Atomic ...

  12. Nuclear Power Corp L T JV | Open Energy Information

    Open Energy Info (EERE)

    Corp L T JV Jump to: navigation, search Name: Nuclear Power Corp-L&T JV Place: Mumbai, Maharashtra, India Zip: 400094 Product: JV between Nuclear Power Corp. and L&T. Coordinates:...

  13. Secretary Chu Visits Vogtle Nuclear Power Plant | Department...

    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 ...

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

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

    at Vogtle Nuclear Power Plant -- As Prepared for Delivery Secretary Chu's Remarks at Vogtle Nuclear Power Plant -- As Prepared for Delivery February 15, 2012 - 12:27pm Addthis It's ...

  15. Howard Baker Center for Public Policy Nuclear Power Conference...

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

    Howard Baker Center for Public Policy Nuclear Power Conference Howard Baker Center for Public Policy Nuclear Power Conference October 4, 2007 - 3:14pm Addthis Remarks as Prepared...

  16. Linking Humans and Systems in Nuclear Power

    SciTech Connect (OSTI)

    Jacques Hugo

    2013-02-01

    Traditional engineering methods do not make provision for the integration of human considerations, while traditional human factors methods do not scale well to the complexity of large-scale nuclear power plant projects. Although the need for up-to-date human factors engineering processes and tools is recognised widely in industry, so far no formal guidance has been developed. This article proposes such a framework.

  17. 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

  18. 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

  19. 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.

  20. 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.

  1. 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.

  2. 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.

  3. 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.

  4. Nuclear power generation and fuel cycle report 1997

    SciTech Connect (OSTI)

    1997-09-01

    Nuclear power is an important source of electric energy and the amount of nuclear-generated electricity continued to grow as the performance of nuclear power plants improved. In 1996, nuclear power plants supplied 23 percent of the electricity production for countries with nuclear units, and 17 percent of the total electricity generated worldwide. However, the likelihood of nuclear power assuming a much larger role or even retaining its current share of electricity generation production is uncertain. The industry faces a complex set of issues including economic competitiveness, social acceptance, and the handling of nuclear waste, all of which contribute to the uncertain future of nuclear power. Nevertheless, for some countries the installed nuclear generating capacity is projected to continue to grow. Insufficient indigenous energy resources and concerns over energy independence make nuclear electric generation a viable option, especially for the countries of the Far East.

  5. CRAD, Nuclear Reactor Facility Operations - December 4, 2014...

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

    Reactor Facility Operations - December 4, 2014 (EA CRAD 31-08, Rev. 0) CRAD, Nuclear Reactor Facility Operations - December 4, 2014 (EA CRAD 31-08, Rev. 0) December 4, 2014 CRAD,...

  6. 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.

  7. Infrastructure and Operations | National Nuclear Security Administrati...

    National Nuclear Security Administration (NNSA)

    term needs. The Associate Administrator for Infrastructure and Operations develops and executes NNSA's infrastructure investment, maintenance, and operations programs and policies....

  8. 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.

  9. Our Operations | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Operations Infrastructure and Operations NNSA's missions require a secure production and laboratory infrastructure meeting immediate and long term needs. The Associate Administrator for Infrastructure and Operations develops and executes NNSA's infrastructure investment, maintenance, and operations programs and policies. Administration Programs Management and Budget The organization provides timely, cost-effective, and efficient administrative and financial support for NNSA headquarters staff.

  10. Expanding Options for Nuclear Power | Department of Energy

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

    Expanding Options for Nuclear Power Expanding Options for Nuclear Power April 15, 2013 - 10:12am Addthis The development of clean, affordable nuclear power options is a key element of the Energy Department's Nuclear Energy Research and Development Roadmap. As a part of this strategy, a high priority of the Department has been to help accelerate the timelines for the commercialization and deployment of small modular reactor (SMR) technologies through the SMR Licensing Technical Support program. |

  11. 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

  12. UNDERSTANDING SEISMIC DESIGN CRITERIA FOR JAPANESE NUCLEAR POWER PLANTS

    Office of Scientific and Technical Information (OSTI)

    UNDERSTANDING SEISMIC DESIGN CRITERIA FOR JAPANESE NUCLEAR POWER PLANTS Y.J. Park and C.H. Hofmayer Brookhaven National Laboratory Upton, Long Island, New York 11973 J.F. Costello U.S. Nuclear Regulatory Commission Washington, D.C. 20555 ABSTRACT 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.

  13. Nuclear power generation and fuel cycle report 1996

    SciTech Connect (OSTI)

    1996-10-01

    This report presents the current status and projections through 2015 of nuclear capacity, generation, and fuel cycle requirements for all countries using nuclear power to generate electricity for commercial use. It also contains information and forecasts of developments in the worldwide nuclear fuel market. Long term projections of U.S. nuclear capacity, generation, and spent fuel discharges for two different scenarios through 2040 are developed. A discussion on decommissioning of nuclear power plants is included.

  14. International Working Group Meeting Focuses on Nuclear Power Infrastructure

    Energy Savers [EERE]

    Development and Financing of New Nuclear Projects | Department of Energy Financing of New Nuclear Projects International Working Group Meeting Focuses on Nuclear Power Infrastructure Development and Financing of New Nuclear Projects December 15, 2009 - 1:09pm Addthis VIENNA, AUSTRIA - The multi-nation Infrastructure Development Working Group (IDWG) held its fifth meeting and also a workshop on the financing of international nuclear power projects in Vienna, Austria, on December 9-10, 2009.

  15. Decontamination and recovery of materials at nuclear facilites - operating history

    SciTech Connect (OSTI)

    Gillis, P.J. Jr.

    1994-12-31

    Non-Destructive Cleaning (NDC) Mobile CO{sub 2} Decontamination Facilities have more than 120 months of operational time conducting radioactive decontamination at Nuclear Power Stations and U.S. Department of Energy sites. During this time, we have compiled an extensive database on what has been decontaminated and the cost savings realized. The following are areas of interest: (1) how the CO{sub 2} decontamination process works; (2) how radioactive wastes are minimized and radioactive exposure to personnel is reduced with the use of the NDC Decontamination Facility; (3) how the self-contained Mobile Decontamination Facility works to provide adequate containment and control of the radioactive materials; (4) what kinds of items have been decontaminated, ranging from tools to underwater television cameras and from electric motors to lead shielding; (5) liquid radioactive waste volume reduction; (6) mixed-waste volume reduction; and (7) achievements in dose reduction to radiation levels that are as low as is reasonably achievable (ALARA) The design and operating features and performance of the Mobile Decontamination Facility, as well as the actual volumes of materials decontaminated, the decontamination factors achieved, the amounts and types of things that are free released, and the actual cost savings in all of these areas have been assessed. The data that was used is actual utility data and not the vendor`s data. All the experiences were from actual power plants.

  16. Infrastructure and Operations | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Infrastructure and Operations NNSA's missions require a secure production and laboratory infrastructure meeting immediate and long term needs. The Associate Administrator for Infrastructure and Operations develops and executes NNSA's infrastructure investment, maintenance, and operations programs and policies. Learn More Ten-Year Site Plans (TYSP) Related Topics infrastructure na-00 operations Related News NNSA Achieves Major Milestone in BUILDER Implementation Extended Life Program asks 'How do

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

    SciTech Connect (OSTI)

    Meijing Wu; Guozhang Shen [Qinshan Nuclear power company (China)

    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)

  18. 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

  19. Illinois Nuclear Profile - Clinton Power Station

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

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

  20. QUARTERLY NUCLEAR POWER DEPLOYMENT SUMMARY OCTOBER 2015

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

    January 2016 Page 1 News Updates The Nuclear Regulatory Commission has issued an ... have received COLs; six (totaling 10 nuclear reactors) remain under active Nuclear ...

  1. HIGH TEMPERATURE, HIGH POWER HETEROGENEOUS NUCLEAR REACTOR

    DOE Patents [OSTI]

    Hammond, R.P.; Wykoff, W.R.; Busey, H.M.

    1960-06-14

    A heterogeneous nuclear reactor is designed comprising a stationary housing and a rotatable annular core being supported for rotation about a vertical axis in the housing, the core containing a plurality of radial fuel- element supporting channels, the cylindrical empty space along the axis of the core providing a central plenum for the disposal of spent fuel elements, the core cross section outer periphery being vertically gradated in radius one end from the other to provide a coolant duct between the core and the housing, and means for inserting fresh fuel elements in the supporting channels under pressure and while the reactor is in operation.

  2. Energy Department Nuclear Systems Are Powering Mars Rover | Department of

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

    Energy Nuclear Systems Are Powering Mars Rover Energy Department Nuclear Systems Are Powering Mars Rover November 28, 2011 - 12:14pm Addthis Washington, D.C. - The Mars Science Laboratory rover, which launched from Cape Canaveral this weekend, is powered by nuclear systems developed by the U.S. Department of Energy (DOE), marking the 28th space mission supported by nuclear energy. This year also marks the 50th anniversary of nuclear-powered space exploration. To commemorate the launch, DOE

  3. emergency operations | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Apply for Our Jobs Our Jobs Working at NNSA Blog Home ... real-time response management system Pantex Emergency Services ... DHSNational Operations Center The Department of Energy ...

  4. Emergency Operations Training Academy | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    ... Introduction Monitoring Division Mgr Training, Adv NARAC Dispersion Modeling NARAC Web Operations Overview of Consequence Management Overview of the DOENNSA Emergency ...

  5. 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.

  6. Small Modular Reactors - Key to Future Nuclear Power

    Energy Savers [EERE]

    Small Modular Reactors - Key to Future Nuclear Power Generation in the U.S. 1,2 Robert Rosner and Stephen Goldberg Energy Policy Institute at Chicago The Harris School of Public Policy Studies Contributor: Joseph S. Hezir, Principal, EOP Foundation, Inc. Technical Paper, Revision 1 November, 2011 1 The research described in this paper was funded by the U.S. DOE through Argonne National Laboratory, which is operated by UChicago Argonne, LLC under contract No. DE-AC02-06CH1357. This report was

  7. Machinery monitoring system installed at nuclear power station

    SciTech Connect (OSTI)

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

    1981-10-01

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

  8. 20 MW Maibarara Geothermal Power Project Starts Commercial Operations...

    Open Energy Info (EERE)

    02092014 DOI Not Provided Check for DOI availability: http:crossref.org Online Internet link for 20 MW Maibarara Geothermal Power Project Starts Commercial Operations...

  9. At Vogtle, Big Results with Nuclear Power | Department of Energy

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

    At Vogtle, Big Results with Nuclear Power At Vogtle, Big Results with Nuclear Power February 20, 2014 - 1:29pm Addthis Construction work inside the Vogtle 3 and 4 module assembly building. | Photo courtesy of Georgia Power Company. Construction work inside the Vogtle 3 and 4 module assembly building. | Photo courtesy of Georgia Power Company. A look inside the Vogtle Unite 3 containment vessel bottom head. | Photo courtesy of Georgia Power Company. A look inside the Vogtle Unite 3 containment

  10. Space nuclear power, propulsion, and related technologies.

    SciTech Connect (OSTI)

    Berman, Marshall

    1992-01-01

    Sandia National Laboratories (Sandia) is one of the nation's largest research and development (R&D) facilities, with headquarters at Albuquerque, New Mexico; a laboratory at Livermore, California; and a test range near Tonopah, Nevada. Smaller testing facilities are also operated at other locations. Established in 1945, Sandia was operated by the University of California until 1949, when, at the request of President Truman, Sandia Corporation was formed as a subsidiary of Bell Lab's Western Electric Company to operate Sandia as a service to the U.S. Government without profit or fee. Sandia is currently operated for the U.S. Department of Energy (DOE) by AT&T Technologies, Inc., a wholly-owned subsidiary of AT&T. Sandia's responsibility is national security programs in defense and energy with primary emphasis on nuclear weapon research and development (R&D). However, Sandia also supports a wide variety of projects ranging from basic materials research to the design of specialized parachutes. Assets, owned by DOE and valued at more than $1.2 billion, include about 600 major buildings containing about 372,000 square meters (m2) (4 million square feet [ft2]) of floor space, located on land totalling approximately 1460 square kilometers (km2) (562 square miles [mi]). Sandia employs about 8500 people, the majority in Albuquerque, with about 1000 in Livermore. Approximately 60% of Sandia's employees are in technical and scientific positions, and the remainder are in crafts, skilled labor, and administrative positions. As a multiprogram national laboratory, Sandia has much to offer both industrial and government customers in pursuing space nuclear technologies. The purpose of this brochure is to provide the reader with a brief summary of Sandia's technical capabilities, test facilities, and example programs that relate to military and civilian objectives in space. Sandia is interested in forming partnerships with industry and government organizations, and has already formed several cooperative alliances and agreements. Because of the synergism of multiple governmental and industrial sponsors of many programs, Sandia is frequently able to provide complex technical solutions in a relatively short time, and often at lower cost to a particular customer. They have listed a few ongoing programs at Sandia related to space nuclear technology as examples of the possible synergisms that could result from forming teams and partnerships with related technologies and objectives.

  11. Safety approaches for high power modular laser operation

    SciTech Connect (OSTI)

    Handren, R.T.

    1993-03-01

    Approximately 20 years ago, a program was initiated at the Lawrence Livermore National Laboratory (LLNL) to study the feasibility of using lasers to separate isotopes of uranium and other materials. Of particular interest has been the development of a uranium enrichment method for the production of commercial nuclear power reactor fuel to replace current more expensive methods. The Uranium Atomic Vapor Laser Isotope Separation (U-AVLIS) Program has progressed to the point where a plant-scale facility to demonstrate commercial feasibility has been built and is being tested. The U-AVLIS Program uses copper vapor lasers which pump frequency selective dye lasers to photoionize uranium vapor produced by an electron beam. The selectively ionized isotopes are electrostatically collected. The copper lasers are arranged in oscillator/amplifier chains. The current configuration consists of 12 chains, each with a nominal output of 800 W for a system output in excess of 9 kW. The system requirements are for continuous operation (24 h a day, 7 days a week) and high availability. To meet these requirements, the lasers are designed in a modular form allowing for rapid change-out of the lasers requiring maintenance. Since beginning operation in early 1985, the copper lasers have accumulated over 2 million unit hours at a >90% availability. The dye laser system provides approximately 2.5 kW average power in the visible wavelength range. This large-scale laser system has many safety considerations, including high-power laser beams, high voltage, and large quantities ({approximately}3000 gal) of ethanol dye solutions. The Laboratory`s safety policy requires that safety controls be designed into any process, equipment, or apparatus in the form of engineering controls. Administrative controls further reduce the risk to an acceptable level. Selected examples of engineering and administrative controls currently being used in the U-AVLIS Program are described.

  12. 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)

  13. Energy Department Nuclear Systems Are Powering Mars Rover | Department...

    Office of Environmental Management (EM)

    by the U.S. Department of Energy (DOE), marking the 28th space mission supported by nuclear energy. This year also marks the 50th anniversary of nuclear-powered space exploration. ...

  14. Nuclear Systems Powering a Mission to Mars | Department of Energy

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

    Systems Powering a Mission to Mars Nuclear Systems Powering a Mission to Mars November 28, 2011 - 11:23am Addthis Radioisotope Power Systems, a strong partnership between the Energy Department's Office of Nuclear Energy and NASA, has been providing the energy for deep space exploration. Assistant Secretary Lyons Assistant Secretary Lyons Assistant Secretary for Nuclear Energy Curiosity Mission: investigate whether the Gale Crater on Mars has ever offered environmental conditions that support the

  15. Pyroelectric Energy Scavenging Techniques for Self-Powered Nuclear Reactor

    Office of Scientific and Technical Information (OSTI)

    Wireless Sensor Networks (Journal Article) | SciTech Connect Journal Article: Pyroelectric Energy Scavenging Techniques for Self-Powered Nuclear Reactor Wireless Sensor Networks Citation Details In-Document Search Title: Pyroelectric Energy Scavenging Techniques for Self-Powered Nuclear Reactor Wireless Sensor Networks Recent advances in technologies for harvesting waste thermal energy from ambient environments present an opportunity to implement truly wireless sensor nodes in nuclear power

  16. President Obama Announces Loan Guarantees to Construct New Nuclear Power

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

    Reactors in Georgia | Department of Energy Loan Guarantees to Construct New Nuclear Power Reactors in Georgia President Obama Announces Loan Guarantees to Construct New Nuclear Power Reactors in Georgia February 16, 2010 - 12:00am Addthis Washington D.C. --- Underscoring his Administration's commitment to jumpstarting the nation's nuclear power industry, President Obama today announced that the Department of Energy has offered conditional commitments for a total of $8.33 billion in loan

  17. QUARTERLY NUCLEAR POWER DEPLOYMENT SUMMARY JANUARY 2016

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

    JANUARY 2016 Updates available at: www.energy.gov/ne NEXT UPDATE - April 2016 Page 1 News Updates  The Tennessee Valley Authority has completed fuel loading of the Watts Bar Unit 2 reactor. TVA plans to begin commercial operation of the 1,150 MW reactor in early 2016 following completion of power ascension testing.  The final environmental impact statement for the PSEG Early Site Permit (ESP) has been completed; an ESP could be issued as early as mid- 2016. If approved, the permit will be

  18. 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.

  19. National Nuclear Security Administration Official Tours Cleanup Operations for Navy

    Broader source: Energy.gov [DOE]

    RICHLAND, Wash. – Adm. James F. Caldwell Jr., director of the DOE National Nuclear Security Administration’s Naval Nuclear Propulsion Program, recently toured the Hanford Site cleanup activities managed by EM’s Richland Operations Office (RL). RL Manager Stacy Charboneau welcomed Caldwell to the site.

  20. Learn More About NNSA's Emergency Operations Office | National Nuclear

    National Nuclear Security Administration (NNSA)

    Security Administration Emergency Response Learn More About NNSA's Emergency Operations Office NNSA ensures that capabilities are in place to respond to any NNSA and Department of Energy facility emergency. It is also the nation's premier responder to any nuclear or radiological incident within the United States or abroad and provides operational planning and training to counter both domestic and international nuclear terrorism. NNSA ensures that capabilities are in place to respond to any

  1. 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.

  2. QUARTERLY NUCLEAR POWER DEPLOYMENT SUMMARY JULY 2013 News Updates

    Energy Savers [EERE]

    late 2015. Dominion Virginia Power has not yet committed to building a new nuclear unit at North Anna. NRC ... of independence between safety related and non-safety ...

  3. Sandia Nuclear Power Safety Expert Elected to National Academy...

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

    Nuclear Power Safety Expert Elected to National Academy of Engineering - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure ...

  4. Guidance for Deployment of Mobile Technologies for Nuclear Power...

    Energy Savers [EERE]

    Guidance for Deployment of Mobile Technologies for Nuclear Power Plant Field Workers Guidance ... Additional benefits in safety, efficiency, and productivity are highly probable given ...

  5. Guangdong Nuclear Power and New Energy Industrial Investment...

    Open Energy Info (EERE)

    Investment Fund Management Company Jump to: navigation, search Name: Guangdong Nuclear Power and New Energy Industrial Investment Fund Management Company Place: Shenzhen,...

  6. State Nuclear Power Technology Corporation SNPTC | Open Energy...

    Open Energy Info (EERE)

    Technology Corporation SNPTC Jump to: navigation, search Name: State Nuclear Power Technology Corporation (SNPTC) Place: Beijing, Beijing Municipality, China Zip: 100032 Product:...

  7. UNDERSTANDING SEISMIC DESIGN CRITERIA FOR JAPANESE NUCLEAR POWER...

    Office of Scientific and Technical Information (OSTI)

    MITI Orders and Notifications: e MITI Order No. 62, "Technical Standards for Nuclear Power Plant Facilities", 1989 (Ref lo). MITI Notification No. 501, "Technical Standards for...

  8. Economic Conditions and Factors Affecting New Nuclear Power Deployment...

    Office of Scientific and Technical Information (OSTI)

    ... With a multiple-year lead time, nuclear power plants are acutely vulnerable to market corrections. less Authors: Harrison, Thomas J. 1 + Show Author Affiliations Oak Ridge ...

  9. 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.

  10. 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.

  11. Facts and Lessons of the Fukushima Nuclear Accident and Safety Improvement- The Operator Viewpoints

    Broader source: Energy.gov [DOE]

    Presenter: Akira Kawano, General Manager, Nuclear International Relations and Strategy Group, Nuclear Power and Plant Siting Administrative Department, Tokyo Electric Power Company

  12. QUARTERLY NUCLEAR POWER DEPLOYMENT SUMMARY JANUARY 2016

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

    COLs; six (totaling 10 nuclear reactors) remain under active Nuclear Regulatory Commission (NRC) review, 9 were suspended 1 due to utility economic or other considerations. ...

  13. Computing an operating parameter of a unified power flow controller

    DOE Patents [OSTI]

    Wilson, David G; Robinett, III, Rush D

    2015-01-06

    A Unified Power Flow Controller described herein comprises a sensor that outputs at least one sensed condition, a processor that receives the at least one sensed condition, a memory that comprises control logic that is executable by the processor; and power electronics that comprise power storage, wherein the processor causes the power electronics to selectively cause the power storage to act as one of a power generator or a load based at least in part upon the at least one sensed condition output by the sensor and the control logic, and wherein at least one operating parameter of the power electronics is designed to facilitate maximal transmittal of electrical power generated at a variable power generation system to a grid system while meeting power constraints set forth by the electrical power grid.

  14. Sandia Nuclear Power Safety Expert Elected to National Academy of

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

    Engineering Nuclear Power Safety Expert Elected to National Academy of Engineering - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing

  15. Summary of space nuclear reactor power systems, 1983--1992

    SciTech Connect (OSTI)

    Buden, D.

    1993-08-11

    This report summarizes major developments in the last ten years which have greatly expanded the space nuclear reactor power systems technology base. In the SP-100 program, after a competition between liquid-metal, gas-cooled, thermionic, and heat pipe reactors integrated with various combinations of thermoelectric thermionic, Brayton, Rankine, and Stirling energy conversion systems, three concepts:were selected for further evaluation. In 1985, the high-temperature (1,350 K), lithium-cooled reactor with thermoelectric conversion was selected for full scale development. Since then, significant progress has been achieved including the demonstration of a 7-y-life uranium nitride fuel pin. Progress on the lithium-cooled reactor with thermoelectrics has progressed from a concept, through a generic flight system design, to the design, development, and testing of specific components. Meanwhile, the USSR in 1987--88 orbited a new generation of nuclear power systems beyond the, thermoelectric plants on the RORSAT satellites. The US has continued to advance its own thermionic fuel element development, concentrating on a multicell fuel element configuration. Experimental work has demonstrated a single cell operating time of about 1 1/2-y. Technology advances have also been made in the Stirling engine; an advanced engine that operates at 1,050 K is ready for testing. Additional concepts have been studied and experiments have been performed on a variety of systems to meet changing needs; such as powers of tens-to-hundreds of megawatts and highly survivable systems of tens-of-kilowatts power.

  16. Concept of Operations for Nuclear Warhead Embedded Sensors

    SciTech Connect (OSTI)

    Rockett, P D; Koncher, T R

    2012-05-16

    Embedded arms-control-sensors provide a powerful new paradigm for managing compliance with future nuclear weapons treaties, where deployed warhead numbers will be reduced to 1000 or less. The CONOPS (Concept of Operations) for use with these sensors is a practical tool with which one may help define design parameters, including size, power, resolution, communications, and physical structure. How frequently must data be acquired and must a human be present? Will such data be acquired for only stored weapons or will it be required of deployed weapons as well? Will tactical weapons be subject to such monitoring or will only strategic weapons apply? Which data will be most crucial? Will OSI's be a component of embedded sensor data management or will these sensors stand alone in their data extraction processes? The problem space is massive, but can be constrained by extrapolating to a reasonable future treaty regime and examining the bounded options this scenario poses. Arms control verification sensors, embedded within the warhead case or aeroshell, must provide sufficient but not excessively detailed data, confirming that the item is a nuclear warhead and that it is a particular warhead without revealing sensitive information. Geolocation will be provided by an intermediate transceiver used to acquire the data and to forward the data to a central processing location. Past Chain-of-Custody projects have included such devices and will be primarily responsible for adding such indicators in the future. For the purposes of a treaty regime a TLI will be verified as a nuclear warhead by knowledge of (a) the presence and mass of SNM, (b) the presence of HE, and (c) the reporting of a unique tag ID. All of these parameters can be obtained via neutron correlation measurements, Raman spectroscopy, and fiber optic grating fabrication, respectively. Data from these sensors will be pushed out monthly and acquired nearly daily, providing one of several verification layers in depth, including on-site inspections, NTM, declarations, and semi-annual BCC meetings. Human intervention will not be necessary. The sheer numbers, small size, and wide distribution of warhead TLIs will mandate the added level of remote monitoring that Embedded Sensors can provide. This multilayer protection will limit the need to increase the frequency of OSIs, by adding confidence that declared TLIs remain as declared and that no undeclared items enter the regime without the other States Party's knowledge. Acceptance of Embedded arms control Sensor technologies will require joint development by all State's Parties involved. Principles of operation and robustness of technologies must be individually evaluated to sustain confidence in the strength of this system against attack. Weapons designers must be assured that these sensors will in no way impact weapon performance and operation, will not affect weapons security and safety, and will have a neutral impact upon weapon system surety. Each State's Party will need to conduct an in depth review of their weapons lifecycle to determine where moves may be reduced to minimize vulnerabilities and where random selection may be used to minimize the ability to make undeclared changes. In the end Verification is a political measure, not a technical one. If the potential users can gain sufficient confidence in the application of Embedded arms control Sensors, they could constitute the final layer of glue to hold together the next Nuclear Arms Control agreement.

  17. Surveillance dosimetry of operating power plants

    SciTech Connect (OSTI)

    McElroy, W.N.; Davis, A.I.; Gold, R.

    1981-10-16

    The main focus of the research efforts presently underway is the LWR power reactor surveillance program in which metallurgical test specimens of the reactor PV and dosimetry sensors are placed in three or more surveillance capsules at or near the reactor PV inner wall. They are then irradiated in a temperature and neutron flux-spectrum environment as similar as possible to the PV itself for periods of about 1.5 to 15 effective full-power years (EFPY), with removal of the last capsule at a fluence corresponding to the 30- to 40-year plant end-of-life (EOL) fluence. Because the neutron flux level at the surveillance position is greater than at the vessel, the test is accelerated wit respect to the vessel exposure, allowing early assessment of EOL conditions.

  18. 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.

  19. Fitness for duty in the nuclear power industry

    SciTech Connect (OSTI)

    Durbin, N.; Moore, C.; Grant, T.; Fleming, T.; Hunt, P.; Martin, R.; Murphy, S.; Hauth, J.; Wilson, R.; Bittner, A.; Bramwell, A.; Macaulay, J.; Olson, J.; Terrill, E.; Toquam, J. )

    1991-09-01

    This report presents an overview of the NRC licensees' implementation of the FFD program during the first full year of the program's operation and provides new information on a variety of FFD technical issues. The purpose of this document is to contribute to appropriate changes to the rule, to the inspection process, and to other NRC activities. It describes the characteristics of licensee programs, discusses the results of NRC inspections, updates technical information covered in previous reports, and identifies lessons learned during the first year. Overall, the experience of the first full year of licensees' FFD program operations indicates that licensees have functioning fitness for duty programs devoted to the NRC rule's performance objectives of achieving drug-free workplaces in which nuclear power plant personnel are not impaired as they perform their duties. 96 refs., 14 tabs.

  20. DOE Orders Mirant Power Plant to Operate Under Limited Circumstances |

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

    Department of Energy Mirant Power Plant to Operate Under Limited Circumstances DOE Orders Mirant Power Plant to Operate Under Limited Circumstances December 20, 2005 - 11:44am Addthis DOE finds emergency; determines plant will help electric reliability WASHINGTON, D.C. - Secretary of Energy Samuel W. Bodman today issued an order requiring Mirant Corporation's Potomac River Generating Station in Alexandria, Virginia (Mirant) to immediately resume limited operation. The order will help provide

  1. DOE Orders Mirant Power Plant to Operate Under Limited Circumstances |

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

    Department of Energy Orders Mirant Power Plant to Operate Under Limited Circumstances DOE Orders Mirant Power Plant to Operate Under Limited Circumstances Docket No. EO-05-01. Order No. 202-05-3: Secretary of Energy Samuel W. Bodman today issued an order requiring Mirant Corporation's Potomac River Generating Station in Alexandria, Virginia (Mirant) to immediately resume limited operation. The order will help provide electric reliability for Washington, D.C., and will do so at the lowest

  2. infrastructure and operations | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    infrastructure and operations NSC completes last part to facilitate relocation This month, employees at the National Security Campus in Kansas City, Mo., are celebrating the completion of the last "build ahead" part needed to maintain their 99.9 percent on-time delivery record during one of the nation's largest industrial moves. More than 275 unique part numbers encompassing... Ten-Year Site Plans (TYSP) The FY 2016-2025 TYSPs are planning documents and as such, represent possible

  3. 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.

  4. Economic Conditions and Factors Affecting New Nuclear Power Deployment

    Office of Scientific and Technical Information (OSTI)

    (Technical Report) | SciTech Connect Economic Conditions and Factors Affecting New Nuclear Power Deployment Citation Details In-Document Search Title: Economic Conditions and Factors Affecting New Nuclear Power Deployment This report documents work performed in support of the US Department of Energy Office of Nuclear Energy's Advanced Small Modular Reactor (AdvSMR) program. The report presents information and results from economic analyses to describe current electricity market conditions

  5. Use of wind power forecasting in operational decisions.

    SciTech Connect (OSTI)

    Botterud, A.; Zhi, Z.; Wang, J.; Bessa, R.J.; Keko, H.; Mendes, J.; Sumaili, J.; Miranda, V.

    2011-11-29

    The rapid expansion of wind power gives rise to a number of challenges for power system operators and electricity market participants. The key operational challenge is to efficiently handle the uncertainty and variability of wind power when balancing supply and demand in ths system. In this report, we analyze how wind power forecasting can serve as an efficient tool toward this end. We discuss the current status of wind power forecasting in U.S. electricity markets and develop several methodologies and modeling tools for the use of wind power forecasting in operational decisions, from the perspectives of the system operator as well as the wind power producer. In particular, we focus on the use of probabilistic forecasts in operational decisions. Driven by increasing prices for fossil fuels and concerns about greenhouse gas (GHG) emissions, wind power, as a renewable and clean source of energy, is rapidly being introduced into the existing electricity supply portfolio in many parts of the world. The U.S. Department of Energy (DOE) has analyzed a scenario in which wind power meets 20% of the U.S. electricity demand by 2030, which means that the U.S. wind power capacity would have to reach more than 300 gigawatts (GW). The European Union is pursuing a target of 20/20/20, which aims to reduce greenhouse gas (GHG) emissions by 20%, increase the amount of renewable energy to 20% of the energy supply, and improve energy efficiency by 20% by 2020 as compared to 1990. Meanwhile, China is the leading country in terms of installed wind capacity, and had 45 GW of installed wind power capacity out of about 200 GW on a global level at the end of 2010. The rapid increase in the penetration of wind power into power systems introduces more variability and uncertainty in the electricity generation portfolio, and these factors are the key challenges when it comes to integrating wind power into the electric power grid. Wind power forecasting (WPF) is an important tool to help efficiently address this challenge, and significant efforts have been invested in developing more accurate wind power forecasts. In this report, we document our work on the use of wind power forecasting in operational decisions.

  6. Klotz visits Bettis Atomic Power Laboratory | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration Klotz visits Bettis Atomic Power Laboratory Wednesday, July 8, 2015 - 1:03pm Lt. Gen. Frank G. Klotz, DOE Undersecretary for Nuclear Security and NNSA Administrator, visited the Bettis Atomic Power Laboratory in West Mifflin, PA on July 2, 2015. NNSA Blog Gen. Klotz toured through several test facilities where Bettis personnel reviewed ongoing development efforts to qualify techniques for in-situ repairs of nuclear powered submarine components, discussed full scale flow

  7. Office of Analysis and Evaluation of Operational Data 1989 annual report, Power reactors

    SciTech Connect (OSTI)

    1990-07-01

    The annual report of the US Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data (AEOD) is devoted to the activities performed during 1989. The report is published in two separate parts. This document, NUREG-1272, Vol. 4, No. 1, covers power reactors and presents an overview of the operating experience of the nuclear power industry from the NRC perspective, including comments about the trends of some key performance measures. The report also includes the principal findings and issues identified in AEOD studies over the past year and summarizes information from such sources as licensee event reports, diagnostic evaluations, and reports to the NRC's Operations Center. This report also compiles the status of staff actions resulting from previous Incident Investigation Team (IIT) reports. 16 figs., 9 tabs.

  8. STATEMENT OF CLAUDIA ANDREWS CHIEF OPERATING OFFICER BONNEVILLE POWER ADMINISTRATION

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

    STATEMENT OF CLAUDIA ANDREWS CHIEF OPERATING OFFICER BONNEVILLE POWER ADMINISTRATION U.S. DEPARTMENT OF ENERGY BEFORE THE SUBCOMMITTEE ON WATER, POWER AND OCEANS COMMITTEE ON NATURAL RESOURCES U.S. HOUSE OF REPRESENTATIVES MARCH 22, 2016 EXAMINING THE MISSIONS AND IMPACTS OF THE PRESIDENT'S PROPOSED FISCAL YEAR 2017 BUDGETS OF THE U.S. FISH AND WILDLIFE SERVICE, THE NATIONAL OCEANIC AND ATMOSPHERIC ADMINISTRATION, THE BUREAU OF RECLAMATION AND THE POWER MARKETING ADMINISTRATIONS Mr. Chairman,

  9. 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.

  10. 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.

  11. Joint Technical Operations Team | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Joint Technical Operations Team JTOT Logo NNSA's Joint Technical Operations Team (JTOT) provides specialized technical capabilities in support of lead federal agencies to respond to weapons of mass destruction. Furthermore, the JTOT provides real-time technical support to other deployed NNSA emergency response assets through the JTOT Home Team. Mission The JTOT mission is to provide scientific and technical support of the lead federal agency during all aspects of a nuclear or radiological

  12. 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.

  13. solar power | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    power NNSA missions now powered by California gold...en sunshine An NNSA national laboratory is taking advantage of California's blue skies to power critical national security and science research. The solar power system installed at Lawrence Livermore National Laboratory (LLNL) is now fully functional and producing electricity. In 2015, NNSA announced the... Final row of solar panels installed at Livermore The last row of panels at the Whitethorn Solar Facility project site at Lawrence

  14. Closed Brayton cycle power conversion systems for nuclear reactors :

    SciTech Connect (OSTI)

    Wright, Steven A.; Lipinski, Ronald J.; Vernon, Milton E.; Sanchez, Travis

    2006-04-01

    This report describes the results of a Sandia National Laboratories internally funded research program to study the coupling of nuclear reactors to gas dynamic Brayton power conversion systems. The research focused on developing integrated dynamic system models, fabricating a 10-30 kWe closed loop Brayton cycle, and validating these models by operating the Brayton test-loop. The work tasks were performed in three major areas. First, the system equations and dynamic models for reactors and Closed Brayton Cycle (CBC) systems were developed and implemented in SIMULINKTM. Within this effort, both steady state and dynamic system models for all the components (turbines, compressors, reactors, ducting, alternators, heat exchangers, and space based radiators) were developed and assembled into complete systems for gas cooled reactors, liquid metal reactors, and electrically heated simulators. Various control modules that use proportional-integral-differential (PID) feedback loops for the reactor and the power-conversion shaft speed were also developed and implemented. The simulation code is called RPCSIM (Reactor Power and Control Simulator). In the second task an open cycle commercially available Capstone C30 micro-turbine power generator was modified to provide a small inexpensive closed Brayton cycle test loop called the Sandia Brayton test-Loop (SBL-30). The Capstone gas-turbine unit housing was modified to permit the attachment of an electrical heater and a water cooled chiller to form a closed loop. The Capstone turbine, compressor, and alternator were used without modification. The Capstone systems nominal operating point is 1150 K turbine inlet temperature at 96,000 rpm. The annular recuperator and portions of the Capstone control system (inverter) and starter system also were reused. The rotational speed of the turbo-machinery is controlled by adjusting the alternator load by using the electrical grid as the load bank. The SBL-30 test loop was operated at the manufacturers site (Barber-Nichols Inc.) and installed and operated at Sandia. A sufficiently detailed description of the loop is provided in this report along with the design characteristics of the turbo-alternator-compressor set to allow other researchers to compare their results with those measured in the Sandia test-loop. The third task consisted of a validation effort. In this task the test loop was operated and compared with the modeled results to develop a more complete understanding of this electrically heated closed power generation system and to validate the model. The measured and predicted system temperatures and pressures are in good agreement, indicating that the model is a reasonable representation of the test loop. Typical deviations between the model and the hardware results are less than 10%. Additional tests were performed to assess the capability of the Brayton engine to continue to remove decay heat after the reactor/heater is shutdown, to develop safe and effective control strategies, and to access the effectiveness of gas inventory control as an alternative means to provide load following. In one test the heater power was turned off to simulate a rapid reactor shutdown, and the turbomachinery was driven solely by the sensible heat stored in the heater for over 71 minutes without external power input. This is an important safety feature for CBC systems as it means that the closed Brayton loop will keep cooling the reactor without the need for auxiliary power (other than that needed to circulate the waste heat rejection coolant) provided the heat sink is available.

  15. 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.

  16. QUARTERLY NUCLEAR POWER DEPLOYMENT SUMMARY APRIL 2013 News Updates

    Energy Savers [EERE]

    ... A Ph. 2 1 Reference COL Application (R-COL) 4 Safety Review: R-COL Ph 1 Issue RAIs ... UPDATE - July 2013 Page 1 QUARTERLY NUCLEAR POWER DEPLOYMENT SUMMARY APRIL 2013 Small ...

  17. Annex: Attributes of Proliferation Resistance for Civilian Nuclear Power Systems

    Broader source: Energy.gov [DOE]

    The NERAC1 Task Force on Technology Opportunities for Increasing the Proliferation Resistance of Global Civilian Nuclear Power Systems (TOPS) determined at its first meeting in November 1999 that a...

  18. 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...

  19. Business risks to utilities as new nuclear power costs escalate

    SciTech Connect (OSTI)

    Severance, Craig A.

    2009-05-15

    A nuclear power megaproject carries with it severe business risks. Despite attempts to shift these risks to taxpayers and ratepayers, ultimately there are no guarantees for utility shareholders. Utility management needs to keep some core principles in mind. (author)

  20. DOE, Invensys Operations Management to Develop, Deploy Operator Training System for Supercritical Coal Power Plants

    Broader source: Energy.gov [DOE]

    A new U.S. Department of Energy cooperative research and development agreement to develop, test, and deploy a dynamic simulator and operator training system could eventually help commercialize important carbon capture technologies at the nation’s power plants.

  1. 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)

  2. Source term estimation during incident response to severe nuclear power

    Office of Scientific and Technical Information (OSTI)

    plant accidents (Technical Report) | SciTech Connect Source term estimation during incident response to severe nuclear power plant accidents Citation Details In-Document Search Title: Source term estimation during incident response to severe nuclear power plant accidents × You are accessing a document from the Department of Energy's (DOE) SciTech Connect. This site is a product of DOE's Office of Scientific and Technical Information (OSTI) and is provided as a public service. Visit OSTI to

  3. Nuclear stopping power in warm and hot dense matter

    SciTech Connect (OSTI)

    Faussurier, Gerald; Blancard, Christophe; Gauthier, Maxence

    2013-01-15

    We present a method to estimate the nuclear component of the stopping power of ions propagating in dense matter. Three kinds of effective pair potentials are proposed. Results from the warm dense matter regime and the domain of high energy density physics are presented and discussed for proton and helium. The role of ionic temperature is examined. The nuclear stopping power can play a noticeable role in hot dense matter.

  4. Renewing America's Nuclear Power Partnership for Energy Security and

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

    Economic Growth | Department of Energy Renewing America's Nuclear Power Partnership for Energy Security and Economic Growth Renewing America's Nuclear Power Partnership for Energy Security and Economic Growth October 8, 2008 - 4:14pm Addthis Remarks as Prepared for Delivery by Secretary Bodman Thank you, Jamie, for that kind introduction. And many thanks as well to Secretary Gutierrez, Deputy Secretary Sullivan and the entire Commerce team for convening this important event. As always, it's

  5. QUARTERLY NUCLEAR POWER DEPLOYMENT SUMMARY JULY 2014

    Energy Savers [EERE]

    4 Updates available at: www.energy.gov/ne NEXT UPDATE - October 2014 Page 1 News Updates  The NRC Atomic Safety and Licensing Board (ASLB) has ruled that Toshiba's participation in Nuclear Innovation North America's South Texas Project does not violate federal rules on foreign ownership, control or domination of nuclear reactors. NRC staff had previously stated that despite having only a 10% ownership stake in the project, Toshiba's level of financial support constituted an impermissible

  6. Converting Maturing Nuclear Sites to Integrated Power Production Islands

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

    Solbrig, Charles W.

    2011-01-01

    Nuclear islands, which are integrated power production sites, could effectively sequester and safeguard the US stockpile of plutonium. A nuclear island, an evolution of the integral fast reactor, utilizes all the Transuranics (Pu plus minor actinides) produced in power production, and it eliminates all spent fuel shipments to and from the site. This latter attribute requires that fuel reprocessing occur on each site and that fast reactors be built on-site to utilize the TRU. All commercial spent fuel shipments could be eliminated by converting all LWR nuclear power sites to nuclear islands. Existing LWR sites have the added advantage ofmore » already possessing a license to produce nuclear power. Each could contribute to an increase in the nuclear power production by adding one or more fast reactors. Both the TRU and the depleted uranium obtained in reprocessing would be used on-site for fast fuel manufacture. Only fission products would be shipped to a repository for storage. The nuclear island concept could be used to alleviate the strain of LWR plant sites currently approaching or exceeding their spent fuel pool storage capacity. Fast reactor breeding ratio could be designed to convert existing sites to all fast reactors, or keep the majority thermal.« less

  7. Report to the US Nuclear Regulatory Commission on Analysis and Evaluation of Operational Data, 1986

    SciTech Connect (OSTI)

    1987-05-01

    This annual report of the US Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data (AEOD) is devoted to the activities performed during calendar year 1986. Comments and observations are provided on operating experience at nuclear power plants and other NRC licensees, including results from selected AEOD studies; summaries of abnormal occurrences involving US nuclear plants; reviews of licensee event reports and their quality, reactor scram experience from 1984 to 1986, engineered safety features actuations, and the trends and patterns analysis program; and assessments of nonreactor and medical misadministration events. In addition, the report provides the year-end status of all recommendations included in AEOD studies, and listings of all AEOD reports issued from 1980 through 1986.

  8. HIGH EFFICIENCY GENERATION OF HYDROGEN FUELS USING NUCLEAR POWER

    SciTech Connect (OSTI)

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

    2003-06-01

    OAK B202 HIGH EFFICIENCY GENERATION OF HYDROGEN FUELS USING NUCLEAR POWER. Combustion of fossil fuels, used to power transportation, generate electricity, heat homes and fuel industry provides 86% of the world's energy. Drawbacks to fossil fuel utilization include limited supply, pollution, and carbon dioxide emissions. Carbon dioxide emissions, thought to be responsible for global warming, are now the subject of international treaties. Together, these drawbacks argue for the replacement of fossil fuels with a less-polluting potentially renewable primary energy such as nuclear energy. Conventional nuclear plants readily generate electric power but fossil fuels are firmly entrenched in the transportation sector. Hydrogen is an environmentally attractive transportation fuel that has the potential to displace fossil fuels. Hydrogen will be particularly advantageous when coupled with fuel cells. Fuel cells have higher efficiency than conventional battery/internal combustion engine combinations and do not produce nitrogen oxides during low-temperature operation. Contemporary hydrogen production is primarily based on fossil fuels and most specifically on natural gas. When hydrogen is produced using energy derived from fossil fuels, there is little or no environmental advantage. There is currently no large scale, cost-effective, environmentally attractive hydrogen production process available for commercialization, nor has such a process been identified. The objective of this work is to find an economically feasible process for the production of hydrogen, by nuclear means, using an advanced high-temperature nuclear reactor as the primary energy source. Hydrogen production by thermochemical water-splitting (Appendix A), a chemical process that accomplishes the decomposition of water into hydrogen and oxygen using only heat or, in the case of a hybrid thermochemical process, by a combination of heat and electrolysis, could meet these goals. Hydrogen produced from fossil fuels has trace contaminants (primarily carbon monoxide) that are detrimental to precious metal catalyzed fuel cells, as is now recognized by many of the world's largest automobile companies. Thermochemical hydrogen will not contain carbon monoxide as an impurity at any level. Electrolysis, the alternative process for producing hydrogen using nuclear energy, suffers from thermodynamic inefficiencies in both the production of electricity and in electrolytic parts of the process. The efficiency of electrolysis (electricity to hydrogen) is currently about 80%. Electric power generation efficiency would have to exceed 65% (thermal to electrical) for the combined efficiency to exceed the 52% (thermal to hydrogen) calculated for one thermochemical cycle. Thermochemical water-splitting cycles have been studied, at various levels of effort, for the past 35 years. They were extensively studied in the late 70s and early 80s but have received little attention in the past 10 years, particularly in the U.S. While there is no question about the technical feasibility and the potential for high efficiency, cycles with proven low cost and high efficiency have yet to be developed commercially. Over 100 cycles have been proposed, but substantial research has been executed on only a few. This report describes work accomplished during a three-year project whose objective is to ''define an economically feasible concept for production of hydrogen, by nuclear means, using an advanced high temperature nuclear reactor as the energy source.'' The emphasis of the first phase was to evaluate thermochemical processes which offer the potential for efficient, cost-effective, large-scale production of hydrogen from water in which the primary energy input is high temperature heat from an advanced nuclear reactor and to select one (or, at most three) for further detailed consideration. During Phase 1, an exhaustive literature search was performed to locate all cycles previously proposed. The cycles located were screened using objective criteria to determine which could benefit, in terms of efficiency and cost, from the high-temperature capabilities of advanced nuclear reactors. The more promising cycles were then analyzed in depth as to their adaptability to advanced high-temperature nuclear reactors. As a result, the Sulfur-Iodine (S-I) cycle was selected for integration into the advanced nuclear reactor system. In Phases 2 and 3, alternative flowsheets were developed and compared. This effort entailed a considerable effort into developing the solution thermodynamics pertinent to the S-I cycle.

  9. Fault Diagnosis with Multi-State Alarms in a Nuclear Power Control Simulation

    SciTech Connect (OSTI)

    Stuart A. Ragsdale; Roger Lew; Ronald L. Boring

    2014-09-01

    This research addresses how alarm systems can increase operator performance within nuclear power plant operations. The experiment examined the effects of two types of alarm systems (two-state and three-state alarms) on alarm compliance and diagnosis for two types of faults differing in complexity. We hypothesized the use of three-state alarms would improve performance in alarm recognition and fault diagnoses over that of two-state alarms. Sensitivity and criterion based on the Signal Detection Theory were used to measure performance. We further hypothesized that operator trust would be highest when using three-state alarms. The findings from this research showed participants performed better and had more trust in three-state alarms compared to two-state alarms. Furthermore, these findings have significant theoretical implications and practical applications as they apply to improving the efficiency and effectiveness of nuclear power plant operations.

  10. FAULT DIAGNOSIS WITH MULTI-STATE ALARMS IN A NUCLEAR POWER CONTROL SIMULATOR

    SciTech Connect (OSTI)

    Austin Ragsdale; Roger Lew; Brian P. Dyre; Ronald L. Boring

    2012-10-01

    This research addresses how alarm systems can increase operator performance within nuclear power plant operations. The experiment examined the effect of two types of alarm systems (two-state and three-state alarms) on alarm compliance and diagnosis for two types of faults differing in complexity. We hypothesized three-state alarms would improve performance in alarm recognition and fault diagnoses over that of two-state alarms. We used sensitivity and criterion based on Signal Detection Theory to measure performance. We further hypothesized that operator trust would be highest when using three-state alarms. The findings from this research showed participants performed better and had more trust in three-state alarms compared to two-state alarms. Furthermore, these findings have significant theoretical implications and practical applications as they apply to improving the efficiency and effectiveness of nuclear power plant operations.

  11. 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)

  12. Office of Safety Infrastructure & Operations | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration Safety Infrastructure & Operations NNSA's G2 Management Information System Wins Association for Enterprise Information's (AFEI) "Excellence in Enterprise Information Award" The G2 team and the 2015 Association for Enterprise Information's (AFEI) Excellence in Enterprise Information Award. (WASHINGTON, D.C) - The National Nuclear Security Administration (NNSA) has received the 2015 Association for Enterprise Information's (AFEI) Excellence in Enterprise

  13. Nuclear electromagnetic charge and current operators in Chiral EFT

    SciTech Connect (OSTI)

    Girlanda, Luca; Marcucci, Laura Elisa; Pastore, Saori; Piarulli, Maria; Schiavilla, Rocco; Viviani, Michele

    2013-08-01

    We describe our method for deriving the nuclear electromagnetic charge and current operators in chiral perturbation theory, based on time-ordered perturbation theory. We then discuss possible strategies for fixing the relevant low-energy constants, from the magnetic moments of the deuteron and of the trinucleons, and from the radiative np capture cross sections, and identify a scheme which, partly relying on {Delta} resonance saturation, leads to a reasonable pattern of convergence of the chiral expansion.

  14. 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.

  15. Nuclear Safety Information Agreement Between the U.S. Nuclear...

    Energy Savers [EERE]

    Regulatory Commission, Office of Nuclear Material Safety and Safeguards, and the U.S. ... and nuclear material operations (DOE does not own or operate power reactors). ...

  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. Integration of Uncertainty Information into Power System Operations

    SciTech Connect (OSTI)

    Makarov, Yuri V.; Lu, Shuai; Samaan, Nader A.; Huang, Zhenyu; Subbarao, Krishnappa; Etingov, Pavel V.; Ma, Jian; Hafen, Ryan P.; Diao, Ruisheng; Lu, Ning

    2011-10-10

    Contemporary power systems face uncertainties coming from multiple sources, including forecast errors of load, wind and solar generation, uninstructed deviation and forced outage of traditional generators, loss of transmission lines, and others. With increasing amounts of wind and solar generation being integrated into the system, these uncertainties have been growing significantly. It is critical important to build knowledge of major sources of uncertainty, learn how to simulate them, and then incorporate this information into the decision-making processes and power system operations, for better reliability and efficiency. This paper gives a comprehensive view on the sources of uncertainty in power systems, important characteristics, available models, and ways of their integration into system operations. It is primarily based on previous works conducted at the Pacific Northwest National Laboratory (PNNL).

  18. Rocketdyne Propulsion and Power DOE Operations annual site environmental report 1997

    SciTech Connect (OSTI)

    Robinson, K.S.

    1998-11-23

    This annual report discusses environmental monitoring at two manufacturing and test sites operated in the Los Angeles area by Rocketdyne Propulsion and Power of Boeing North American, Inc. These are identified as Area 4 of the SSFL and the De Soto site. These sites have been used for research and development (R and D), engineering, and testing in a broad range of technical fields primarily in energy research and nuclear reactor technology. The De Soto site had research and development laboratories involved with nuclear research. This work was terminated in 1995 and only D and D activities will have potential for impact on the environment. Since 1956, Area 4 has been used for work with nuclear materials, including fabricating nuclear reactor fuels, testing nuclear reactors, and dissembling used fuel elements. This work ended in 1988 and subsequent efforts have been directed toward decommissioning and decontamination of the former nuclear facilities. The primary purpose of this report is to present information on environmental and effluent monitoring of DOE-sponsored activities to the regulatory agencies responsible for oversight. Information presented here concentrates on Area 4 at SSFL, which is the only area at SSFL where DOE operations were performed.

  19. Transforming Power Grid Operations via High Performance Computing

    SciTech Connect (OSTI)

    Huang, Zhenyu; Nieplocha, Jarek

    2008-07-31

    Past power grid blackout events revealed the adequacy of grid operations in responding to adverse situations partially due to low computational efficiency in grid operation functions. High performance computing (HPC) provides a promising solution to this problem. HPC applications in power grid computation also become necessary to take advantage of parallel computing platforms as the computer industry is undergoing a significant change from the traditional single-processor environment to an era for multi-processor computing platforms. HPC applications to power grid operations are multi-fold. HPC can improve todays grid operation functions like state estimation and contingency analysis and reduce the solution time from minutes to seconds, comparable to SCADA measurement cycles. HPC also enables the integration of dynamic analysis into real-time grid operations. Dynamic state estimation, look-ahead dynamic simulation and real-time dynamic contingency analysis can be implemented and would be three key dynamic functions in future control centers. HPC applications call for better decision support tools, which also need HPC support to handle large volume of data and large number of cases. Given the complexity of the grid and the sheer number of possible configurations, HPC is considered to be an indispensible element in the next generation control centers.

  20. HEMP emergency planning and operating procedures for electric power systems

    SciTech Connect (OSTI)

    Reddoch, T.W.; Markel, L.C. )

    1991-01-01

    Investigations of the impact of high-altitude electromagnetic pulse (HEMP) on electric power systems and electrical equipment have revealed that HEMP creates both misoperation and failures. These events result from both the early time E[sub 1] (steep-front pulse) component and the late time E[sub 3] (geomagnetic perturbations) component of HEMP. In this report a HEMP event is viewed in terms of its marginal impact over classical power system disturbances by considering the unique properties and consequences of HEMP. This report focuses on system-wide electrical component failures and their potential consequences from HEMP. In particular, the effectiveness of planning and operating procedures for electric systems is evaluated while under the influence of HEMP. This assessment relies on published data and characterizes utilities using the North American Electric Reliability Council's regions and guidelines to model electric power system planning and operations. Key issues addressed by the report include how electric power systems are affected by HEMP and what actions electric utilities can initiate to reduce the consequences of HEMP. The report also reviews the salient features of earlier HEMP studies and projects, examines technology trends in the electric power industry which are affected by HEMP, characterizes the vulnerability of power systems to HEMP, and explores the capability of electric systems to recover from a HEMP event.

  1. Options to reduce the operating costs at fossil power stations

    SciTech Connect (OSTI)

    Mehl, L.; White, T.R.

    1998-12-31

    With the coming of deregulation in the electric power industry, existing power plants will have to evaluate options to reduce their operating costs in methods more commonly used in the industrial sector. Similar to organizations throughout the country, electrical generation companies are looking for ways to reduce their costs. The projected impact of figure deregulation on free enterprise production and trading have further emphasized this need. Historically, the ability to sell or dispatch electrical load based on economic advantages, has existed within local systems. Generating facilities with higher production costs must implement operating cost reductions or expect even lower capacity factors following deregulation. This paper examines various means to reducing operating costs and the methods used in their evaluation.

  2. Office of Emergency Operations | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Office of Emergency Operations

  3. 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.

  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. 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.

  6. What future for nuclear power? Workshop report

    SciTech Connect (OSTI)

    1998-12-31

    A Workshop on this highly controversial subject, organized by the Energy and Environment Programme of the RIIA, was held on 10th November 1997 at Green College, Oxford. The meeting was attended by some forty people from eight countries, coming from the nuclear and electricity generating industry, governments, research organizations, academic institutions, environmental pressure groups and inter-governmental organizations. In addition, subsequent to this Workshop, there have been a number of smaller, more informal discussions on various aspects of the subject. This paper summarizes the main conclusions arising from the Workshop and from these later discussions.

  7. 6,"Edwin I Hatch","Nuclear","Georgia Power Co",1759 7,"Thomas...

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

    Power Co",1793 6,"Edwin I Hatch","Nuclear","Georgia Power Co",1759 7,"Thomas A Smith Energy Facility","Natural gas","Oglethorpe Power Corporation",1290 ...

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

    DOE Patents [OSTI]

    Hampel, Viktor E.

    1989-01-01

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

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

    DOE Patents [OSTI]

    Hampel, V.E.

    1988-05-17

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

  10. 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.

  11. Nuclear Archeology for CANDU Power Reactors

    SciTech Connect (OSTI)

    Broadhead, Bryan L

    2011-01-01

    The goal of this work is the development of so-called 'nuclear archeology' techniques to predict the irradiation history of both fuel-related and non-fuel-related materials irradiated in the CANDU (CANada Deuterium Uranium) family of nuclear reactors. In this application to CANDU-type reactors, two different scenarios for the collection of the appropriate data for use in these procedures will be assumed: the first scenario is the removal of the pressure tubes, calandria tubes, or fuel cladding and destructive analysis of the activation products contained in these structural materials; the second scenario is the nondestructive analysis (NDA) of the same hardware items via high-resolution gamma ray scans. There are obvious advantages and disadvantages for each approach; however, the NDA approach is the central focus of this work because of its simplicity and lack of invasiveness. The use of these techniques along with a previously developed inverse capability is expected to allow for the prediction of average flux levels and irradiation time, and the total fluence for samples where the values of selected isotopes can be measured.

  12. Model-reference adaptive control applied to load-following of a space-nuclear power system

    SciTech Connect (OSTI)

    Metzger, J.D.; El-Genk, M.S.; Parlos, A.G.; New Mexico Univ., Albuquerque, NM . Inst. for Space Nuclear Power Studies; Texas A and M Univ., College Station, TX . Dept. of Nuclear Engineering)

    1989-01-01

    Nuclear power systems are presently being investigated as an alternative for both commercial and military space power systems because of their projected longevity of 7 to 10 years, their mass advantage over other space power sources at powers above approximately 25 kW{sub e}, and their ability to operate without direct illumination from the sun. These space-nuclear power systems are being designed to supply from tens of kilowatts to multimegawatts of power for continuous operation of seven years and more. Space-nuclear power systems designs that meet these requirements will not be available for refueling or maintenance during their lifetime. To ensure that the space-nuclear power system will operate safely and will respond in a predictable and desired manner, the design of the system's controller must account for changes in the system parameters over its lifetime. This paper applies model-reference adaptive control to an increase in the power demand by the load. A model-reference adaptive controller will force the actual space-nuclear power system to follow the predictable and desired response of a reference model, despite changes in the actual system's operating parameters. Included in this paper are the model-reference adaptive control algorithm, the description of the computer simulation of a space-nuclear power system and the reference model, and results that demonstrate the application of model-reference adaptive control to a change in the load power demand. The results demonstrate that model-reference adaptive control can ensure the transient response of the system despite differences between the design of the system and the as-built system as well as for variations in the systems parameters. 5 refs., 3 figs.

  13. 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.

  14. Hans Bethe, Powering the Stars, and Nuclear Physics

    Office of Scientific and Technical Information (OSTI)

    Hans Bethe, Energy Production in Stars, and Nuclear Physics Awards and Tributes * Resources with Additional Information Hans Bethe Courtesy of Cornell University "Hans Bethe was one of the great physicists not only of the twentieth century, but of all time. During his long life, he uncovered the secrets powering the stars, published the standard work on nuclear physics, built atomic weapons, and called for a halt to their proliferation. Bethe's dual legacy is one of genius and

  15. Nuclear Power and the Environment - Energy Explained, Your Guide To

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

    Understanding Energy - Energy Information Administration Nuclear > Nuclear Power & the Environment Energy Explained - Home What Is Energy? Forms of Energy Sources of Energy Laws of Energy Units and Calculators Energy Conversion Calculators British Thermal Units (Btu) Degree-Days U.S. Energy Facts State and U.S. Territory Data Use of Energy In Industry For Transportation In Homes In Commercial Buildings Efficiency and Conservation Energy and the Environment Greenhouse Gases Effect on

  16. Solid state laser media driven by remote nuclear powered fluorescence

    DOE Patents [OSTI]

    Prelas, Mark A.

    1992-01-01

    An apparatus is provided for driving a solid state laser by a nuclear powered fluorescence source which is located remote from the fluorescence source. A nuclear reaction produced in a reaction chamber generates fluorescence or photons. The photons are collected from the chamber into a waveguide, such as a fiber optic waveguide. The waveguide transports the photons to the remote laser for exciting the laser.

  17. 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.

  18. POWER GENERATION FROM LIQUID METAL NUCLEAR FUEL

    DOE Patents [OSTI]

    Dwyer, O.E.

    1958-12-23

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

  19. The History of Nuclear Power in Space | Department of Energy

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

    The History of Nuclear Power in Space The History of Nuclear Power in Space June 9, 2015 - 11:42am Addthis Marissa Newhall Marissa Newhall Director of Digital Strategy and Communications How can I participate? It's Space Week on Energy.gov -- and we're highlighting the contributions of the Energy Department and our National Labs to the U.S. space program. Join us for "The Energy of Star Wars: A Google+ Hangout" on Friday June 12 at 2 p.m. EDT. Ask questions now and during the Hangout

  20. Nuclear Power: High Hopes, Unfulfilled Promise (Conference) | SciTech

    Office of Scientific and Technical Information (OSTI)

    Connect Nuclear Power: High Hopes, Unfulfilled Promise Citation Details In-Document Search Title: Nuclear Power: High Hopes, Unfulfilled Promise Authors: Gupta, Rajan [1] + Show Author Affiliations Los Alamos National Laboratory Publication Date: 2012-03-26 OSTI Identifier: 1053857 Report Number(s): LA-UR-12-20205 DOE Contract Number: AC52-06NA25396 Resource Type: Conference Resource Relation: Conference: EES Colloquium, LANL ; 2012-03-19 - 2012-03-19 ; Los Alamos, New Mexico, United States

  1. Energy Department Announces New Investments in Advanced Nuclear Power

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

    Reactors to Help Meet America's Carbon Emission Reduction Goal | Department of Energy in Advanced Nuclear Power Reactors to Help Meet America's Carbon Emission Reduction Goal Energy Department Announces New Investments in Advanced Nuclear Power Reactors to Help Meet America's Carbon Emission Reduction Goal January 15, 2016 - 9:01am Addthis News Media Contact 202-586-4940 DOENews@hq.doe.gov WASHINGTON - In support of the Administration's goal to produce more carbon-free energy, today the U.S.

  2. Nuclear Power Facilities (2008) | Department of Energy

    Energy Savers [EERE]

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

  3. QUARTERLY NUCLEAR POWER DEPLOYMENT SUMMARY JANUARY 2015

    Energy Savers [EERE]

    5 Updates available at: www.energy.gov/ne NEXT UPDATE - April 2015 Page 1 News Updates  The NRC has scheduled a public Commissioner's hearing for February 4 on DTE Electric's application for a combined license to build and operate a General Electric Hitachi Economic Simplified Boiling Water Reactor (ESBWR) at the Enrico Fermi Generating Station near Newport, Michigan. This is the third time an applicant has reached the "final step" in the part 52 reactor licensing process.  The

  4. Solar power purchase for DOE laboratories | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration Library / Press Releases Solar power purchase for DOE laboratories January 13, 2015 WASHINGTON D.C. -- The U.S. Department of Energy/National Nuclear Security Administration (DOE/NNSA) announced today it has finalized the license agreement with Whitethorn Solar, a wholly owned subsidiary of Juwi Solar Inc. (Juwi), for a solar electrical generation system onsite at Lawrence Livermore National Laboratory. When completed, the power generated by this system will represent the

  5. A survey of fatigue monitoring in the nuclear power industry

    SciTech Connect (OSTI)

    Ware, A.G.

    1991-12-31

    The original design of nuclear power plants addressed fatigue concerns by including calculations of projected fatigue usage for specific components; the calculations were based on estimates of the number and severity of expected transients over the 40-year design life of the plants. In some cases, the transients occurring in the plants are not as severe as was anticipated in the original design analyses, while in other cases events have occurred that were not anticipated in the design basis documents. Field failures caused by fatigue have identified some of those cases. In response, several organizations in the United States and overseas have developed fatigue monitoring programs to more accurately estimate the fatigue usage. One basic approach consists of reconstructing the fatigue usage to date based on the transients recorded in the operating history instead of those projected in the design documents. Another approach includes monitoring the plant instrumentation to determine actual values for parameters such as temperature and pressure and using the measured values in the fatigue usage calculations instead of the values projected in the design documents. The use of existing plant instrumentation to measure temperature, pressure, flow rate, etc., along with the incorporation of conservative assumptions, had generally proven adequate for estimating fatigue usage; however, in some cases additional instrumentation installed for local monitoring can provide a more accurate estimate, especially where thermal stratification is known to occur. Fatigue monitoring can aid in identifying fatigue concerns not anticipated in the original design and for reducing the excessive conservatism in some of the original design calculations so that the fatigue lives of these components can be justified as they age. Fatigue monitoring can also assist efforts to reduce ongoing fatigue usage through design modifications and operating procedure changes.

  6. A survey of fatigue monitoring in the nuclear power industry

    SciTech Connect (OSTI)

    Ware, A.G.

    1991-01-01

    The original design of nuclear power plants addressed fatigue concerns by including calculations of projected fatigue usage for specific components; the calculations were based on estimates of the number and severity of expected transients over the 40-year design life of the plants. In some cases, the transients occurring in the plants are not as severe as was anticipated in the original design analyses, while in other cases events have occurred that were not anticipated in the design basis documents. Field failures caused by fatigue have identified some of those cases. In response, several organizations in the United States and overseas have developed fatigue monitoring programs to more accurately estimate the fatigue usage. One basic approach consists of reconstructing the fatigue usage to date based on the transients recorded in the operating history instead of those projected in the design documents. Another approach includes monitoring the plant instrumentation to determine actual values for parameters such as temperature and pressure and using the measured values in the fatigue usage calculations instead of the values projected in the design documents. The use of existing plant instrumentation to measure temperature, pressure, flow rate, etc., along with the incorporation of conservative assumptions, had generally proven adequate for estimating fatigue usage; however, in some cases additional instrumentation installed for local monitoring can provide a more accurate estimate, especially where thermal stratification is known to occur. Fatigue monitoring can aid in identifying fatigue concerns not anticipated in the original design and for reducing the excessive conservatism in some of the original design calculations so that the fatigue lives of these components can be justified as they age. Fatigue monitoring can also assist efforts to reduce ongoing fatigue usage through design modifications and operating procedure changes.

  7. Cost estimate guidelines for advanced nuclear power technologies

    SciTech Connect (OSTI)

    Delene, J.G.; Hudson, C.R. II.

    1990-03-01

    To make comparative assessments of competing technologies, consistent ground rules must be applied when developing cost estimates. This document provides a uniform set of assumptions, ground rules, and requirements that can be used in developing cost estimates for advanced nuclear power technologies. 10 refs., 8 figs., 32 tabs.

  8. 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.

  9. 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.

  10. Wind Power Forecasting Error Frequency Analyses for Operational Power System Studies: Preprint

    SciTech Connect (OSTI)

    Florita, A.; Hodge, B. M.; Milligan, M.

    2012-08-01

    The examination of wind power forecasting errors is crucial for optimal unit commitment and economic dispatch of power systems with significant wind power penetrations. This scheduling process includes both renewable and nonrenewable generators, and the incorporation of wind power forecasts will become increasingly important as wind fleets constitute a larger portion of generation portfolios. This research considers the Western Wind and Solar Integration Study database of wind power forecasts and numerical actualizations. This database comprises more than 30,000 locations spread over the western United States, with a total wind power capacity of 960 GW. Error analyses for individual sites and for specific balancing areas are performed using the database, quantifying the fit to theoretical distributions through goodness-of-fit metrics. Insights into wind-power forecasting error distributions are established for various levels of temporal and spatial resolution, contrasts made among the frequency distribution alternatives, and recommendations put forth for harnessing the results. Empirical data are used to produce more realistic site-level forecasts than previously employed, such that higher resolution operational studies are possible. This research feeds into a larger work of renewable integration through the links wind power forecasting has with various operational issues, such as stochastic unit commitment and flexible reserve level determination.

  11. UPDATE: nuclear power program information and data, July-September 1981

    SciTech Connect (OSTI)

    DOE /NBM--6011986

    1981-01-01

    UPDATE is published by the Office of Coordination and Special Projects, Office of Nuclear Reactor Programs, to provide a quick reference source on the current status of nuclear powerplant construction and operation in the United States and for information on the fuel cycle, economics, and performance of nuclear generating units. Similar information on other means of electric generation as related to nuclear power is included when appropriate. The subject matter of the reports and analyses presented in UPDATE will vary from issue to issue, reflecting changes in foci of interest and new developments in the field of commercial nuclear power generation. UPDATA is intended to provide a timely source of current statistics, results of analyses, and programmatic information proceeding from the activities of the Office of Nuclear Reactor Programs and other components of the Department of Energy, as well as condensations of topical articles from other sources of interest to the nuclear community. It also facilitates quick responses to requests for data and information of the type often solicited from this office.

  12. Multimegawatt space nuclear power supply, Phase 1 Final report

    SciTech Connect (OSTI)

    Not Available

    1989-02-17

    This Specification establishes the performance, design, development, and test requirements for the Boeing Multimegawatt Space Nuclear Power System (MSNPS). The Boeing Multimegawatt Space Power System is part of the DOE/SDIO Multimegawatt Space Nuclear Power Program. The purpose of this program is to provide a space-based nuclear power system to meet the needs of SDIO missions. The Boeing MSNPS is a category 1 concept which is capable of delivering 10's of MW(e) for 100's of seconds with effluent permitted. A design goal is for the system to have growth or downscale capability for other power system concepts. The growth objective is to meet the category 3 capability of 100's of MW(e) for 100's of seconds, also with effluent permitted. The purpose of this preliminary document is to guide the conceptual design effort throughout the Phase 1 study effort. This document will be updated through out the study. It will thus result in a record of the development of the design effort.

  13. Top 6 Things You Didn't Know About Nuclear Power | Department...

    Energy Savers [EERE]

    Nuclear Power December 12, 2014 - 10:39am Addthis These are the first lightbulbs lit by nuclear fission at Argonne's EBR or Experimental Breeder Reactor.| Energy Department...

  14. 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.

  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. 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.

  17. 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.

  18. Rocketdyne Propulsion and Power DOE operations annual site environmental report 1996

    SciTech Connect (OSTI)

    Tuttle, R.J.

    1997-11-10

    Rocketdyne currently operates several facilities in the San Fernando Valley/Simi Valley area, for manufacturing, testing, and research and development (R and D). These operations include manufacturing liquid-fueled rocket engines, such as the Space Shuttle Main Engine (SSME) and engines used for expendable launch vehicles used to place artificial satellites into orbit. This work includes fabrication and testing of rocket engines, lasers, and heat-transfer systems; and R and D in a wide range of high-technology fields, such as the electrical power system for the Space Station. Previously, this work also included development, fabrication, and disassembly of nuclear reactors, reactor fuel, and other radioactive materials, under the Atomics International Division (AI). AI was merged into Rocketdyne in 1984 and many of the AI functions were transferred to existing Rocketdyne departments. This nuclear work was terminated in 1988, and subsequently, all radiological work has been directed toward decontamination and decommissioning (D and D) of the previously used nuclear facilities and associated site areas. The majority of this work is done for the Department of Energy (DOE). This Annual Site Environmental Report for 1996 concentrates on the environmental conditions related to DOE operations at Area IV of SSFL and at De Soto.

  19. 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)

  20. Feasibility Study of a Nuclear-Stirling Power Plant for the Jupiter Icy Moons Orbiter

    SciTech Connect (OSTI)

    Schmitz, Paul C.; Schreiber, Jeffrey G.; Penswick, L. Barry

    2005-02-06

    NASA is undertaking the design of a new spacecraft to explore the planet Jupiter and its three moons Calisto, Ganymede and Europa. This proposed mission, known as Jupiter Icy Moons Orbiter (JIMO) would use a nuclear reactor and an associated electrical generation system (Reactor Power Plant - RPP) to provide power to the spacecraft. The JIMO spacecraft is envisioned to use this power for science and communications as well as Electric Propulsion (EP). Among other potential power-generating concepts, previous studies have considered Thermoelectric and Brayton power conversion systems, coupled to a liquid metal reactor for the JIMO mission. This paper will explore trades in system mass and radiator area for a nuclear reactor power conversion system, however this study will focus on Stirling power conversion. Stirling convertors have a long heritage operating in both power generation and the cooler industry, and are currently in use in a wide variety of applications. The Stirling convertor modeled in this study is based upon the Component Test Power Convertor design that was designed and operated successfully under the Civil Space Technology Initiative for use with the SP-100 nuclear reactor in the 1980's and early 1990's. The baseline RPP considered in this study consists of four dual-opposed Stirling convertors connected to the reactor by a liquid lithium loop. The study design is such that two of the four convertors would operate at any time to generate the 100 kWe while the others are held in reserve. For this study the Stirling convertors hot-side temperature is 1050 K, would operate at a temperature ratio of 2.4 for a minimum mass system and would have a system efficiency of 29%. The Stirling convertor would generate high voltage (400 volt), 100 Hz single phase AC that is supplied to the Power Management and Distribution system. The waste heat is removed from the Stirling convertors by a flowing liquid sodium-potassium eutectic and then rejected by a shared radiator. The radiator consists of two coplanar wings, which would be deployed after the reactor is in space. For this study design, the radiators would be located behind the conical radiation shield of the reactor and fan out as the radiator's distance from the reactor increases. System trades were performed to vary cycle state point temperatures and convertor design as well as power output. Other redundancy combinations were considered to understand the affects of convertor size and number of spares to the system mass.

  1. 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 include a process model and a N2H2 economic assessment model (both developed by the Idaho National Laboratory). Both models are described in this report. The N2H2 model closely tracked and provided similar results as the H2A model and was instrumental in assessing the effects of plant availability on price when operated in the shoulder mode for electrical pricing. Differences between the H2A and N2H2 model are included in this report.

  2. HEMP emergency planning and operating procedures for electric power systems. Power Systems Technology Program

    SciTech Connect (OSTI)

    Reddoch, T.W.; Markel, L.C.

    1991-12-31

    Investigations of the impact of high-altitude electromagnetic pulse (HEMP) on electric power systems and electrical equipment have revealed that HEMP creates both misoperation and failures. These events result from both the early time E{sub 1} (steep-front pulse) component and the late time E{sub 3} (geomagnetic perturbations) component of HEMP. In this report a HEMP event is viewed in terms of its marginal impact over classical power system disturbances by considering the unique properties and consequences of HEMP. This report focuses on system-wide electrical component failures and their potential consequences from HEMP. In particular, the effectiveness of planning and operating procedures for electric systems is evaluated while under the influence of HEMP. This assessment relies on published data and characterizes utilities using the North American Electric Reliability Council`s regions and guidelines to model electric power system planning and operations. Key issues addressed by the report include how electric power systems are affected by HEMP and what actions electric utilities can initiate to reduce the consequences of HEMP. The report also reviews the salient features of earlier HEMP studies and projects, examines technology trends in the electric power industry which are affected by HEMP, characterizes the vulnerability of power systems to HEMP, and explores the capability of electric systems to recover from a HEMP event.

  3. 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.

  4. 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.

  5. Load rejection operation in conventional power plants in ENEL - Italy

    SciTech Connect (OSTI)

    Gadda, E. ); Radice, A. )

    1989-09-01

    The capability of maintaining auxiliary load after a main breaker trip following an emergency in the electric power system is of major concern for any thermoelectric generating unit. In ENEL the reliability of run back to house load of fossil fired units has been greatly improved by adopting a new procedure. Instead of that originally recommended the new procedure allows to trip all fuel input to the boiler and maintains house load operating the turbine on mass and energy stored in the boiler. This procedure was qualified a few years ago and since then is used in the 320 MW units in operation (the main bulk of ENEL's thermal capacity) whether equipped with subcritical once through boilers or with assisted circulation drum boilers. A series of test carried out recently on supercritical 660 MW units have shown that adopting the same procedure these larger units can sustain successfully the run back to house load too. Up to now the new procedure has been used in many other thermal units of size ranging between 70 MW to 240 MW and can be performed in most of ENEL's thermal power plants.

  6. 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...

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

    SciTech Connect (OSTI)

    Not Available

    1988-06-01

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

  8. Improving the reliability of Class 1E power distribution to instrumentation and control cabinets on nuclear power plants in the USA. Final report

    SciTech Connect (OSTI)

    Brennen, M.B.

    1995-09-01

    This study was conducted to explore nontraditional electric power distribution concepts to improve the reliability of uninterruptible power to vital Instrumentation and Control (I and C) cabinets in future US nuclear power plants. The study incorporated comparative technical and economic evaluations of existing and nontraditional uninterruptible power supply (UPS) concepts. All nontraditional distribution concepts were based on available or already emerging components or semiconductor devices. Another purpose of the study was to reduce the cost and complexity of present power distribution and to lower maintenance, replacement, degradation and fault location requirements. The possible reduction of distribution losses, especially during operation under battery power, was also evaluated. The study indicates that direct current distribution at 48 or 125 Vdc levels would have more than an order of magnitude improvement over the reliability of present alternating current supplies at comparable cost. Furthermore, losses under battery power could be reduced significantly with respect to present distribution losses. An inherent advantage of DC distribution is that power transfer from the failed power bus to an operational bus occurs naturally and instantaneously via two simple and reliable semiconductor diodes. AC distribution, on the other hand, requires complex synchronization, decision making and gated semiconductor switching devices for power bus transfer all of which could be eliminated. Some of the concepts presented may also be applied to make existing vital (Class 1E) uninterruptible power supplies in US nuclear plants more reliable.

  9. 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...

  10. Los Alamos turns its nuclear weapons power to war on cancer

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

    Los Alamos turns its nuclear weapons power to war on cancer Los Alamos turns its nuclear weapons power to war on cancer Los Alamos Physicist Eva Birnbaum shows how the laboratory ...

  11. Cooling Water Issues and Opportunities at U.S. Nuclear Power...

    Energy Savers [EERE]

    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 ...

  12. Department of Energy to Co-Sponsor Workshop on Nuclear Power...

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

    Co-Sponsor Workshop on Nuclear Power Plant Life Extension R&D Department of Energy to Co-Sponsor Workshop on Nuclear Power Plant Life Extension R&D September 29, 2010 - 11:38am ...

  13. TTF3 POWER COUPLER THERMAL ANALYSIS FOR LCLS-II CW OPERATION...

    Office of Scientific and Technical Information (OSTI)

    TTF3 POWER COUPLER THERMAL ANALYSIS FOR LCLS-II CW OPERATION Citation Details In-Document Search Title: TTF3 POWER COUPLER THERMAL ANALYSIS FOR LCLS-II CW OPERATION Authors: Xiao,...

  14. 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.

  15. 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.

  16. 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.

  17. 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.

  18. NA 40 - Associate Administrator for Emergency Operations | National Nuclear

    National Nuclear Security Administration (NNSA)

    Security Administration 40 - Associate Administrator for Emergency Operations

  19. Reducing power consumption while performing collective operations on a plurality of compute nodes

    DOE Patents [OSTI]

    Archer, Charles J.; Blocksome, Michael A.; Peters, Amanda E.; Ratterman, Joseph D.; Smith, Brian E.

    2011-10-18

    Methods, apparatus, and products are disclosed for reducing power consumption while performing collective operations on a plurality of compute nodes that include: receiving, by each compute node, instructions to perform a type of collective operation; selecting, by each compute node from a plurality of collective operations for the collective operation type, a particular collective operation in dependence upon power consumption characteristics for each of the plurality of collective operations; and executing, by each compute node, the selected collective operation.

  20. DOE Selects Savannah River Nuclear Solutions, LLC to Manage and Operate its

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

    Savannah River Site | Department of Energy Nuclear Solutions, LLC to Manage and Operate its Savannah River Site DOE Selects Savannah River Nuclear Solutions, LLC to Manage and Operate its Savannah River Site January 10, 2007 - 10:24am Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced that Savannah River Nuclear Solutions (SRNS), LLC has been selected as the management and operating contractor for DOE's Savannah River Site (SRS) in Aiken, South Carolina. The

  1. 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.

  2. 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.

  3. 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.

  4. A Nuclear Renaissance: The Role of Nuclear Power in Mitigating Climate Change

    SciTech Connect (OSTI)

    Winslow, Anne

    2011-06-28

    The U. N. Framework Convention on Climate Change calls for the stabilization of greenhouse gas (GHG) emissions at double the preindustrial atmospheric carbon dioxide concentration to avoid dangerous anthropogenic interference with the climate system. To achieve this goal, carbon emissions in 2050 must not exceed their current level, despite predictions of a dramatic increase in global electricity demand. The need to reduce GHG emissions and simultaneously provide for additional electricity demand has led to a renewed interest in the expansion of alternatives to fossil fuels--particularly renewable energy and nuclear power. As renewable energy sources are often constrained by the intermittency of natural energy forms, scale-ability concerns, cost and environmental barriers, many governments and even prominent environmentalist turn to nuclear energy as a source of clean, reliable base-load electricity. Described by some as a ''nuclear renaissance'', this trend of embracing nuclear power as a tool to mitigate climate change will dramatically influence the feasibility of emerging nuclear programs around the world.

  5. Aging Management Guideline for commercial nuclear power plants: Battery chargers, inverters and uninterruptible power supplies. Final report

    SciTech Connect (OSTI)

    Berg, R.; Stroinski, M.; Giachetti, R.

    1994-02-01

    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 battery chargers, inverters and uninterruptible power supplies 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.

  6. Pyroelectric Energy Scavenging Techniques for Self-Powered Nuclear Reactor Wireless Sensor Networks

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

    Hunter, Scott Robert; Lavrik, Nickolay V; Datskos, Panos G; Clayton, Dwight A

    2014-11-01

    Recent advances in technologies for harvesting waste thermal energy from ambient environments present an opportunity to implement truly wireless sensor nodes in nuclear power plants. These sensors could continue to operate during extended station blackouts and during periods when operation of the plant s internal power distribution system has been disrupted. The energy required to power the wireless sensors must be generated using energy harvesting techniques from locally available energy sources, and the energy consumption within the sensor circuitry must therefore be low to minimize power and hence the size requirements of the energy harvester. Harvesting electrical energy from thermalmore » energy sources can be achieved using pyroelectric or thermoelectric conversion techniques. Recent modeling and experimental studies have shown that pyroelectric techniques can be cost competitive with thermoelectrics in self powered wireless sensor applications and, using new temperature cycling techniques, has the potential to be several times as efficient as thermoelectrics under comparable operating conditions. The development of a new thermal energy harvester concept, based on temperature cycled pyroelectric thermal-to-electrical energy conversion, is outlined. This paper outlines the modeling of cantilever and pyroelectric structures and single element devices that demonstrate the potential of this technology for the development of high efficiency thermal-to-electrical energy conversion devices.« less

  7. Pyroelectric Energy Scavenging Techniques for Self-Powered Nuclear Reactor Wireless Sensor Networks

    SciTech Connect (OSTI)

    Hunter, Scott Robert; Lavrik, Nickolay V; Datskos, Panos G; Clayton, Dwight A

    2014-01-01

    Recent advances in technologies for harvesting waste thermal energy from ambient environments present an opportunity to implement truly wireless sensor nodes in nuclear power plants. These sensors could continue to operate during extended station blackouts and during periods when operation of the plant s internal power distribution system has been disrupted. The energy required to power the wireless sensors must be generated using energy harvesting techniques from locally available energy sources, and the energy consumption within the sensor circuitry must therefore be low to minimize power and hence the size requirements of the energy harvester. Harvesting electrical energy from thermal energy sources can be achieved using pyroelectric or thermoelectric conversion techniques. Recent modeling and experimental studies have shown that pyroelectric techniques can be cost competitive with thermoelectrics in self powered wireless sensor applications and, using new temperature cycling techniques, has the potential to be several times as efficient as thermoelectrics under comparable operating conditions. The development of a new thermal energy harvester concept, based on temperature cycled pyroelectric thermal-to-electrical energy conversion, is outlined. This paper outlines the modeling of cantilever and pyroelectric structures and single element devices that demonstrate the potential of this technology for the development of high efficiency thermal-to-electrical energy conversion devices.

  8. Nuclear power fleets and uranium resources recovered from phosphates

    SciTech Connect (OSTI)

    Gabriel, S.; Baschwitz, A.; Mathonniere, G.

    2013-07-01

    Current light water reactors (LWR) burn fissile uranium, whereas some future reactors, as Sodium fast reactors (SFR) will be capable of recycling their own plutonium and already-extracted depleted uranium. This makes them a feasible solution for the sustainable development of nuclear energy. Nonetheless, a sufficient quantity of plutonium is needed to start up an SFR, with the plutonium already being produced in light water reactors. The availability of natural uranium therefore has a direct impact on the capacity of the reactors (both LWR and SFR) that we can build. It is therefore important to have an accurate estimate of the available uranium resources in order to plan for the world's future nuclear reactor fleet. This paper discusses the correspondence between the resources (uranium and plutonium) and the nuclear power demand. Sodium fast reactors will be built in line with the availability of plutonium, including fast breeders when necessary. Different assumptions on the global uranium resources are taken into consideration. The largely quoted estimate of 22 Mt of uranium recovered for phosphate rocks can be seriously downscaled. Based on our current knowledge of phosphate resources, 4 Mt of recoverable uranium already seems to be an upper bound value. The impact of the downscaled estimate on the deployment of a nuclear fleet is assessed accordingly. (authors)

  9. Establishing a value chain for human factors in nuclear power plantcontrol room modernization

    SciTech Connect (OSTI)

    Joe, Jeffrey Clark; Thomas, Kenneth David; Boring, Ronald Laurids

    2015-07-01

    Commercial nuclear power plants in the United States (U.S.) have operated reliably and efficiently for decades. With the life extensions of plants now being planned for operation beyond their original operating licenses, there are opportunities to achieve even greater efficiencies, while maintaining high operational reliabilities, with strategic, risk- and economically-informed, upgrades to plant systems and infrastructure. The U.S. Department of Energy’s Light Water Reactor Sustainability (LWRS) program supports the commercial nuclear industry’s modernization efforts through research and development (R&D) activities across many areas to help establish the technical and economic bases for modernization activities. The Advanced Instrumentation, Information, and Control Systems Technologies pathway is one R&D focus area for the LWRS program, and has researchers at Idaho National Laboratory working with select utility partners to use human factors and instrumentation and controls R&D to help modernize the plant’s main control room. However, some in the nuclear industry have not been as enthusiastic about using human factors R&D to inform life extension decision making. Part of the reason for this may stem from uncertainty decision-makers have regarding how human factors fits into the value chain for nuclear power plant control room modernization. This paper reviews past work that has attempted to demonstrate the value of human factors, and then describes the value chain concept, how it applies to control room modernization, and then makes a case for how and why human factors is an essential link in the modernization value chain.

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

    SciTech Connect (OSTI)

    Harty, H.; Dowis, W.J.

    1983-06-01

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

  11. Refractory alloy technology for space nuclear power applications

    SciTech Connect (OSTI)

    Cooper, R.H. Jr.; Hoffman, E.E.

    1984-01-01

    Purpose of this symposium is twofold: (1) to review and document the status of refractory alloy technology for structural and fuel-cladding applications in space nuclear power systems, and (2) to identify and document the refractory alloy research and development needs for the SP-100 Program in both the short and the long term. In this symposium, an effort was made to recapture the space reactor refractory alloy technology that was cut off in midstream around 1973 when the national space nuclear reactor program began in the early 1960s, was terminated. The six technical areas covered in the program are compatibility, processing and production, welding and component fabrication, mechanical and physical properties, effects of irradiation, and machinability. The refractory alloys considered are niobium, molybdenum, tantalum, and tungsten. Thirteen of the 14 pages have been abstracted separately. The remaining paper summarizes key needs for further R and D on refractory alloys. (DLC)

  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. Surveys of organizational culture and safety culture in nuclear power

    SciTech Connect (OSTI)

    Brown, Walter S.

    2000-07-30

    The results of a survey of organizational culture at a nuclear power plant are summarized and compared with those of a similar survey which has been described in the literature on ''high-reliability organizations''. A general-purpose cultural inventory showed a profile of organizational style similar to that reported in the literature; the factor structure for the styles was also similar to that of the plant previously described. A specialized scale designed to measure ''safety culture'' did not distinguished among groups within the organization that would be expected to differ.

  15. Wind Power Impacts on Electric Power System Operating Costs: Summary and Perspective on Work to Date; Preprint

    SciTech Connect (OSTI)

    Smith, J. C.; DeMeo, E. A.; Parsons, B.; Milligan, M.

    2004-03-01

    Electric utility system planners and operators are concerned that variations in wind plant output may increase the operating costs of the system. This concern arises because the system must maintain an instantaneous balance between the aggregate demand for electric power and the total power generated by all power plants feeding the system. This is a highly sophisticated task that utility operators and automatic controls perform routinely, based on well-known operating characteristics for conventional power plants and a great deal of experience accumulated over many years. System operators are concerned that variations in wind plant output will force the conventional power plants to provide compensating variations to maintain system balance, thus causing the conventional power plants to deviate from operating points chosen to minimize the total cost of operating the system. The operators' concerns are compounded by the fact that conventional power plants are generally under their control and thus are dispatchable, whereas wind plants are controlled instead by nature. Although these are valid concerns, the key issue is not whether a system with a significant amount of wind capacity can be operated reliably, but rather to what extent the system operating costs are increased by the variability of the wind.

  16. FORM EIA-923 POWER PLANT OPERATIONS REPORT INSTRUCTIONS

    Gasoline and Diesel Fuel Update (EIA)

    by-products, operational cooling water data, and operational data for NOx, SO2, ...cooling, steam for purchase or hot water) from a common source. 7. CHP Plant ...

  17. Microsoft PowerPoint - Nuclear Material Import Export License...

    National Nuclear Security Administration (NNSA)

    ... - Specific license specifies: * Quantity of nuclear material that may exported * Chemicalphysical form of nuclear material * Intermediate nuclear facilities that material may ...

  18. 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.

  19. Regulatory process for decommissioning nuclear power reactors. Final report

    SciTech Connect (OSTI)

    1998-03-01

    This report provides regulatory guidance for utilities consistent with the changes in the decommissioning rule, 10 CFR50.82 as revised in July 1996. The purpose of this report is to explain the new rule in the context of related industry experience and to provide practical guidance to licensees contemplating or implementing a shutdown. Because the regulatory process is still rapidly evolving, this report reflects only a current status of the acceptable methods and practices derived from a review of the current regulations, guidance documents and industry experience for decommissioning a nuclear power reactor. EPRI anticipates periodic updates of this document to incorporate various utility experiences with decommissioning, and also to reflect any regulatory changes. The report provides a summary of ongoing federal agency and industry activities and the regulatory requirements that are currently applicable, or no longer applicable, to nuclear power plants at the time of permanent shutdown through the early decommissioning stage. The report describes the major components of a typical decommissioning action plan, providing industry experience and guidance for licensees considering or implementing permanent shutdown.

  20. Optimization and Comparison of Direct and Indirect Supercritical Carbon Dioxide Power Plant Cycles for Nuclear Applications

    SciTech Connect (OSTI)

    Edwin A. Harvego; Michael G. McKellar

    2011-11-01

    There have been a number of studies involving the use of gases operating in the supercritical mode for power production and process heat applications. Supercritical carbon dioxide (CO2) is particularly attractive because it is capable of achieving relatively high power conversion cycle efficiencies in the temperature range between 550 C and 750 C. Therefore, it has the potential for use with any type of high-temperature nuclear reactor concept, assuming reactor core outlet temperatures of at least 550 C. The particular power cycle investigated in this paper is a supercritical CO2 Recompression Brayton Cycle. The CO2 Recompression Brayton Cycle can be used as either a direct or indirect power conversion cycle, depending on the reactor type and reactor outlet temperature. The advantage of this cycle when compared to the helium Brayton cycle is the lower required operating temperature; 550 C versus 850 C. However, the supercritical CO2 Recompression Brayton Cycle requires an operating pressure in the range of 20 MPa, which is considerably higher than the required helium Brayton cycle operating pressure of 8 MPa. This paper presents results of analyses performed using the UniSim process analyses software to evaluate the performance of both a direct and indirect supercritical CO2 Brayton Recompression cycle for different reactor outlet temperatures. The direct supercritical CO2 cycle transferred heat directly from a 600 MWt reactor to the supercritical CO2 working fluid supplied to the turbine generator at approximately 20 MPa. The indirect supercritical CO2 cycle assumed a helium-cooled Very High Temperature Reactor (VHTR), operating at a primary system pressure of approximately 7.0 MPa, delivered heat through an intermediate heat exchanger to the secondary indirect supercritical CO2 Brayton Recompression cycle, again operating at a pressure of about 20 MPa. For both the direct and indirect cycles, sensitivity calculations were performed for reactor outlet temperature between 550 C and 850 C. The UniSim models used realistic component parameters and operating conditions to model the complete reactor and power conversion systems. CO2 properties were evaluated, and the operating ranges of the cycles were adjusted to take advantage of the rapidly changing properties of CO2 near the critical point. The results of the analyses showed that, for the direct supercritical CO2 power cycle, thermal efficiencies in the range of 40 to 50% can be achieved. For the indirect supercritical CO2 power cycle, thermal efficiencies were approximately 10% lower than those obtained for the direct cycle over the same reactor outlet temperature range.

  1. 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, supplemented by other LLNL scientists, invested over 5000 person-hours of time and generated over 300 analyses and predictions.

  2. NUCLEAR POWERED CO2 CAPTURE FROM THE ATMOSPHERE

    SciTech Connect (OSTI)

    Sherman, S

    2008-09-22

    A process for capturing CO{sub 2} from the atmosphere was recently proposed. This process uses a closed cycle of sodium and calcium hydroxide, carbonate, and oxide transformations to capture dilute CO{sub 2} from the atmosphere and to generate a concentrated stream of CO{sub 2} that is amenable to sequestration or subsequent chemical transformations. In one of the process steps, a fossil-fueled lime kiln is needed, which reduces the net CO{sub 2} capture of the process. It is proposed to replace the fossil-fueled lime kiln with a modified kiln heated by a high-temperature nuclear reactor. This will have the effect of eliminating the use of fossil fuels for the process and increasing the net CO{sub 2} capture. Although the process is suitable to support sequestration, the use of a nuclear power source for the process provides additional capabilities, and the captured CO{sub 2} may be combined with nuclear-produced hydrogen to produce liquid fuels via Fischer-Tropsch synthesis or other technologies. Conceivably, such plants would be carbon-neutral, and could be placed virtually anywhere without being tied to fossil fuel sources or geological sequestration sites.

  3. 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.

  4. A 48-month extended fuel cycle for the B and W mPower{sup TM} small modular nuclear reactor

    SciTech Connect (OSTI)

    Erighin, M. A. [Babcock and Wilcox Company, 109 Ramsey Place, Lynchburg, VA 24502 (United States)

    2012-07-01

    The B and W mPower{sup TM} reactor is a small, rail-shippable pressurized water reactor (PWR) with an integral once-through steam generator and an electric power output of 150 MW, which is intended to replace aging fossil power plants of similar output. The core is composed of 69 reduced-height, but otherwise standard, PWR assemblies with the familiar 17 x 17 fuel rod array on a 21.5 cm inter-assembly pitch. The B and W mPower core design and cycle management plan, which were performed using the Studsvik core design code suite, follow the pattern of a typical nuclear reactor fuel cycle design and analysis performed by most nuclear fuel management organizations, such as fuel vendors and utilities. However, B and W is offering a core loading and cycle management plan for four years of continuous power operations without refueling and without the hurdles of chemical shim. (authors)

  5. Microsoft PowerPoint - Arkansa River System Operation.ppt

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

    Serving The Army and the Nation Tulsa District Tulsa District Tulsa District Arkansas River System Arkansas River System Operation Operation One Corps Serving The Army and the Nation Tulsa District Overview Overview * * Tulsa District Tulsa District * * Authorized Purposes Authorized Purposes * * Types of projects and storage zones Types of projects and storage zones * * Flood damage risk reduction operation. Flood damage risk reduction operation. * * Arkansas River System Operation Arkansas

  6. The Use of Thorium within the Nuclear Power Industry - 13472

    SciTech Connect (OSTI)

    Miller, Keith

    2013-07-01

    Thorium is 3 to 4 times more abundant than uranium and is widely distributed in nature as an easily exploitable resource in many countries. Unlike natural uranium, which contains ∼0.7% fissile {sup 235}U isotope, natural thorium does not contain any fissile material and is made up of the fertile {sup 232}Th isotope only. Therefore thorium and thorium-based fuel as metal, oxide or carbide, has been utilized in combination with fissile {sup 235}U or {sup 239}Pu in nuclear research and power reactors for conversion to fissile {sup 233}U, thereby enlarging fissile material resources. During the pioneering years of nuclear energy, from the mid 1950's to mid 1970's, there was considerable interest worldwide to develop thorium fuels and fuel cycles in order to supplement uranium reserves. Thorium fuels and fuel cycles are particularly relevant to countries having large thorium deposits but very limited uranium reserves for their long term nuclear power programme. The feasibility of thorium utilization in high temperature gas cooled reactors (HTGR), light water reactors (LWR), pressurized heavy water reactors (PHWRs), liquid metal cooled fast breeder reactors (LMFBR) and molten salt breeder reactors (MSBR) were demonstrated. The initial enthusiasm for thorium fuels and fuel cycles was not sustained among the developing countries later, due to new discovery of uranium deposits and their improved availability. However, in recent times, the need for proliferation-resistance, longer fuel cycles, higher burnup, and improved waste form characteristics, reduction of plutonium inventories and in situ use of bred-in fissile material has led to renewed interest in thorium-based fuels and fuel cycles. (authors)

  7. 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.

  8. Development and validation of instantaneous risk model in nuclear power plant's risk monitor

    SciTech Connect (OSTI)

    Wang, J.; Li, Y.; Wang, F.; Wang, J.; Hu, L.

    2012-07-01

    The instantaneous risk model is the fundament of calculation and analysis in a risk monitor. This study focused on the development and validation of an instantaneous risk model. Therefore the principles converting from the baseline risk model to the instantaneous risk model were studied and separated trains' failure modes modeling method was developed. The development and validation process in an operating nuclear power plant's risk monitor were also introduced. Correctness of instantaneous risk model and rationality of converting method were demonstrated by comparison with the result of baseline risk model. (authors)

  9. FRAMEWORK AND APPLICATION FOR MODELING CONTROL ROOM CREW PERFORMANCE AT NUCLEAR POWER PLANTS

    SciTech Connect (OSTI)

    Ronald L Boring; David I Gertman; Tuan Q Tran; Brian F Gore

    2008-09-01

    This paper summarizes an emerging project regarding the utilization of high-fidelity MIDAS simulations for visualizing and modeling control room crew performance at nuclear power plants. The key envisioned uses for MIDAS-based control room simulations are: (i) the estimation of human error associated with advanced control room equipment and configurations, (ii) the investigative determination of contributory cognitive factors for risk significant scenarios involving control room operating crews, and (iii) the certification of reduced staffing levels in advanced control rooms. It is proposed that MIDAS serves as a key component for the effective modeling of cognition, elements of situation awareness, and risk associated with human performance in next generation control rooms.

  10. 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.

  11. Facility Operations and User Support | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    continuing product support, software license and maintenance fees, procurement of operational equipment and media, quality and reliability activities, and collaborations. ...

  12. Facility Operations and User Support | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration Facility Operations and User Support This sub-program provides both necessary physical facility and operational support for reliable, cross-lab production computing and storage environments as well as a suite of user services for effective use of ASC tri-lab computing resources. The scope of the facility operations includes planning, integration and deployment, continuing product support, software license and maintenance fees, procurement of operational equipment and media,

  13. 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.

  14. Nuclear power and the allocation of emissions allowances: a new hampshire case study

    SciTech Connect (OSTI)

    Space, William

    2007-04-15

    The Regional Greenhouse Gas Initiative's model rule allows states to allocate carbon allowances to nuclear power plants. New Hampshire's 2003 decision to include nuclear uprates in its NO{sub x} allocations represents a relevant precedent. (author)

  15. Selected financial and operating ratios of public power systems

    SciTech Connect (OSTI)

    Choate, S.

    1996-01-01

    This article is a review of the title publication, which is produced by the American Public Power Association. The report is considered to be a valuable management tool to public power systems in evaluating their competitive positions in the dynamic electric utility industry. It examines 22 categories of ratio indicators that can be used by public power systems to assess their performance relative to other utilities of comparable size in the same geographic region. More than 400 utilities are summarized in the report.

  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. 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)

  18. Los Alamos turns its nuclear weapons power to war on cancer

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

    Los Alamos turns its nuclear weapons power to war on cancer Los Alamos turns its nuclear weapons power to war on cancer Los Alamos Physicist Eva Birnbaum shows how the laboratory is manufacturing a radioactive treatment that targets tumors, without killing the surrounding healthy tissue. December 20, 2015 LANL physicist Eva Birnbaum LANL physicist Eva Birnbaum Los Alamos turns its nuclear weapons power to war on cancer NBC News got exclusive access to Los Alamos National Laboratory where

  19. 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.

  20. DHS/National Operations Center | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    DHS/National Operations Center The Department of Energy (DOE)/ Department of Homeland Security (DHS) Watch Office Desk in DHS's National Operations Center (NOC) represents DOE/NNSA within the NOC. In conjunction with over 80 federal, state, and local government agencies, the DOE/DHS Operations Center Watch Officer(s) collect, analyze and facilitate the exchange of vital information between DHS and DOE supporting the DHS mission of preventing and/or responding to acts of terrorism in the United

  1. 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.

  2. Water Use in the Development and Operations of Geothermal Power Plants |

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

    Department of Energy Operations of Geothermal Power Plants Water Use in the Development and Operations of Geothermal Power Plants This report summarizes what is currently known about the life cycle water requirements of geothermal electric power-generating systems and the water quality of geothermal waters. It is part of a larger effort to compare the life cycle impacts of large-scale geothermal electricity generation with other power generation technologies. PDF icon

  3. Water Use in the Development and Operations of Geothermal Power Plants |

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

    Department of Energy Water Use in the Development and Operations of Geothermal Power Plants Water Use in the Development and Operations of Geothermal Power Plants This report summarizes what is currently known about the life cycle water requirements of geothermal electric power-generating systems and the water quality of geothermal waters. It is part of a larger effort to compare the life cycle impacts of large-scale geothermal electricity generation with other power generation technologies.

  4. Impact of Improved Solar Forecasts on Bulk Power System Operations in ISO-NE: Preprint

    SciTech Connect (OSTI)

    Brancucci Martinez-Anido, C.; Florita, A.; Hodge, B. M.

    2014-09-01

    The diurnal nature of solar power is made uncertain by variable cloud cover and the influence of atmospheric conditions on irradiance scattering processes. Its forecasting has become increasingly important to the unit commitment and dispatch process for efficient scheduling of generators in power system operations. This study examines the value of improved solar power forecasting for the Independent System Operator-New England system. The results show how 25% solar power penetration reduces net electricity generation costs by 22.9%.

  5. Method and apparatus for optimizing operation of a power generating plant using artificial intelligence techniques

    DOE Patents [OSTI]

    Wroblewski, David; Katrompas, Alexander M.; Parikh, Neel J.

    2009-09-01

    A method and apparatus for optimizing the operation of a power generating plant using artificial intelligence techniques. One or more decisions D are determined for at least one consecutive time increment, where at least one of the decisions D is associated with a discrete variable for the operation of a power plant device in the power generating plant. In an illustrated embodiment, the power plant device is a soot cleaning device associated with a boiler.

  6. "Is There a Future for Nuclear Power After Fukushima?", Dr. Alexander...

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

    On Saturday MBG Auditorium "Is There a Future for Nuclear Power After Fukushima?", Dr. ... For the safety of staff and visitors, PPPL security officers retain the right to ...

  7. Deputy Secretary Poneman Delivers Remarks on Nuclear Power at Tokyo American Center in Japan

    Broader source: Energy.gov [DOE]

    WASHINGTON, D.C. – Energy Deputy Secretary Daniel Poneman spoke at the Tokyo American Center today about nuclear power after Fukushima.

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

    Broader source: Energy.gov [DOE]

    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...

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

    SciTech Connect (OSTI)

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

    2011-01-01

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

  10. Response of the Potomac Electric Power Company to the Operating...

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

    Preliminary Response of PJM Interconnection, L.L.C. to the Operating Plan of Mirant Potomac River, LLC Comments on Department of Energy's Emergency Order To Resume Limited ...

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

    Energy Savers [EERE]

    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

  12. Microsoft PowerPoint - NRC Nuclear Export Controls Implementing...

    National Nuclear Security Administration (NNSA)

    Legal Basis * Atomic Energy Act of 1954, as amended * Nuclear Non-Proliferation Act of 1978 * Treaties, Conventions and Agreements including: - Nuclear Non-Proliferation Treaty - ...

  13. Electric power annual 1994. Volume 2, Operational and financial data

    SciTech Connect (OSTI)

    1995-11-28

    This year, the annual is published in two volumes. Volume I focused on US electric utilities and contained final 1994 data on net generation, fossil fuel consumption, stocks, receipts, and cost. This Volume II presents annual 1994 summary statistics for the electric power industry, including information on both electric utilities and nonutility power producers. Included are preliminary data for electric utility retail sales of electricity, associated revenue, and average revenue per kilowatthour of electricity sold (based on form EIA-861) and for electric utility financial statistics, environmental statistics, power transactions, and demand- side management. Final 1994 data for US nonutility power producers on installed capacity and gross generation, as well as supply and disposition information, are also provided in Volume II. Technical notes and a glossary are included.

  14. 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

  15. 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.

  16. 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.

  17. 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

  18. Booster main magnet power supply, present operation and potential future upgrades

    SciTech Connect (OSTI)

    Bajon, E.; Bannon, M.; Marneris, I.; Danowski, G.; Sandberg, J.; Savatteri, S.

    2011-03-28

    The Brookhaven Booster Main Magnet Power Supply (MMPS) is a 24 pulse thyristor control supply, rated at 5500 Amps, +/-2000 Volts, or 3000 Amps, +/-6000 Volts. The power supply is fed directly from the power utility and the peak magnet power is 18 MWatts. This peak power is seen directly at the incoming ac line. This power supply has been in operation for the last 18 years. This paper will describe the present topology and operation of the power supply, the feedback control system and the different modes of operation of the power supply. Since the power supply has been in operation for the last 18 years, upgrading this power supply is essential. A new power supply topology has been studied where energy is stored in capacitor banks. DC to DC converters are used to convert the dc voltage stored in the capacitor banks to pulsed DC voltage into the magnet load. This enables the average incoming power from the ac line to be constant while the peak magnet power is pulsed to +/- 18 MWatts. Simulations and waveforms of this power supply will be presented.

  19. Nuclear Regulatory Commission Handling of Beyond Design Basis Events for Nuclear Power Reactors

    Broader source: Energy.gov [DOE]

    Presenter: Bill Reckley, Chief, Policy and Support Branch, Japan Lessons-Learned Project Directorate, Office of Nuclear Reactor Regulation, US Nuclear Regulatory Commission US Nuclear Regulatory Commission

  20. Multiple-Reheat Brayton Cycles for Nuclear Power Conversion with Molten

    Office of Scientific and Technical Information (OSTI)

    Coolants (Journal Article) | SciTech Connect Journal Article: Multiple-Reheat Brayton Cycles for Nuclear Power Conversion with Molten Coolants Citation Details In-Document Search Title: Multiple-Reheat Brayton Cycles for Nuclear Power Conversion with Molten Coolants Gas-turbine power conversion systems can have lower capital costs than comparable steam-turbine systems due to their higher power density. The recent commercialization of magnetic bearing systems for large turbomachinery now

  1. KCP operations began 65 years ago today | National Nuclear Security...

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

    operations began 65 years ago today Thursday, February 27, 2014 - 4:43pm On Feb. 28, 1949, ... Today, the Kansas City Plant is celebrating 65 years of delivering on its national ...

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

    SciTech Connect (OSTI)

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

    2012-07-01

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

  3. 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).

  4. 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

  5. EARLY-STAGE DESIGN AND EVALUATION FOR NUCLEAR POWER PLANT CONTROL ROOM UPGRADES

    SciTech Connect (OSTI)

    Ronald L. Boring; Jeffrey C. Joe; Thomas A. Ulrich; Roger T. Lew

    2015-03-01

    As control rooms are modernized with new digital systems at nuclear power plants, it is necessary to evaluate operator performance with these systems as part of a verification and validation process. While there is regulatory and industry guidance for some modernization activities, there are no well defined standard processes or predefined metrics available for assessing what is satisfactory operator interaction with new systems, especially during the early design stages. This paper proposes a framework defining the design process and metrics for evaluating human system interfaces as part of control room modernization. The process and metrics are generalizable to other applications and serve as a guiding template for utilities undertaking their own control room modernization activities.

  6. 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: ...

  7. Nuclear Power Generation and Fuel Cycle Report 1996

    Reports and Publications (EIA)

    1996-01-01

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

  8. Operating Reserves and Wind Power Integration: An International Comparison; Preprint

    SciTech Connect (OSTI)

    Milligan, M.; Donohoo, P.; Lew, D.; Ela, E.; Kirby, B.; Holttinen, H.; Lannoye, E.; Flynn, D.; O'Malley, M.; Miller, N.; Eriksen, P. B.; Gottig, A.; Rawn, B.; Gibescu, M.; Lazaro, E. G.; Robitaille, A.; Kamwa, I.

    2010-10-01

    This paper provides a high-level international comparison of methods and key results from both operating practice and integration analysis, based on an informal International Energy Agency Task 25: Large-scale Wind Integration.

  9. 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.

  10. Enterprise Assessments Targeted Review of Nuclear Reactor Facility Operations at Sandia National Laboratories … March 2016

    Energy Savers [EERE]

    Targeted Review of Nuclear Reactor Facility Operations at Sandia National Laboratories March 2016 Office of Nuclear Safety and Environmental Assessments Office of Environment, Safety and Health Assessments Office of Enterprise Assessments U.S. Department of Energy i Table of Contents Acronyms ...................................................................................................................................................... ii Executive Summary

  11. Spallator and APEX nuclear fuel cycle: a new option for nuclear power

    SciTech Connect (OSTI)

    Steinberg, M.

    1982-01-01

    A new nuclear fuel cycle is described which provides a long term supply of nuclear fuel for the thermal LWR nuclear power reactors and eliminates the need for long-term storage of radioactive waste. Fissile fuel is produced by the Spallator which depends on the production of spallation neutrons by the interaction of high-energy (1 to 2 GeV) protons on a heavy-metal target. The neutrons are absorbed in a surrounding natural-uranium or thorium blanket in which fissile Pu-239 to U-233 is produced. Advances in linear accelerator technology makes it possible to design and construct a high-beam-current continuous-wave proton linac for production purposes. The target is similar to a sub-critical reactor and produces heat which is converted to electricity for supplying the linac. The Spallator is a self-sufficient fuel producer, which can compete with the fast breeder. The APEX fuel cycle depends on recycling the transuranics and long-lived fission products while extracting the stable and short-lived fission products when reprocessing the fuel. Transmutation and decay within the fuel cycle and decay of short-lived fission products external to the fuel cycle eliminates the need for long-term geological age shortage of fission-product waste.

  12. The Spallator and APEX nuclear fuel cycle: a new option for nuclear power

    SciTech Connect (OSTI)

    Steinberg, M.

    1983-02-01

    A new nuclear fuel cycle is described which provides a long term supply of nuclear fuel for the thermal LWR nuclear power reactors and eliminates the need for long-term storage of radioactive waste. Fissile fuel is produced by the Spallator which depends on the production of spallation neutrons by the interaction of high energy (1 to 2 GeV) protons on a heavy metal target. The neutrons are absorbed in a surrounding natural uranium or thorium blanket in which fissile Pu-239 or U-233 is produced. Advances in linear accelerator technology makes it possible to design and construct a high beam current continuous wave proton linac for production purposes. The target is similar to a sub-critical reactor and produces heat which is converted to electricity for supplying the linac. The Spallator is a selfsufficient fuel producer, which can compete with the fast breeder. The APEX fuel cycle depends on recycling the transuranics and long-lived fission products while extracting the stable and short-lived fission products when reprocessing the fuel. Transmutation and decay within the fuel cycle and decay of the short-lived fission products external to the fuel cycle eliminates the need for long-term geological age storage of fission product waste.

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

    SciTech Connect (OSTI)

    Tropasso, R.T.

    1995-12-31

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

  14. Nuclear Safety Specialist Functional Area Qualification Standard

    Energy Savers [EERE]

    83-2007 November 2007 DOE STANDARD NUCLEAR SAFETY SPECIALIST FUNCTIONAL AREA QUALIFICATION ... Center (NTC) * Institute of Nuclear Power Operations (INPO) * American Institute ...

  15. REVIEW Of COMPUTERIZED PROCEDURE GUIDELINES FOR NUCLEAR POWER PLANT CONTROL ROOMS

    SciTech Connect (OSTI)

    David I Gertman; Katya Le Blanc; Ronald L Boring

    2011-09-01

    Computerized procedures (CPs) are recognized as an emerging alternative to paper-based procedures for supporting control room operators in nuclear power plants undergoing life extension and in the concept of operations for advanced reactor designs. CPs potentially reduce operator workload, yield increases in efficiency, and provide for greater resilience. Yet, CPs may also adversely impact human and plant performance if not designed and implemented properly. Therefore, it is important to ensure that existing guidance is sufficient to provide for proper implementation and monitoring of CPs. In this paper, human performance issues were identified based on a review of the behavioral science literature, research on computerized procedures in nuclear and other industries, and a review of industry experience with CPs. The review of human performance issues led to the identification of a number of technical gaps in available guidance sources. To address some of the gaps, we developed 13 supplemental guidelines to support design and safety. This paper presents these guidelines and the case for further research.

  16. Innovative Sensors and Controls to Support Efficient Operation of State-of-the-Art Power Plants

    Broader source: Energy.gov [DOE]

    The Department of Energy’s Office of Fossil Energy has selected three projects to develop novel sensing and control technologies aimed at the efficient operation of advanced, zero-emission power systems and the improvement of operations at existing fossil energy power plants.

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

    SciTech Connect (OSTI)

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

    1987-06-01

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

  18. 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 identified by experts to improve upon the design of the DCS. A set of nine design recommendations was developed to address these potential issues. The design principles addressed the following areas: (1) color, (2) pop-up window structure, (3) navigation, (4) alarms, (5) process control diagram, (6) gestalt grouping, (7) typography, (8) terminology, and (9) data entry. Visuals illustrating the improved DCS displays accompany the design recommendations. These nine design principles serve as the starting point to a planned general DCS style guide that can be used across the U.S. nuclear industry to aid in the future design of effective DCS interfaces.

  19. Vital area identification for U.S. Nuclear Regulatory Commission nuclear power reactor licensees and new reactor applicants.

    SciTech Connect (OSTI)

    Whitehead, Donnie Wayne; Varnado, G. Bruce

    2008-09-01

    U.S. Nuclear Regulatory Commission nuclear power plant licensees and new reactor applicants are required to provide protection of their plants against radiological sabotage, including the placement of vital equipment in vital areas. This document describes a systematic process for the identification of the minimum set of areas that must be designated as vital areas in order to ensure that all radiological sabotage scenarios are prevented. Vital area identification involves the use of logic models to systematically identify all of the malicious acts or combinations of malicious acts that could lead to radiological sabotage. The models available in the plant probabilistic risk assessment and other safety analyses provide a great deal of the information and basic model structure needed for the sabotage logic model. Once the sabotage logic model is developed, the events (or malicious acts) in the model are replaced with the areas in which the events can be accomplished. This sabotage area logic model is then analyzed to identify the target sets (combinations of areas the adversary must visit to cause radiological sabotage) and the candidate vital area sets (combinations of areas that must be protected against adversary access to prevent radiological sabotage). Any one of the candidate vital area sets can be selected for protection. Appropriate selection criteria will allow the licensee or new reactor applicant to minimize the impacts of vital area protection measures on plant safety, cost, operations, or other factors of concern.

  20. 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 discussions are summarized in this report

  1. Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit-1: Analysis of core damage frequency from internal events during mid-loop operations. Appendix I, Volume 2, Part 5

    SciTech Connect (OSTI)

    Chu, T.L.; Musicki, Z.; Kohut, P.; Yang, J.; Bozoki, G.; Hsu, C.J.; Diamond, D.J.; Bley, D.; Johnson, D.; Holmes, B.

    1994-06-01

    Traditionally, probabilistic risk assessments (PRA) of severe accidents in nuclear power plants have considered initiating events potentially occurring only during full power operation. Some previous screening analyses that were performed for other modes of operation suggested that risks during those modes were small relative to full power operation. However, more recent studies and operational experience have implied that accidents during low power and shutdown could be significant contributors to risk. During 1989, the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully examine the potential risks during low power and shutdown operations. The program includes two parallel projects being performed by Brookhaven National Lab. (BNL) and Sandia National Labs. (SNL). Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the plants to be studied. The objectives of the program are to assess the risks of severe accidents initiated during plant operational states other than full power operation and to compare the estimated core damage frequencies, important accident sequences and other qualitative and quantitative results with those accidents initiated during full power operation as assessed in NUREG-1150. The objective of this volume of the report is to document the approach utilized in the level-1 internal events PRA for the Surry plant, and discuss the results obtained. A phased approach was used in the level-1 program. In phase 1, which was completed in Fall 1991, a coarse screening analysis examining accidents initiated by internal events (including internal fire and flood) was performed for all plant operational states (POSs). The objective of the phase 1 study was to identify potential vulnerable plant configurations, to characterize (on a high, medium, or low basis) the potential core damage accident scenarios, and to provide a foundation for a detailed phase 2 analysis.

  2. Impact of Improved Solar Forecasts on Bulk Power System Operations in ISO-NE (Presentation)

    SciTech Connect (OSTI)

    Brancucci Martinez-Anido, C.; Florita, A.; Hodge, B.M.

    2014-11-01

    The diurnal nature of solar power is made uncertain by variable cloud cover and the influence of atmospheric conditions on irradiance scattering processes. Its forecasting has become increasingly important to the unit commitment and dispatch process for efficient scheduling of generators in power system operations. This presentation is an overview of a study that examines the value of improved solar forecasts on Bulk Power System Operations.

  3. Impact of Distributed Wind on Bulk Power System Operations in ISO-NE (Presentation)

    SciTech Connect (OSTI)

    Brancucci Martinez-Anido, C.; Hodge, B. M.; Palchak, D.; Miettinen, J.

    2014-11-01

    The work presented in the paper corresponding to this presentation aims to study the impact of a range of penetration levels of distributed wind on the operation of the electric power system at the transmission level. This presentation is an overview of a case study on the power system in Independent System Operator New England. It is analyzed using PLEXOS, a commercial power system simulation tool

  4. Stochastic Methods for Planning and Operating Power Systems with Large Amounts of Wind and Solar Power: Preprint

    SciTech Connect (OSTI)

    Milligan, M.; Donohoo, P.; O'Malley, M.

    2012-09-01

    Wind and solar generators differ in their generation characteristics than conventional generators. The variable output and imperfect predictability of these generators face a stochastic approach to plan and operate the power system without fundamentally changing the operation and planning problems. This paper overviews stochastic modeling challenges in operations, generation planning, and transmission planning, with references to current industry and academic work. Different stochastic problem formulations, including approximations, are also discussed.

  5. 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.

  6. New Research Center to Increase Safety and Power Output of U.S. Nuclear

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

    Reactors | Department of Energy Research Center to Increase Safety and Power Output of U.S. Nuclear Reactors New Research Center to Increase Safety and Power Output of U.S. Nuclear Reactors May 3, 2011 - 3:41pm Addthis Oak Ridge, Tenn. - Today the Department of Energy dedicated the Consortium for Advanced Simulation of Light Water Reactors (CASL), an advanced research facility that will accelerate the advancement of nuclear reactor technology. CASL researchers are using supercomputers to

  7. Guide to Combined Heat and Power Systems for Boiler Owners and Operators,

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

    July 2004 | Department of Energy Guide to Combined Heat and Power Systems for Boiler Owners and Operators, July 2004 Guide to Combined Heat and Power Systems for Boiler Owners and Operators, July 2004 Many owners and operators of industrial, commercial, and institutional (ICI) boiler systems need to use energy more efficiently. This 2004 guide is organized into topics that address many of the fundamental issues encountered in planning a CHP project and focuses on technical subjects

  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 technology, and (3) different architectures within the same technology. Using this convention, the first diversity usage family, designated Strategy A, is characterized by fundamentally diverse technologies. Strategy A at the system or platform level is illustrated by the example of analog and digital implementations. The second diversity usage family, designated Strategy B, is achieved through the use of distinctly different technologies. Strategy B can be described in terms of different digital technologies, such as the distinct approaches represented by general-purpose microprocessors and field-programmable gate arrays. The third diversity usage family, designated Strategy C, involves the use of variations within a technology. An example of Strategy C involves different digital architectures within the same technology, such as that provided by different microprocessors (e.g., Pentium and Power PC). The grouping of diversity criteria combinations according to Strategies A, B, and C establishes baseline diversity usage and facilitates a systematic organization of strategic approaches for coping with CCF vulnerabilities. Effectively, these baseline sets of diversity criteria constitute appropriate CCF mitigating strategies for digital safety systems. The strategies represent guidance on acceptable diversity usage and can be applied directly to ensure that CCF vulnerabilities identified through a D3 assessment have been adequately resolved. Additionally, a framework has been generated for capturing practices regarding diversity usage and a tool has been developed for the systematic assessment of the comparative effect of proposed diversity strategies (see Appendix A).

  9. 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%.

  10. Energy Department Nuclear Systems Are Powering Mars Rover

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

    Vogtle Advanced Nuclear Energy Project | Department of Energy Remaining $1.8 Billion in Loan Guarantees for Vogtle Advanced Nuclear Energy Project Energy Department Issues Remaining $1.8 Billion in Loan Guarantees for Vogtle Advanced Nuclear Energy Project June 24, 2015 - 9:20am Addthis NEWS MEDIA CONTACT (202) 586-4940 To further support the construction of two advanced nuclear reactors at the Alvin W. Vogtle Electric Generating Plant, the Department of Energy announced today it will issue

  11. Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1: Evaluation of severe accident risks for plant operational state 5 during a refueling outage. Main report and appendices, Volume 6, Part 1

    SciTech Connect (OSTI)

    Brown, T.D.; Kmetyk, L.N.; Whitehead, D.; Miller, L.; Forester, J.; Johnson, J.

    1995-03-01

    Traditionally, probabilistic risk assessments (PRAS) of severe accidents in nuclear power plants have considered initiating events potentially occurring only during full power operation. Recent studies and operational experience have, however, implied that accidents during low power and shutdown could be significant contributors to risk. In response to this concern, in 1989 the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully examine the potential risks during low power and shutdown operations. Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the plants to be studied. The program consists of two parallel projects being performed by Brookhaven National Laboratory (Surry) and Sandia National Laboratories (Grand Gulf). The program objectives include assessing the risks of severe accidents initiated during plant operational states other than full power operation and comparing the estimated risks with the risk associated with accidents initiated during full power operation as assessed in NUREG-1150. The scope of the program is that of a Level-3 PRA. The subject of this report is the PRA of the Grand Gulf Nuclear Station, Unit 1. The Grand Gulf plant utilizes a 3833 MWt BUR-6 boiling water reactor housed in a Mark III containment. The Grand Gulf plant is located near Port Gibson, Mississippi. The regime of shutdown analyzed in this study was plant operational state (POS) 5 during a refueling outage, which is approximately Cold Shutdown as defined by Grand Gulf Technical Specifications. The entire PRA of POS 5 is documented in a multi-volume NUREG report (NUREG/CR-6143). The internal events accident sequence analysis (Level 1) is documented in Volume 2. The Level 1 internal fire and internal flood analyses are documented in Vols 3 and 4, respectively.

  12. 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 developing technical basis to support acceptance criteria and set point decisions, particularly for advanced sensors which do not yet have a cumulative history of operating performance.

  13. 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.

  14. 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.

  15. Convexity of Energy-Like Functions: Theoretical Results and Applications to Power System Operations

    SciTech Connect (OSTI)

    Dvijotham, Krishnamurthy; Chertkov, Michael; Low, Steven

    2015-01-22

    Power systems are undergoing unprecedented transformations with increased adoption of renewables and distributed generation, as well as the adoption of demand response programs. All of these changes, while making the grid more responsive and potentially more efficient, pose significant challenges for power systems operators. Conventional operational paradigms are no longer sufficient as the power system may no longer have big dispatchable generators with sufficient positive and negative reserves. This increases the need for tools and algorithms that can efficiently predict safe regions of operation of the power system. In this paper, we study energy functions as a tool to design algorithms for various operational problems in power systems. These have a long history in power systems and have been primarily applied to transient stability problems. In this paper, we take a new look at power systems, focusing on an aspect that has previously received little attention: Convexity. We characterize the domain of voltage magnitudes and phases within which the energy function is convex in these variables. We show that this corresponds naturally with standard operational constraints imposed in power systems. We show that power of equations can be solved using this approach, as long as the solution lies within the convexity domain. We outline various desirable properties of solutions in the convexity domain and present simple numerical illustrations supporting our results.

  16. Office for Analysis and Evaluation of Operational Data 1992 annual report: Power reactors. Volume 7, No. 1

    SciTech Connect (OSTI)

    1993-07-01

    The annual report of the US Nuclear Regulatory Commission`s Office for Analysis and Evaluation of Operational Data (AEOD) is devoted to the activities performed during 1992. The report is published in two separate parts. NUREG-1272, Vol. 7, No. 1, covers power reactors and presents an overview of the operating experience of the nuclear power industry from the NRC perspective, including comments about the trends of some key performance, measures. The report also includes the principal findings and issues identified in AEOD studies over the past year, and summarizes information from such sources as licensee event report% diagnostic evaluations, and reports to the NRC`s Operations Center. The reports contain a discussion of the Incident Investigation Team program and summarize the Incident Investigation Team and Augmented Inspection Team reports for that group of licensees. NUREG-1272, Vol. 7, No. 2, covers nonreactors and presents a review of the events and concerns during 1992 associated with the use of licensed material in nonreactor applications, such as personnel overexposures and medical misadministrations. Each volume contains a list of the AEOD reports issued for 1984--1992.

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

    SciTech Connect (OSTI)

    Brown, L.C.

    2002-11-01

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

  18. Baseline Evaluations to Support Control Room Modernization at Nuclear Power Plants

    SciTech Connect (OSTI)

    Boring, Ronald L.; Joe, Jeffrey C.

    2015-02-01

    For any major control room modernization activity at a commercial nuclear power plant (NPP) in the U.S., a utility should carefully follow the four phases prescribed by the U.S. Nuclear Regulatory Commission in NUREG-0711, Human Factors Engineering Program Review Model. These four phases include Planning and Analysis, Design, Verification and Validation, and Implementation and Operation. While NUREG-0711 is a useful guideline, it is written primarily from the perspective of regulatory review, and it therefore does not provide a nuanced account of many of the steps the utility might undertake as part of control room modernization. The guideline is largely summative—intended to catalog final products—rather than formative—intended to guide the overall modernization process. In this paper, we highlight two crucial formative sub-elements of the Planning and Analysis phase specific to control room modernization that are not covered in NUREG-0711. These two sub-elements are the usability and ergonomics baseline evaluations. A baseline evaluation entails evaluating the system as-built and currently in use. The usability baseline evaluation provides key insights into operator performance using the control system currently in place. The ergonomics baseline evaluation identifies possible deficiencies in the physical configuration of the control system. Both baseline evaluations feed into the design of the replacement system and subsequent summative benchmarking activities that help ensure that control room modernization represents a successful evolution of the control system.

  19. Updating Human Factors Engineering Guidelines for Conducting Safety Reviews of Nuclear Power Plants

    SciTech Connect (OSTI)

    O, J.M.; Higgins, J.; Stephen Fleger - NRC

    2011-09-19

    The U.S. Nuclear Regulatory Commission (NRC) reviews the human factors engineering (HFE) programs of applicants for nuclear power plant construction permits, operating licenses, standard design certifications, and combined operating licenses. The purpose of these safety reviews is to help ensure that personnel performance and reliability are appropriately supported. Detailed design review procedures and guidance for the evaluations is provided in three key documents: the Standard Review Plan (NUREG-0800), the HFE Program Review Model (NUREG-0711), and the Human-System Interface Design Review Guidelines (NUREG-0700). These documents were last revised in 2007, 2004 and 2002, respectively. The NRC is committed to the periodic update and improvement of the guidance to ensure that it remains a state-of-the-art design evaluation tool. To this end, the NRC is updating its guidance to stay current with recent research on human performance, advances in HFE methods and tools, and new technology being employed in plant and control room design. This paper describes the role of HFE guidelines in the safety review process and the content of the key HFE guidelines used. Then we will present the methodology used to develop HFE guidance and update these documents, and describe the current status of the update program.

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

    SciTech Connect (OSTI)

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

    2003-06-20

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

  1. A historical perspective of remote operations and robotics in nuclear facilities. Robotics and Intelligent Systems Program

    SciTech Connect (OSTI)

    Herndon, J.N.

    1992-12-31

    The field of remote technology is continuing to evolve to support man`s efforts to perform tasks in hostile environments. The technology which we recognize today as remote technology has evolved over the last 45 years to support human operations in hostile environments such as nuclear fission and fusion, space, underwater, hazardous chemical, and hazardous manufacturing. The four major categories of approach to remote technology have been (1) protective clothing and equipment for direct human entry, (2) extended reach tools using distance for safety, (3) telemanipulators with barriers for safety, and (4) teleoperators incorporating mobility with distance and/or barriers for safety. The government and commercial nuclear industry has driven the development of the majority of the actual teleoperator hardware available today. This hardware has been developed largely due to the unsatisfactory performance of the protective-clothing approach in many hostile applications. Manipulation systems which have been developed include crane/impact wrench systems, unilateral power manipulators, mechanical master/slaves, and servomanipulators. Viewing systems have included periscopes, shield windows, and television systems. Experience over the past 45 years indicates that maintenance system flexibility is essential to typical repair tasks because they are usually not repetitive, structured, or planned. Fully remote design (manipulation, task provisions, remote tooling, and facility synergy) is essential to work task efficiency. Work for space applications has been primarily research oriented with relatively few successful space applications, although the shuttle`s remote manipulator system has been quite successful. In the last decade, underwater applications have moved forward significantly, with the offshore oil industry and military applications providing the primary impetus.

  2. Microsoft PowerPoint - Australian Nuclear Cooperation Agreements...

    National Nuclear Security Administration (NNSA)

    Australian Nuclear Cooperation Agreements Dr Vanessa Robertson, Australian Safeguards and Non-Proliferation Office The Australian Safeguards and Non-Proliferation Office 2 Director ...

  3. Nuclear Power Generation and Fuel Cycle Report 1997

    Reports and Publications (EIA)

    1997-01-01

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

  4. Nuclear energy is an important source of power, supplying 20

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

    Los Alamos National Laboratory is playing a key role in developing these solutions with its core strengths in nuclear fuels development, testing, and characterization advanced ...

  5. Automatic ultrasonic inspection system for wear determination in calandria tubes of Embalse Nuclear Power Plant

    SciTech Connect (OSTI)

    Katchadjian, Pablo Desimone, Carlos Garcia, Alejandro; Antonaccio, Carlos; Schroeter, Fernando; Molina, Hctor

    2015-03-31

    Embalse Nuclear Power Plant (CNE) (CANDU design) is reaching its end of life and due to elapsed operating time the problem of deformation by accelerated creep occurs in the pressure tubes (PT), leading to a possible contact between calandria tubes (CT), concentric to the PT, and some Liquid Injection Shutdown System (LISS) nozzles that pass underneath them. With determination of CT wear, after the predicted contact occurs, the wear rate of the TC could be determined and thus take less conservative measures over the remaining life of the component. This paper presents the development of an ultrasonic technique for measuring wear in CT, with nominal thickness of 1.34 mm. Because the only access is through the interior of PT, to perform this measurement it is necessary to pass through three different interfaces.

  6. Review of Methods Related to Assessing Human Performance in Nuclear Power Plant Control Room Simulations

    SciTech Connect (OSTI)

    Katya L Le Blanc; Ronald L Boring; David I Gertman

    2001-11-01

    With the increased use of digital systems in Nuclear Power Plant (NPP) control rooms comes a need to thoroughly understand the human performance issues associated with digital systems. A common way to evaluate human performance is to test operators and crews in NPP control room simulators. However, it is often challenging to characterize human performance in meaningful ways when measuring performance in NPP control room simulations. A review of the literature in NPP simulator studies reveals a variety of ways to measure human performance in NPP control room simulations including direct observation, automated computer logging, recordings from physiological equipment, self-report techniques, protocol analysis and structured debriefs, and application of model-based evaluation. These methods and the particular measures used are summarized and evaluated.

  7. Handbook of human-reliability analysis with emphasis on nuclear power plant applications. Final report

    SciTech Connect (OSTI)

    Swain, A D; Guttmann, H E

    1983-08-01

    The primary purpose of the Handbook is to present methods, models, and estimated human error probabilities (HEPs) to enable qualified analysts to make quantitative or qualitative assessments of occurrences of human errors in nuclear power plants (NPPs) that affect the availability or operational reliability of engineered safety features and components. The Handbook is intended to provide much of the modeling and information necessary for the performance of human reliability analysis (HRA) as a part of probabilistic risk assessment (PRA) of NPPs. Although not a design guide, a second purpose of the Handbook is to enable the user to recognize error-likely equipment design, plant policies and practices, written procedures, and other human factors problems so that improvements can be considered. The Handbook provides the methodology to identify and quantify the potential for human error in NPP tasks.

  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. Study on neutronic of very small Pb - Bi cooled no-onsite refueling nuclear power reactor (VSPINNOR)

    SciTech Connect (OSTI)

    Arianto, Fajar; Su'ud, Zaki; Zuhair

    2014-09-30

    A conceptual design study on Very Small Pb-Bi No-Onsite Refueling Cooled Nuclear Reactor (VSPINNOR) with Uranium nitride fuel using MCNPX program has been performed. In this design the reactor core is divided into three regions with different enrichment. At the center of the core is laid fuel without enrichment (internal blanket). While for the outer region using fuel enrichment variations. VSPINNOR fast reactor was operated for 10 years without refueling. Neutronic analysis shows optimized result of VSPINNOR has a core of 50 cm radius and 100 cm height with 300 MWth thermal power output at 60% fuel fraction that can be operated 18 years without refueling or fuel shuffling.

  12. The importance of input variables to a neural network fault-diagnostic system for nuclear power plants

    SciTech Connect (OSTI)

    Lanc, T.L.

    1992-01-01

    This thesis explores safety enhancement for nuclear power plants. Emergency response systems currently in use depend mainly on automatic systems engaging when certain parameters go beyond a pre-specified safety limit. Often times the operator has little or no opportunity to react since a fast scram signal shuts down the reactor smoothly and efficiently. These accidents are of interest to technical support personnel since examining the conditions that gave rise to these situations help determine causality. In many other cases an automated fault-diagnostic advisor would be a valuable tool in assisting the technicians and operators to determine what just happened and why.

  13. The importance of input variables to a neural network fault-diagnostic system for nuclear power plants

    SciTech Connect (OSTI)

    Lanc, T.L.

    1992-12-31

    This thesis explores safety enhancement for nuclear power plants. Emergency response systems currently in use depend mainly on automatic systems engaging when certain parameters go beyond a pre-specified safety limit. Often times the operator has little or no opportunity to react since a fast scram signal shuts down the reactor smoothly and efficiently. These accidents are of interest to technical support personnel since examining the conditions that gave rise to these situations help determine causality. In many other cases an automated fault-diagnostic advisor would be a valuable tool in assisting the technicians and operators to determine what just happened and why.

  14. Statement from Deputy Secretary of Energy Elizabeth Sherwood-Randall after Visiting the Fukushima Dai-ichi Nuclear Power Station

    Broader source: Energy.gov [DOE]

    Deputy Secretary Elizabeth Sherwood-Randall's statement after visiting the Fukushima Dai-ichi Nuclear Power Station in Japan

  15. Powering | GE Global Research

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

    Powering the Nuclear Navy The Naval Nuclear Propulsion Program provides militarily effective nuclear propulsion plants and ensures their safe, reliable and long-lived operation. NNSA's Naval Reactors Program provides the design, development and operational support required to provide militarily effective nuclear propulsion plants and ensure their safe, reliable and long-lived operation. Learn More USS George H.W. Bush conducts flight operations Concern for the Environment Protection of People

  16. Impacts of Improved Day-Ahead Wind Forecasts on Power Grid Operations: September 2011

    SciTech Connect (OSTI)

    Piwko, R.; Jordan, G.

    2011-11-01

    This study analyzed the potential benefits of improving the accuracy (reducing the error) of day-ahead wind forecasts on power system operations, assuming that wind forecasts were used for day ahead security constrained unit commitment.

  17. Variable Frequency Operations of an Offshore Wind Power Plant with HVDC-VSC: Preprint

    SciTech Connect (OSTI)

    Gevorgian, V.; Singh, M.; Muljadi, E.

    2011-12-01

    In this paper, a constant Volt/Hz operation applied to the Type 1 wind turbine generator. Various control aspects of Type 1 generators at the plant level and at the turbine level will be investigated. Based on DOE study, wind power generation may reach 330 GW by 2030 at the level of penetration of 20% of the total energy production. From this amount of wind power, 54 GW of wind power will be generated at offshore wind power plants. The deployment of offshore wind power plants requires power transmission from the plant to the load center inland. Since this power transmission requires submarine cable, there is a need to use High-Voltage Direct Current (HVDC) transmission. Otherwise, if the power is transmitted via alternating current, the reactive power generated by the cable capacitance may cause an excessive over voltage in the middle of the transmission distance which requires unnecessary oversized cable voltage breakdown capability. The use of HVDC is usually required for transmission distance longer than 50 kilometers of submarine cables to be economical. The use of HVDC brings another advantage; it is capable of operating at variable frequency. The inland substation will be operated to 60 Hz synched with the grid, the offshore substation can be operated at variable frequency, thus allowing the wind power plant to be operated at constant Volt/Hz. In this paper, a constant Volt/Hz operation applied to the Type 1 wind turbine generator. Various control aspects of Type 1 generators at the plant level and at the turbine level will be investigated.

  18. Impacts of Large Amounts of Wind Power on Design and Operation of Power Systems; Results of IEA Collaboration

    SciTech Connect (OSTI)

    Parsons, B. and Ela, E.; Holttinen, H.; Meibom, P.; Orths, A.; O'Malley, M.; Ummels, B.C.; Tande, J.

    2008-06-01

    There are a multitude of studies completed and ongoing related to the cost of wind integration. However, the results are not easy to compare. An international forum for exchange of knowledge of power system impacts of wind power has been formed under the IEA Implementing Agreement on Wind Energy. IEA WIND R&D Task 25 on Design and Operation of Power Systems with Large Amounts of Wind Power produced a state-of-the-art report in October 2007, where the most relevant wind-power grid integration studies were analyzed, especially regarding methodologies and input data. This paper summarizes the results from 18 case studies, with discussion on differences in methodology as well as issues that have been identified to impact the cost of wind integration.

  19. 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.

  20. SWiFT Operations

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

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

  1. 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 restoring the ability of degraded EPR to be compliant and resist fracture. The results of this research reveal that absorption of chemical treatments can lower the glass transition temperature and modulus of EPR. Chemical treatments pursued thus far have proven ineffective at restoring EPR strength and elongation at break. Future work will combine the plasticizer modalities found to successfully increase the volume of the EPR, reduce EPR glass transition temperature and reduce EPR modulus with promising chemistries that will repair the damage of the polymer, potentially using the plasticizer as a host for the new chemistry.

  2. A review for identification of initiating events in event tree development process on nuclear power plants

    SciTech Connect (OSTI)

    Riyadi, Eko H.

    2014-09-30

    Initiating event is defined as any event either internal or external to the nuclear power plants (NPPs) that perturbs the steady state operation of the plant, if operating, thereby initiating an abnormal event such as transient or loss of coolant accident (LOCA) within the NPPs. These initiating events trigger sequences of events that challenge plant control and safety systems whose failure could potentially lead to core damage or large early release. Selection for initiating events consists of two steps i.e. first step, definition of possible events, such as by evaluating a comprehensive engineering, and by constructing a top level logic model. Then the second step, grouping of identified initiating event's by the safety function to be performed or combinations of systems responses. Therefore, the purpose of this paper is to discuss initiating events identification in event tree development process and to reviews other probabilistic safety assessments (PSA). The identification of initiating events also involves the past operating experience, review of other PSA, failure mode and effect analysis (FMEA), feedback from system modeling, and master logic diagram (special type of fault tree). By using the method of study for the condition of the traditional US PSA categorization in detail, could be obtained the important initiating events that are categorized into LOCA, transients and external events.

  3. 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.

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

    SciTech Connect (OSTI)

    Cooke, Conrad; Spann, Holger

    2013-07-01

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

  5. 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.

  6. 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)

  7. Development and Analysis of Advanced High-Temperature Technology for Nuclear Heat Transport and Power Conversion

    SciTech Connect (OSTI)

    Per F. Peterson

    2010-03-01

    This project by the Thermal Hydraulics Research Laboratory at U.C. Berkeley Studied advanced high-temperature heat transport and power conversion technology, in support of the Nuclear Hydrogen Initiative and Generation IV.

  8. Prospects for Nuclear Power(Davis 2012) | OpenEI Community

    Open Energy Info (EERE)

    Prospects for Nuclear Power(Davis 2012) Home > Groups > Energy Systems Integration Qinsun's picture Submitted by Qinsun(35) Member 15 November, 2012 - 13:36 This paper analyzed the...

  9. Tornado vs. Hurricane Which is More Critical for Design of U.S. Nuclear Power Plants?

    Broader source: Energy.gov [DOE]

    Tornado vs. Hurricane Which is More Critical for Design of U.S. Nuclear Power Plants? Javad Moslemian Sargent & Lundy, LLC U. S. Department of Energy Natural Phenomena Hazards Meeting October 21-22, 2014

  10. Theoretical uncertainties in the nuclear matrix elements of neutrinoless double beta decay: The transition operator

    SciTech Connect (OSTI)

    Menndez, Javier

    2013-12-30

    We explore the theoretical uncertainties related to the transition operator of neutrinoless double-beta (0???) decay. The transition operator used in standard calculations is a product of one-body currents, that can be obtained phenomenologically as in Tomoda [1] or imkovic et al. [2]. However, corrections to the operator are hard to obtain in the phenomenological approach. Instead, we calculate the 0??? decay operator in the framework of chiral effective theory (EFT), which gives a systematic order-by-order expansion of the transition currents. At leading orders in chiral EFT we reproduce the standard one-body currents of Refs. [1] and [2]. Corrections appear as two-body (2b) currents predicted by chiral EFT. We compute the effects of the leading 2b currents to the nuclear matrix elements of 0??? decay for several transition candidates. The 2b current contributions are related to the quenching of Gamow-Teller transitions found in nuclear structure calculations.

  11. Energy Department Announces New Investments in Advanced Nuclear Power Reactors

    Broader source: Energy.gov [DOE]

    WASHINGTON – Today, as part of the President’s all-of-the-above energy approach and Climate Action Plan, the Energy Department announced awards for five companies to lead key nuclear energy...

  12. NPP financial and regulatory risks-Importance of a balanced and comprehensive nuclear law for a newcomer country considering nuclear power programme

    SciTech Connect (OSTI)

    Manan, J. A. N. Abd Mostafa, N. A.; Salim, M. F.

    2015-04-29

    The nature of Nuclear Power Plant (NPP) projects are: long duration (10-15 years for new build), high capital investment, reasonable risks and highly regulated industries to meet national and international requirement on Safety, Security, Safeguards (3S) and Liabilities. It requires long term planning and commitment from siting to final disposal of waste/spent fuel. Potential financial and regulatory risks are common in massive NPP projects and will be magnified in the case of using unproven technology. If the risks are not properly managed, it can lead to high project and operation costs, and, fail to fulfil its objectives to provide compatible electricity prices and. energy security. To ensure successful, the government and investors need to ensure that the NPP project is bankable with low cost of project and funding, have fair treatment and proper risk mitigation, and able to complete on time with no cost overrun. One of the requirements as prerequisite for the development of NPP as stipulated by the International Atomic Energy Agency (IAEA) is the establishment of a Legal and Regulatory Framework. The main objective of nuclear law is to ensure that the activities and projects carried-out in the country are legal and compliant to national and international requirements. The law should also be able to provide fair treatment of risks on its activities that is acceptable to investors. The challenge for a newcomer country is to develop a balanced and comprehensive national nuclear law that meet these objectives while taking into consideration various stakeholders’ interest without compromising on safety, security, safeguard, liability requirements and other international obligations. This paper highlights the nature of NPP projects, its potential and associated financial and regulatory risks, and its major concerns and challenges. It proposes possible risks treatment and mitigation through the formulation of a balanced and comprehensive legislation by clear understanding of various requirements of public, regulators, investors, financial institutions, international community, operator and other important stakeholders. Ambiguities and uncertainties, especially with regards to certain conditions and requirements should be minimised by emulating good practices of experienced nuclear regulators. The imposition of various financial requirements such as funds for decommissioning, radioactive waste management, financial security, nuclear liabilities and licensing fees are necessary, but at the same time the quantum needs to be clearly defined. Concerns on absolute liability of the operators need to be addressed through a creation of necessary and proper nuclear insurance legislations to mitigate operator S nuclear liability obligations and other financial risks. Another major risk to investors is the possibility of public resistance which will not only can hinder the construction but can also stop operation of the nuclear power plant which will contribute to huge losses to investors and countries. This may require a provision in the legislation that provide proper compensation for these situations and at the same time to allow operators to engage in nuclear promotional activities, such as community benefit and public consultation as voluntary initiatives. Through proper planning, research, consultation and execution, the proposed nuclear law shall be able to promote good regulatory practices for public and investors’ confidence and benefit. Early involvement of various stakeholders is essential as a platform for regular communications between regulators and interested parties. Stakeholders’ participation in the NPP programme and law developments will also promote transparency of the projects while upholding the independency of the regulators.

  13. "Is There a Future for Nuclear Power After Fukushima?", Dr. Alexander

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

    Glaser, Woodrow Wilson School of Public and International Affairs and Department of Mechanical and Aerospace Engineering, Princeton University | Princeton Plasma Physics Lab January 21, 2012, 9:30am Science On Saturday MBG Auditorium "Is There a Future for Nuclear Power After Fukushima?", Dr. Alexander Glaser, Woodrow Wilson School of Public and International Affairs and Department of Mechanical and Aerospace Engineering, Princeton University Is There a Future for Nuclear Power

  14. CERCLA Preliminary Assessment of DOE'S Nevada Operations Office Nuclear Weapons Testing

    Office of Legacy Management (LM)

    tudies/B ackground Book 1 CERCLA Preliminary Assessment of DOE'S Nevada Operations Office Nuclear Weapons Testing Areas Vol. 11, April 1988 DISCLAIMER Portions of this document may be illegible in electronic image products. Images are produced from the best available original document. CERCLA PRELIMINARY ASSESSMENT OF DOE'S NEVADA OPERATIONS OFFICE WCILEAR WEAPONS T E S r n G AREAS Prepared by Water Resources Center Desert Research Institute University of Nevada System ,Prepared for U . S .

  15. Occupational Radiation Exposure at Commercial Nuclear Power Reactors and Other Facilities 2010, Prepared for the Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, May 2012

    SciTech Connect (OSTI)

    D. E. Lewis D. A. Hagemeyer Y. U. McCormick

    2012-07-07

    This report summarizes the occupational exposure data that are maintained in the U.S. Nuclear Regulatory Commission’s (NRC) Radiation Exposure Information and Reporting System (REIRS). The bulk of the information contained in the report was compiled from the 2010 annual reports submitted by five of the seven categories of NRC licensees subject to the reporting requirements of 10 CFR 20.2206. Because there are no geologic repositories for high-level waste currently licensed and no NRC-licensed low-level waste disposal facilities currently in operation, only five categories will be considered in this report. The annual reports submitted by these licensees consist of radiation exposure records for each monitored individual. These records are analyzed for trends and presented in this report in terms of collective dose and the distribution of dose among the monitored individuals. Annual reports for 2010 were received from a total of 190 NRC licensees. The summation of reports submitted by the 190 licensees indicated that 192,424 individuals were monitored, 81,961 of whom received a measurable dose. When adjusted for transient workers who worked at more than one licensee during the year, there were actually 142,471 monitored individuals and 62,782 who received a measurable dose. The collective dose incurred by these individuals was 10,617 person-rem, which represents a 12% decrease from the 2009 value. This decrease was primarily due to the decrease in collective dose at commercial nuclear power reactors, as well as a decrease in the collective dose for most of the other categories of NRC licensees. The number of individuals receiving a measurable dose also decreased, resulting in an average measurable dose of 0.13 rem for 2010. The average measurable dose is defined as the total effective dose equivalent (TEDE) divided by the number of individuals receiving a measurable dose. In calendar year 2010, the average annual collective dose per reactor for light water reactor (LWR) licensees was 83 person-rem. This represents a 14% decrease from the value reported for 2009 (96 person-rem). The decrease in collective dose for commercial nuclear power reactors was due to an 11% decrease in total outage hours in 2010. During outages, activities involving increased radiation exposure such as refueling and maintenance are performed while the reactor is not in operation. The average annual collective dose per reactor for boiling water reactors (BWRs) was 137 personrem for 35 BWRs, and 55 person-rem for 69 pressurized water reactors (PWRs). Analyses of transient individual data indicate that 29,333 individuals completed work assignments at two or more licensees during the monitoring year. The dose distributions are adjusted each year to account for the duplicate reporting of transient individuals by multiple licensees. The adjustment to account for transient individuals has been specifically noted in footnotes in the figures and tables for commercial nuclear power reactors. In 2010, the average measurable dose per individual for all licensees calculated from reported data was 0.13 rem. Although the average measurable dose per individual from data submitted by licensees was 0.13 rem, a corrected dose distribution resulted in an average measurable dose per individual of 0.17 rem.

  16. Summary and bibliography of safety-related events at boiling-water nuclear power plants as reported in 1980

    SciTech Connect (OSTI)

    McCormack, K.E.; Gallaher, R.B.

    1982-03-01

    This document presents a bibliography that contains 100-word abstracts of event reports submitted to the US Nuclear Regulatory Commission concerning operational events that occurred at boiling-water-reactor nuclear power plants in 1980. The 1547 abstracts included on microfiche in this bibliography describe incidents, failures, and design or construction deficiencies that were experienced at the facilities. These abstracts are arranged alphabetically by reactor name and then chronologically for each reactor. Full-size keyword and permuted-title indexes to facilitate location of individual abstracts are provided following the text. Tables that summarize the information contained in the bibliography are also provided. The information in the tables includes a listing of the equipment items involved in the reported events and the associated number of reports for each item. Similar information is given for the various kinds of instrumentation and systems, causes of failures, deficiencies noted, and the time of occurrence (i.e., during refueling, operation, testing, or construction).

  17. Impact of Distributed Wind on Bulk Power System Operations in ISO-NE: Preprint

    SciTech Connect (OSTI)

    Brancucci Martinez-Anido, C.; Hodge, B. M.; Palchak, D.; Miettinen, J.

    2014-09-01

    The work presented in this paper aims to study the impact of a range of penetration levels of distributed wind on the operation of the electric power system at the transmission level. This paper presents a case study on the power system in Independent System Operator New England. It is analyzed using PLEXOS, a commercial power system simulation tool. The results show that increasing the integration of distributed wind reduces total variable electricity generation costs, coal- and gas-fired electricity generation, electricity imports, and CO2 emissions, and increases wind curtailment. The variability and uncertainty of wind power also increases the start-up and shutdown costs and ramping of most conventional power plants.

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

    SciTech Connect (OSTI)

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

    1987-08-01

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

  19. Use of Modal Sensitivity to Operating Conditions for Damping Control in Power Systems

    SciTech Connect (OSTI)

    Huang, Zhenyu; Zhou, Ning; Tuffner, Francis K.; Trudnowski, Daniel J.

    2011-01-04

    Small signal stability is an inherent characteristic of dynamic systems such as power systems. Pole positioning through power system stabilizers (PSS) is often used for improving damping in power systems. A well-designed PSS can be very effective in damping oscillations, especially local oscillations. However, designing PSSs for inter-area oscillations has been a very challenging task due to time-varying operating conditions affecting the characteristics of inter-area oscillations. This paper explores the sensitivity relationship between oscillations and operating conditions and employs the relationship to derive recommendations for operators actions to adjust operating conditions so as to improve damping. Low damping is usually considered to be a result of heavy power transfer in long distance. Studies in this paper show that this generally holds true while locations have significant impact on damping of oscillations. Therefore it is important to consider locations in deriving recommendations. This paper proposes the concept of relative modal sensitivity and presents the application of relative modal sensitivity to derive recommendations for operators action in damping control.

  20. Electric power 2007

    SciTech Connect (OSTI)

    2007-07-01

    Subjects covered include: power industry trends - near term fuel strategies - price/quality/delivery/opportunity; generating fleet optimization and plant optimization; power plant safety and security; coal power plants - upgrades and new capacity; IGCC, advanced combustion and CO{sub 2} capture technologies; gas turbine and combined cycle power plants; nuclear power; renewable power; plant operations and maintenance; power plant components - design and operation; environmental; regulatory issues, strategies and technologies; and advanced energy strategies and technologies. The presentations are in pdf format.