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Sample records for nuclear power systems

  1. 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...

  2. Working Group Report on - Space Nuclear Power Systems and Nuclear...

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

    Working Group Report on - Space Nuclear Power Systems and Nuclear Waste Technology R&D Working Group Report on - Space Nuclear Power Systems and Nuclear Waste Technology R&D "Even...

  3. 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)

  4. 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)

  5. Nuclear Power 

    E-Print Network [OSTI]

    2010-01-01

    be inherently safe and environmentally benign. These realities of today's world are among the reasons that lead to serious interest in deploying nuclear power as a sustainable energy source. Today's nuclear reactors are safe and highly efficient energy systems...

  6. SELFMONITORING DISTRIBUTED MONITORING SYSTEM FOR NUCLEAR POWER PLANTS (PRELIMINARY VERSION)

    E-Print Network [OSTI]

    SELF­MONITORING DISTRIBUTED MONITORING SYSTEM FOR NUCLEAR POWER PLANTS (PRELIMINARY VERSION) Aldo and identification are extremely important activities for the safety of a nuclear power plant. In particular inside huge and complex production plants. 1 INTRODUCTION Safety in nuclear power plants requires

  7. Nuclear power systems for Lunar and Mars exploration

    SciTech Connect (OSTI)

    Sovie, R.J.; Bozek, J.M.

    1994-09-01

    Initial studies of a variety of mission scenarios for the new Space Exploration Initiative, and the technologies necessary to enable or significantly enhance them, have identified the development of advanced space power systems - whether solar, chemical or nuclear - to be of prime importance. Lightweight, compact, reliable power systems for planetary rovers and a variety of surface vehicles, utility surface power, and power for advanced propulsion systems were identified as critical needs for these missions. This paper discusses these mission scenarios, the concomitant power system requirements; the power system options considered and identifies the significant potential benefits of nuclear power for meeting the power needs of the above applications.

  8. Assessment of the Effect of Different Isolation Systems on Seismic Response of a Nuclear Power Plant

    E-Print Network [OSTI]

    Wong, Jenna

    2014-01-01

    Diesel Generators." Nuclear Power International MagazineIsolation Structure for Nuclear Power Plant, Japan ElectricIsolation System for Nuclear Power Plants, JEAG 4614-2000,

  9. Utility system integration and optimization models for nuclear power management

    E-Print Network [OSTI]

    Deaton, Paul Ferris

    1973-01-01

    A nuclear power management model suitable for nuclear utility systems optimization has been developed for use in multi-reactor fuel management planning over periods of up to ten years. The overall utility planning model ...

  10. System aspects of a Space Nuclear Reactor Power System

    SciTech Connect (OSTI)

    Jaffe, L.; Fujita, T.; Beatty, R.; Bhandari, P.; Chow, E.; Deininger, W.; Ewell, R.; Grossman, M.; Kia, T.; Nesmith, B.

    1988-01-01

    Selected systems aspects of a 300 kW nuclear reactor power system for spacecraft have been studied. The approach included examination of two candidate missions and their associated spacecraft, and a number of special topics dealing with the power system design and operation. The missions considered were a reusable orbital transfer vehicle and a space-based radar. The special topics included: power system configuration and scaling, launch vehicle integration, operating altitude, orbital storage, start-up, thawing, control, load following, procedures in case of malfunction, restart, thermal and nuclear radiation to other portions of the spacecraft, thermal stresses between subsystems, boom and cable designs, vibration modes, altitude control, reliability, and survivability. Among the findings are that the stowed length of the power system is important to mission design and that orbital storage for months to years may be needed for missions involving orbital assembly. The power system design evolved during the study and has continued to evolve; the current design differs somewhat from that examined in this paper.

  11. 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.

  12. ME 337C Introduction to Nuclear Power Systems ABET EC2000 syllabus

    E-Print Network [OSTI]

    Ben-Yakar, Adela

    ME 337C ­ Introduction to Nuclear Power Systems Page 1 ABET EC2000 syllabus ME 337C ­ Introduction to Nuclear Power Systems Fall 2009 Required or Elective: Elective 2008-2010 Catalog Data: Radioactivity, nuclear interactions: fission and fusion, fission reactors, nuclear power systems, nuclear power safety

  13. Use of expert systems in nuclear power plants

    SciTech Connect (OSTI)

    Uhrig, R.E.

    1989-01-01

    The application of technologies, particularly expert systems, to the control room activities in a nuclear power plant has the potential to reduce operator error and increase plant safety, reliability, and efficiency. Furthermore, there are a large number of nonoperating activities (testing, routine maintenance, outage planning, equipment diagnostics, and fuel management) in which expert systems can increase the efficiency and effectiveness of overall plant and corporate operations. This document presents a number of potential applications of expert systems in the nuclear power field. 36 refs., 2 tabs.

  14. Nuclear Power - System Simulations and Operation 

    E-Print Network [OSTI]

    2011-01-01

    Nuclear Codes 21 Antonella L. Costa, Patr?cia A. L. Reis, Clarysson A. M. Silva, Claubia Pereira, Maria Auxiliadora F. Veloso, Bruno T. Guerra, Humberto V. Soares and Amir Z. Mesquita Chapter 3 Development of an Appendix K Version of RELAP5-3D... 2 1 2 ( , , . . . , , , .. . , ); 1 , .. . ( , , . .. , , , . .. , ); 1 , .. . i i n k j j n k dy f y y y p p p t i n dt z g y y y p p p t j l = = = = where y: the state varia b l e s ; p: the input; z : the output variabl e s Somet i...

  15. 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.

  16. Technology Survey and Performance Scaling for the Design of High Power Nuclear Electric Power and Propulsion Systems

    E-Print Network [OSTI]

    1 Technology Survey and Performance Scaling for the Design of High Power Nuclear Electric Power OF HIGH POWER NUCLEAR ELECTRIC POWER AND PROPULSION SYSTEMS by Daniel B. White Jr. Submitted for the degree of Doctor of Philosophy in Aeronautics and Astronautics ABSTRACT High power nuclear electric

  17. Nuclear electromagnetic pulse (EMP) and electric power systems

    SciTech Connect (OSTI)

    Barnes, P.R.; Vance, E.F.; Askins, H.W. Jr.

    1984-04-01

    A nuclear detonation at high altitudes produces a transient electromagnetic pulse (EMP) of high-intensity electromagnetic fields. A single high-altitude burst can subject most of the continental United States to a strong EMP. These intense fields induce voltage and current transients in electrical conductors. Surges would be induced by EMP in transmission and distribution circuits and in control and communication elements in electric power systems throughout the national grid. Such widespread disturbances could upset the stability of electrical energy systems and result in massive power failures. The extent and nature of EMP-caused damages are not well known for utility electric power systems. Failures are likely to be associated with insulation damage and failures of low-voltage and solid-state components. It is concluded from a review of past studies that EMP may pose a serious threat to the nation's electrical energy supply.

  18. Formal Verification of Safety I&C System Designs: Two Nuclear Power Plant Related Applications

    E-Print Network [OSTI]

    Heljanko, Keijo

    and control (I&C) systems play a crucial role in the operation of nuclear power plants (NPP) and other safety of the environment is covered. The reactor emergency cooling system is in use in an operating nuclear power plant is a reactor emergency cooling system in an operating nuclear power plant. 2. MODEL CHECKING METHODOLOGY

  19. Nuclear electromagnetic pulse and the electric power system

    SciTech Connect (OSTI)

    Legro, J.R.; Reed, T.J.

    1985-01-01

    A single, high-altitude nuclear detonation over the continental United States can expose large geographic areas to transient, electromagnetic pulse (EMP). The initial electromagnetic fields produced by this event have been defined as high-altitude electromagnetic pulse (HEMP). Later-time, low frequency fields have been defined as magnetohydrodynamic-electromagnetic pulse (MHD-EMP). Nuclear detonations at, or near the surface of the earth can also produce transient EMP. These electromagnetic phenomena have been defined as source region electromagnetic pulse (SREMP). The Division of Electric Energy Systems (EES) of the United States Department of Energy (DOE) has formulated and implemented a Program Plan to assess the possible effects of the above nuclear EMP on civilian electric power systems. This unclassified research effort is under the technical leadership of the Oak Ridge National Laboratory. This paper presents a brief perspective of EMP phenomenology and important interaction issues for power systems based on research performed by Westinghouse Advanced Systems Technology as a principal subcontractor in the research effort.

  20. 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.

  1. Estimation of the reliability of space nuclear power systems by probabilistic risk assessment techniques 

    E-Print Network [OSTI]

    Gutner, Sophie Isabelle

    1996-01-01

    A successful space mission depends on the reliable operation of the spacecraft's electrical power system. For payloads requiring high power levels, various designs of space nuclear power systems (SNPS) are available. Designers have conducted limited...

  2. Technology survey and performance scaling for the design of high power nuclear electric power and propulsion systems

    E-Print Network [OSTI]

    White, Daniel B., Jr

    2011-01-01

    High power nuclear electric propulsion systems have the capability to enable many next-generation space exploration applications. To date, use of electric primary propulsion in flight systems has been limited to low-power, ...

  3. 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.

  4. 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).

  5. Power conversion system design for supercritical carbon dioxide cooled indirect cycle nuclear reactors

    E-Print Network [OSTI]

    Gibbs, Jonathan Paul

    2008-01-01

    The supercritical carbon dioxide (S-CO?) cycle is a promising advanced power conversion cycle which couples nicely to many Generation IV nuclear reactors. This work investigates the power conversion system design and ...

  6. Conceptual study of high power proton linac for accelerator driven subcritical nuclear power system

    E-Print Network [OSTI]

    Yu Qi; Ouyang Hua Fu; Xu Tao Guang

    2001-01-01

    As a prior option of the next generation of energy source, the accelerator driven subcritical nuclear power system (ADS) can use efficiently the uranium and thorium resource, transmute the high-level long-lived radioactive wastes and raise nuclear safety. The ADS accelerator should provide the proton beam with tens megawatts. The superconducting linac is a good selection of ADS accelerator because of its high efficiency and low beam loss rate. The ADS accelerator presented by the consists of a 5 MeV radio-frequency quadrupole, a 100 MeV independently phased superconducting cavity linac and a 1 GeV elliptical superconducting cavity linac. The accelerating structures and main parameters are determined and the research and development plan is considered

  7. Visualization and continuous simulation of a space nuclear power system 

    E-Print Network [OSTI]

    Rawal, Rajiv

    1992-01-01

    - tor Systems. In Third International Symposium on Science and Engineering on Cray Supemornputers (Minneapolis, Minnesota, Sept. 9-11). 1987. 6 Ransom, V. H. et al. RELAP5/MODg Code Manual. EG Ic G Idaho, Inc, Idaho National Engineering Laboratory.... There is need for improvement in the current process. Omega is a graphical user interface driven software, which enables quasi real time anal- ysis of reactor characteristics to be gained without either constructing or operating a full scale space nuclear...

  8. Ice Thermal Storage Systems for Nuclear Power Plant Supplemental Cooling and Peak Power Shifting

    SciTech Connect (OSTI)

    Haihua Zhao; Hongbin Zhang; Phil Sharpe; Blaise Hamanaka; Wei Yan; WoonSeong Jeong

    2013-03-01

    Availability of cooling water has been one of the major issues for the nuclear power plant site selection. Cooling water issues have frequently disrupted the normal operation at some nuclear power plants during heat waves and long draught. One potential solution is to use ice thermal storage (ITS) systems that reduce cooling water requirements and boost the plant’s thermal efficiency in hot hours. ITS uses cheap off-peak electricity to make ice and uses the ice for supplemental cooling during peak demand time. ITS also provides a way to shift a large amount of electricity from off peak time to peak time. For once-through cooling plants near a limited water body, adding ITS can bring significant economic benefits and avoid forced derating and shutdown during extremely hot weather. For the new plants using dry cooling towers, adding the ITS systems can effectively reduce the efficiency loss during hot weather so that new plants could be considered in regions lack of cooling water. This paper will review light water reactor cooling issues and present the feasibility study results.

  9. Gain-scheduled controller design for load-following in static space nuclear power systems 

    E-Print Network [OSTI]

    Onbasioglu, Fetiye Ozlem

    1993-01-01

    The use of shunt regulators for load-following of proposed static space nuclear power systems (SNPSS) raises a number of concerns, such as the possibility of a failure in the shunt regulators requiring reactor shutdown, or the possible need...

  10. A system-of-systems framework of Nuclear Power Plant Probabilistic Seismic Hazard Analysis by Fault Tree analysis and Monte Carlo simulation

    E-Print Network [OSTI]

    Boyer, Edmond

    A system-of-systems framework of Nuclear Power Plant Probabilistic Seismic Hazard Analysis by Fault consider the impacts produced on a nuclear power plant (the critical plant) embedded in the connected power simulation. As outcome of the analysis, the probability that the nuclear power plant reaches an unsafe state

  11. Preliminary assessment of high power, NERVA-class dual-mode space nuclear propulsion and power systems

    SciTech Connect (OSTI)

    Buksa, J.J.; Kirk, W.L.; Cappiello, M.W. (Nuclear Technology and Engineering Division, Los Alamos National Laboratory, Los Alamos, New Mexico 87544 (US))

    1991-01-05

    A preliminary assessment of the technical feasibility and mass competitiveness of a dual-mode nuclear propulsion and power system based on the NERVA rocket engine has been completed. Results indicate that the coupling of the ROVER reactor to a direct Brayton power conversion system can be accomplished through a number of design features. Furthermore, based on previously published and independently calculated component masses, the dual-mode system was found to have the potential to be mass competitive with propulsion/power systems that use separate reactors. The uncertainties of reactor design modification and shielding requirements were identified as important issues requiring future investigation.

  12. A Pattern-Based Method for Safe Control Systems Exemplified within Nuclear Power

    E-Print Network [OSTI]

    Střlen, Ketil

    A Pattern-Based Method for Safe Control Systems Exemplified within Nuclear Power Production Andr´e Alexandersen Hauge1,3 and Ketil Střlen2,3 1 Department of Software Engineering, Institute for Energy Technology. This article exemplifies the application of a pattern-based method, called SaCS (Safe Control Systems

  13. 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''.

  14. 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.

  15. Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume IV. Commercial potential

    SciTech Connect (OSTI)

    Not Available

    1980-06-01

    This volume of the Nonproliferation Alternative Systems Assessment Program (NASAP) report provides time and cost estimates for positioning new nuclear power systems for commercial deployment. The assessment also estimates the rates at which the new systems might penetrate the domestic market, assuming the continuing viability of the massive light-water reactor network that now exists worldwide. This assessment does not recommend specific, detailed program plans and budgets for individual systems; however, it is clear from this analysis that any of the systems investigated could be deployed if dictated by national interest.

  16. Transient modeling of thermionic space nuclear power systems 

    E-Print Network [OSTI]

    Berge, Francoise M

    1991-01-01

    be activated or disabled. The reactor kinetics model itself can be disabled so that only the thermal-hydraulic model is solved. Five types of reactivity feed- back mechanisms are implemented in CENTAR: programmed reactivity, fuel tempera- ture feedback... do not include the reactivity control. The power can be controlled as a function of the transient time. The pump head, on the other hand, can be specified to be constant and/or controlled as a function of the transient time and/or any temperature...

  17. Energy Department Nuclear Systems Are Powering Mars Rover

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would like submitKansasCommunities Energy Efficiency CompetitionDepartment ofdoe logo U.S.

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would like submitKansasCommunities Energy Efficiency CompetitionDepartment ofdoe logo

  19. NUCLEAR POWER in CALIFORNIA

    E-Print Network [OSTI]

    NUCLEAR POWER in CALIFORNIA: 2007 STATUS REPORT CALIFORNIA ENERGY COMMISSION October 2007 CEC-100 public workshops on nuclear power. The Integrated Energy Policy Report Committee, led by Commissioners, California Contract No. 700-05-002 Prepared For: California Energy Commission Barbara Byron, Senior Nuclear

  20. Near-term improvements for nuclear power plant control room annunciator systems. [PWR; BWR

    SciTech Connect (OSTI)

    Rankin, W.L.; Duvernoy, E.G.; Ames, K.R.; Morgenstern, M.H.; Eckenrode, R.J.

    1983-04-01

    This report sets forth a basic design philosophy with its associated functional criteria and design principles for present-day, hard-wired annunciator systems in the control rooms of nuclear power plants. It also presents a variety of annunciator design features that are either necessary for or useful to the implementation of the design philosophy. The information contained in this report is synthesized from an extensive literature review, from inspection and analysis of control room annunciator systems in the nuclear industry and in related industries, and from discussions with a variety of individuals who are knowledgeable about annunciator systems, nuclear plant control rooms, or both. This information should help licensees and license applicants in improving their hard-wired, control room annunciator systems as outlined by NUREG-0700.

  1. Use of probabilistic risk assessment in expert system usage for nuclear power plant safety

    SciTech Connect (OSTI)

    Uhrig, R.E.

    1987-01-01

    The introduction of probability risk assessments (PRA's) to nuclear power plants in the Rasmussen Report (WASH-1400) gave us a means of evaluating the risk to the public associated with the operation of nuclear power plants, at least on a relative basis. While the choice of the ''source term'' and methodology in a PRA significantly influence the absolute probability and the consequences of core melt, comparison of two PRA calculations for two configurations of the same plant, carried out on a consistent basis, can be readily identify the increase in risk associated with going from one configuration of a plant to another by removing components or systems from service. This ratio of core melt probabilities (assuming no recovery of failed systems) obtained from two PRA calculations for different configurations was the criterion (called ''risk factor'') chosen as a basis for making a decision in an expert system as to what mitigating action, if any, would be taken to avoid a trip situation from developing. PRISIM was developed by JBF Associates of Knoxville under the sponsorship of the NRC as a system for Resident Inspectors at nuclear power plants to provide them with a relative safety status of the plant under all configurations. PRISIM calculated the risk factor---the ration of core melt probabilities of the plant under the current configuration relative to the normal configuration with all systems functioning---using an algorithm that emulates the results of the original PRA. It also presents time and core melt (assuming no recovery of systems or components).

  2. Multi-reactor power system configurations for multimegawatt nuclear electric propulsion

    SciTech Connect (OSTI)

    George, J.A.

    1991-09-01

    A modular, multi-reactor power system and vehicle configuration for piloted nuclear electric propulsion (NEP) missions to Mars is presented. Such a design could provide enhanced system and mission reliability, allowing a comfortable safety margin for early manned flights, and would allow a range of piloted and cargo missions to be performed with a single power system design. Early use of common power modules for cargo missions would also provide progressive flight experience and validation of standardized systems for use in later piloted applications. System and mission analysis are presented to compare single and multi-reactor configurations for piloted Mars missions. A conceptual design for the Hydra modular multi-reactor NEP vehicle is presented.

  3. Reliability and optimization studies of nuclear and solar powered systems utilizing a Stirling engine for the space station 

    E-Print Network [OSTI]

    Schmitz, Paul Charles

    1990-01-01

    RELIABILITY AND OPTIMIZATION STUDIES OF NUCLEAR AND SOLAR POWERED SYSTEMS UTILIZING A STIRLING ENGINE FOR THE SPACE STATION A Thesis by PAUL CHARLES SCHMITZ Submitted to the Office of Graduate Studies of Texas A&M University in partial... fulfillment of the requirements for the degree of MASTER OF SCIENCE August 1990 Major Subject: Nuclear Engineering RELIABILITY AND OPTIMIZATION STUDIES OF NUCLEAR AND SOLAR POWERED SYSTEMS UTILIZING A STIRLING ENGINE FOR THE SPACE STATION A Thesis...

  4. Study on design of superconducting proton linac for accelerator driven subcritical nuclear power system

    E-Print Network [OSTI]

    Yu Qi; Xu Tao Guang

    2002-01-01

    As a prior option of the next generation of energy source, the accelerator driven subcritical nuclear power system (ADS) can use efficiently the uranium and thorium resource, transmute the high-level long-lived radioactive wastes and raise nuclear safety. The ADS accelerator should provide the proton beam with tens megawatts. The superconducting linac (SCL) is a good selection of ADS accelerator because of its high efficiency and low beam loss rate. It is constitute by a series of the superconducting accelerating cavities. The cavity geometry is determined by means of the electromagnetic field computation. The SCL main parameters are determined by the particle dynamics computation

  5. Nuclear Power and Its Fuel Cycle No technological system more dramatically illustrates the central themes of this book-

    E-Print Network [OSTI]

    Kammen, Daniel M.

    109 7 Nuclear Power and Its Fuel Cycle No technological system more dramatically illustrates public opinion toward nuclear technology. But probably the biggest obstacle to further nuclear the central themes of this book- the complexity of real world applications of technology and the pitfalls

  6. 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.

  7. Comparison of Different Internal Dosimetry Systems for Selected Radionuclides Important to Nuclear Power Production

    SciTech Connect (OSTI)

    Leggett, Richard Wayne; Eckerman, Keith F; Manger, Ryan P

    2013-08-01

    This report compares three different radiation dosimetry systems currently applied by various U.S. Federal agencies and dose estimates based on these three dosimetry systems for a set of radionuclides often identified in power reactor effluents. These dosimetry systems were developed and applied by the International Commission on Radiological Protection at different times over the past six decades. Two primary modes of intake of radionuclides are addressed: ingestion in drinking water and inhalation. Estimated doses to individual organs and to the whole body based on each dosimetry system are compared for each of four age groups: infant, child, teenager, and adult. Substantial differences between dosimetry systems in estimated dose per unit intake are found for some individual radionuclides, but differences in estimated dose per unit intake generally are modest for mixtures of radionuclides typically found in nuclear power plant effluents.

  8. Climate Change, Nuclear Power and Nuclear

    E-Print Network [OSTI]

    Climate Change, Nuclear Power and Nuclear Proliferation: Magnitude Matters Rob Goldston MIT IAP biomass wind hydro coal CCS coal nat gas CCS nat gas nuclear Gen IV nuclear Gen III nuclear Gen II 5-1 Electricity Generation: CCS and Nuclear Power Technology Options Available Global Electricity Generation WRE

  9. The effects of solar-geomagnetically induced currents on electrical systems in nuclear power stations

    SciTech Connect (OSTI)

    Subudhi, M. [Brookhaven National Lab., Upton, NY (United States)] [Brookhaven National Lab., Upton, NY (United States); Carroll, D.P. [Florida Univ., Gainesville, FL (United States)] [Florida Univ., Gainesville, FL (United States); Kasturi, S. [MOS, Inc., Melville, NY (United States)] [MOS, Inc., Melville, NY (United States)

    1994-01-01

    This report presents the results of a study to evaluate the potential effects of geomagnetically induced currents (GICs) caused by the solar disturbances on the in-plant electrical distribution system and equipment in nuclear power stations. The plant-specific electrical distribution system for a typical nuclear plant is modeled using the ElectroMagnetic Transient Program (EMTP). The computer model simulates online equipment and loads from the station transformer in the switchyard of the power station to the safety-buses at 120 volts to which all electronic devices are connected for plant monitoring. The analytical model of the plant`s electrical distribution system is studied to identify the transient effects caused by the half-cycle saturation of the station transformers due to GIC. This study provides results of the voltage harmonics levels that have been noted at various electrical buses inside the plant. The emergency circuits appear to be more susceptible to high harmonics due to the normally light load conditions. In addition to steady-state analysis, this model was further analyzed simulating various plant transient conditions (e.g., loss of load or large motor start-up) occurring during GIC events. Detail models of the plant`s protective relaying system employed in bus transfer application were included in this model to study the effects of the harmonic distortion of the voltage input. Potential harmonic effects on the uniterruptable power system (UPS) are qualitatively discussed as well.

  10. Definition, Expansion and Screening of Architectures for Planetary Exploration Class Nuclear Electric Propulsion and Power Systems

    E-Print Network [OSTI]

    Definition, Expansion and Screening of Architectures for Planetary Exploration Class Nuclear, expansion and screening of Nuclear Electric Propulsion and Power concepts capable of achieving planetary left blank 2 #12;Definition, Expansion and Screening of Architectures for Planetary Exploration Class

  11. 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.

  12. Development of a hybrid intelligent system for on-line real-time monitoring of nuclear power plant operations

    E-Print Network [OSTI]

    Yildiz, Bilge, 1976-

    2003-01-01

    A nuclear power plant (NPP) has an intricate operational domain involving systems, structures and components (SSCs) that vary in scale and complexity. Many of the large scale SSCs contribute to the lost availability in the ...

  13. 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.

  14. Brayton power conversion system parametric design modelling for nuclear electric propulsion. Final report

    SciTech Connect (OSTI)

    Ashe, T.L.; Otting, W.D.

    1993-11-01

    The parametrically based closed Brayton cycle (CBC) computer design model was developed for inclusion into the NASA LeRC overall Nuclear Electric Propulsion (NEP) end-to-end systems model. The code is intended to provide greater depth to the NEP system modeling which is required to more accurately predict the impact of specific technology on system performance. The CBC model is parametrically based to allow for conducting detailed optimization studies and to provide for easy integration into an overall optimizer driver routine. The power conversion model includes the modeling of the turbines, alternators, compressors, ducting, and heat exchangers (hot-side heat exchanger and recuperator). The code predicts performance to significant detail. The system characteristics determined include estimates of mass, efficiency, and the characteristic dimensions of the major power conversion system components. These characteristics are parametrically modeled as a function of input parameters such as the aerodynamic configuration (axial or radial), turbine inlet temperature, cycle temperature ratio, power level, lifetime, materials, and redundancy.

  15. EEE 564 Interdisciplinary Nuclear Power Operations (3 hrs) Catalog Description: Nuclear power plant systems. Study of the interrelationship and propagation of

    E-Print Network [OSTI]

    Zhang, Junshan

    EEE 564 Interdisciplinary Nuclear Power Operations (3 hrs) Catalog Description: Nuclear power plant (Generation II) pressurized water reactors (PWRs) and boiling water reactors (BWRs) as well as the new Electric's advanced boiling water reactor (ABWR) and economic simplified boiling water reactor (ESBWR

  16. 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.

  17. Working Group Report on - Space Nuclear Power Systems and Nuclear Waste

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power AdministrationRobust,Field-effectWorking WithTelecentricNCubictheThepresented in1: Model or

  18. CONSTRUCTION OF NUCLEAR POWER PLANTS

    E-Print Network [OSTI]

    CONSTRUCTION OF NUCLEAR POWER PLANTS A Workshop on "NUCLEAR ENERGY RENAISSANCE" Addressing OF ST. LUCIE-2 at FLORIDA POWER & LIGHT COMPANY · Robert E. Uhrig 1974-1986 ­ Vice President, Nuclear IN CONSTRUCTION OF ST. LUCIE-2 #12;LESSONS LEARNED FROM St. Lucie-2 NUCLEAR POWER PLANTS CAN BE BUILT

  19. Iowa Nuclear Profile - Power Plants

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

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

  20. Illinois Nuclear Profile - Power Plants

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

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

  1. Arkansas 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...

  2. Nebraska Nuclear Profile - Power Plants

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

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

  3. Maryland 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...

  4. Missouri 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...

  5. Virginia Nuclear Profile - Power Plants

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

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

  6. Arizona Nuclear Profile - Power Plants

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

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

  7. Florida Nuclear Profile - Power Plants

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

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

  8. Ohio Nuclear Profile - Power Plants

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

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

  9. Michigan Nuclear Profile - Power Plants

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

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

  10. Alabama Nuclear Profile - Power Plants

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

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

  11. 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...

  12. Massachusetts 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...

  13. Georgia Nuclear Profile - Power Plants

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

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

  14. Vermont Nuclear Profile - Power Plants

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

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

  15. Kansas Nuclear Profile - Power Plants

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

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

  16. 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...

  17. Minnesota Nuclear Profile - Power Plants

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

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

  18. Wisconsin Nuclear Profile - Power Plants

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

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

  19. Gas production and behavior in the coolant of the SP-100 Space Nuclear Power System

    SciTech Connect (OSTI)

    McGhee, J.M.

    1989-08-01

    The radiologic generation and subsequent behavior of helium gas in the lithium coolant of SP-100 class space nuclear power reactors was investigated analytically in a two part study. Part One of the study consisted of a calculation of coolant radiologic helium gas production rates in a SP-100 class reactor using the discrete ordinates code TWODANT. Cross sections were developed from ENDF/B-V data via the MATXS6s master cross section library. Cross sections were self shielded assuming one homogeneous core region, and doppler broadened to 1300 K using the cross section preparation code TRANSX. Calculations were performed using an S{sub 4}/P{sub 1} approximation and 80 neutron energy groups. Part Two of the study consisted of a theoretical investigation into the behavior of helium gas in the primary loop of lithium cooled space reactors. The SP-100 space power system was used as a representative of such a system. Topics investigated included: (1) heterogeneous and homogeneous nucleation; (2) bubble growth/collapse by diffusion, mechanical temperature/pressure effects, and coalescence; and, (3) the effects on bubble distribution of microgravity, magnetic fields, and inertially induced buoyancy. 104 refs., 78 figs., 28 tabs.

  20. Impacts of a nominal nuclear electromagnetic pulse on electric power systems

    SciTech Connect (OSTI)

    Kruse, V.J.; Nickel, D.L.; Bonk, J.J.; Taylor, E.R. Jr. (ABB Power Systems, Inc., Pittsburgh, PA (USA))

    1991-04-01

    A high-altitude nuclear detonation several hundred kilometers above the central United States will subject much of the nation to an electromagnetic pulse (EMP) consisting of intense steep-front short- duration transient electromagnetic fields followed by a geomagnetic disturbance with a duration of tens of seconds. Since 1983, the Department of Energy has been actively pursuing a research program to assess the potential impacts of one or more EMP events on the nation's electric energy supply. A nominal EMP environmental suitable for assessing geographically large systems has been used to provide an indication of EMP impacts on electric power systems. It was found that a single high-altitude burst, which significantly disturbs the geomagnetic field, could cause significant load and generation loss, but permanent damage would be isolated. Multiple bursts would increase the disturbance. Nevertheless, based on the effects of a nominal EMP environment, a long-term blackout is not expected since major components such as power transformers are not likely to be damaged. 60 refs., 10 figs., 8 tabs.

  1. Impacts of a nominal nuclear electromagnetic pulse on electric power systems; A probabilistic approach

    SciTech Connect (OSTI)

    Kruse, V.J.; Nickel, D.L.; Taylor, E.R. Jr. (ABB Power Systems Inc., Pittsburgh, PA (US)); Barnes, P.R. (Oak Ridge National Lab., TN (United States))

    1991-07-01

    This paper reports on a high-altitude nuclear detonation several hundred kilometers above the central United States that will subject much of the nation to an electromagnetic pulse (EMP) consisting of intense steep-front short-duration transient electromagnetic fields followed by a geomagnetic disturbance with a duration of tens of seconds. Since 1983, the Department of energy has been actively pursuing a research program to assess the potential impacts of one or more EMP events on the nation's electric energy supply. A nominal EMP environment suitable for assessing geographically large systems has been used to provide an indication of EMP impacts on electric power systems. It was found that a single high-altitude burst, which significantly disturbs the geomagnetic field, could cause significant load and generation loss, but permanent damage would be isolated. Multiple bursts would increase the disturbance. Nevertheless, based on the effects of a nominal EMP environment, a long term blackout is not expected since major components such as power transformers are not likely to be damaged.

  2. Generation IV Nuclear Energy Systems ...

    E-Print Network [OSTI]

    Kemner, Ken

    Generation IV Nuclear Energy Systems ... The U.S. Department of Energy's Office of Nuclear Energy enhance safety and security, and develop nuclear power as an energy source for industrial applications Information ... U.S. Department of Energy www.energy.gov DOE Office of Nuclear Energy www.nuclear

  3. Sandia Energy - Nuclear Energy Systems Laboratory (NESL) / Brayton...

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

    Nuclear Energy Systems Laboratory (NESL) Brayton Lab Home Stationary Power Nuclear Fuel Cycle Advanced Nuclear Energy Nuclear Energy Systems Laboratory (NESL) Brayton Lab...

  4. 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...

  5. 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.

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

    DOE Patents [OSTI]

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

    1995-01-01

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

  7. Testing, licensing, and code requirements for seismic isolation systems (for nuclear power plants)

    SciTech Connect (OSTI)

    Seidensticker, R.W.

    1987-01-01

    The use of seismic isolation as an earthquake hazard mitigation strategy for nuclear reactor power plants is rapidly receiving interest throughout the world. Seismic isolation has already been used on at least two French PWR plants, was to have been used for plants to be built in Iran, and is under serious consideration for advanced LMR plants (in the US, UK, France, and Japan). In addition, there is a growing use of seismic isolation throughout the world for other critical facilities such as hospitals, emergency facilities, buildings with very high-cost equipment (e.g., computers) and as a strategy to reduce loss of life and expensive equipment in earthquakes. Such a design approach is in complete contrast to the conventional seismic design strategy in which the structure and components are provided with sufficient strength and ductility to resist the earthquake forces and to prevent structural collapses or failure. The use of seismic isolation for nuclear plants can, therefore, be expected to be a significant licensing issue. For isolation, the licensing process must shift away in large measure from the superstructure and concentrate on the behavior of the seismic isolation system. This paper is not intended to promote the advantages of seismic isolation system, but to explore in some detail those technical issues which must be satisfactorily addressed to achieve full licensability of the use of seismic isolation as a viable, attractive and economical alternative to current traditional design approaches. Special problems and topics associated with testing and codes and standards development are addressed. A positive program for approach or strategy to secure licensing is presented.

  8. 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.

  9. Power system

    DOE Patents [OSTI]

    Hickam, Christopher Dale (Glasford, IL)

    2008-03-18

    A power system includes a prime mover, a transmission, and a fluid coupler having a selectively engageable lockup clutch. The fluid coupler may be drivingly connected between the prime mover and the transmission. Additionally, the power system may include a motor/generator drivingly connected to at least one of the prime mover and the transmission. The power-system may also include power-system controls configured to execute a control method. The control method may include selecting one of a plurality of modes of operation of the power system. Additionally, the control method may include controlling the operating state of the lockup clutch dependent upon the mode of operation selected. The control method may also include controlling the operating state of the motor/generator dependent upon the mode of operation selected.

  10. 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...

  11. 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;...

  12. 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;...

  13. Louisiana Nuclear Profile - Power Plants

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

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

  14. 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.

  15. Nuclear Power Plant Design Project

    E-Print Network [OSTI]

    Nuclear Power Plant Design Project A Response to the Environmental and Economic Challenge Of Global) .................................................................... 14 4.4 High Temperature Gas Reactor

  16. Washington Nuclear Profile - Power Plants

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

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

  17. Mississippi Nuclear Profile - Power Plants

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

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

  18. Connecticut Nuclear Profile - Power Plants

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

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

  19. Pennsylvania Nuclear Profile - Power Plants

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

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

  20. California Nuclear Profile - Power Plants

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

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

  1. Preliminary systems-interaction results from the Digraph Matrix Analysis of the Watts Bar Nuclear Power Plant safety-injection systems

    SciTech Connect (OSTI)

    Sacks, I.J.; Ashmore, B.C.; Champney, J.M.; Alesso, H.P.

    1983-06-01

    This report provides preliminary results generated by a Digraph Matrix Analysis (DMA) for a Systems Interaction analysis performed on the Safety Injection System of the Tennessee Valley Authority Watts Bar Nuclear Power Plant. An overview of DMA is provided along with a brief description of the computer codes used in DMA.

  2. 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.

  3. 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.

  4. 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.

  5. 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.

  6. The Decline and Death of Nuclear Power

    E-Print Network [OSTI]

    Melville, Jonathan

    2013-01-01

    The Economist (2012). Nuclear power: The 30-year itch. TheDramatic fall in new nuclear power stations after Fukushima.environment/2012/mar/08/fall-nuclear-power- stations-

  7. The Decline and Death of Nuclear Power

    E-Print Network [OSTI]

    Melville, Jonathan

    2013-01-01

    2012). NRC: Nuclear Security and Safeguards.nrc.gov.in nuclear reactor maintenance and security. However, when aof nuclear power plants, as well as physical security to

  8. The Decline and Death of Nuclear Power

    E-Print Network [OSTI]

    Melville, Jonathan

    2013-01-01

    Y. , & Kitazawa, K. (2012). Fukushima in review: A complexin new nuclear power stations after Fukushima. The Guardian.nuclear-power- stations-fukushima Hvistendahl, M. (2007,

  9. Can Nuclear Power Be Flexible? Laurent POURET + William J. NUTTALL

    E-Print Network [OSTI]

    Aickelin, Uwe

    1 Can Nuclear Power Be Flexible? Laurent POURET + William J. NUTTALL Judge Business School the issue of whether nuclear power can play a flexible role within an electricity system. It does not deal with the issue of whether nuclear power should play such a role, but it does examine why in most cases it does

  10. Long-Term Planning for Nuclear Energy Systems Under Deep Uncertainty

    E-Print Network [OSTI]

    Kim, Lance Kyungwoo

    2011-01-01

    of early nuclear power development . . . . . . . . . . . . .Quirk. The Turnkey Era in Nuclear Power. Land Economics, 56(Information System. Nuclear Power Plants Information:

  11. NUCLEAR POWER PLANT Nuclear power plants have safety and security procedures in place and

    E-Print Network [OSTI]

    NUCLEAR POWER PLANT ACCIDENTS Nuclear power plants have safety and security procedures in place and are closely monitored by the Nuclear Regulatory Commission (NRC). An accident at a nuclear power plant could of nuclear power plant accidents? Radioactive materials in the plume from the nuclear power plant can settle

  12. The Decline and Death of Nuclear Power

    E-Print Network [OSTI]

    Melville, Jonathan

    2013-01-01

    fall in new nuclear power stations after Fukushima. Thenuclear-power- stations-fukushima Hvistendahl, M. (2007,

  13. Nuclear Power Trends Energy Economics and Sustainability

    E-Print Network [OSTI]

    Nuclear Power Trends Energy Economics and Sustainability L. H. Tsoukalas Purdue University Nuclear Nuclear Today · 439 nuclear power reactors (31 countries) · Over 12,000 years of operating experience · Nuclear reactors supply 16% of the world's electricity as base-load power (372,000 MWe of total capacity

  14. Future Prospects for Nuclear Power after Fukushima

    E-Print Network [OSTI]

    Goldberg, Bennett

    Future Prospects for Nuclear Power after Fukushima Nuclear is a highintensity energy source at the FukushimaDaiichi nuclear power plant in Japan has changed the perception of nuclear as a safe energy source as the next generation of Light Water Reactors. We will also discuss the future prospects of nuclear power

  15. 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.

  16. The sequence coding and search system: An approach for constructing and analyzing event sequences at commercial nuclear power plants

    SciTech Connect (OSTI)

    Mays, G.T.

    1989-04-01

    The US Nuclear Regulatory Commission (NRC) has recognized the importance of the collection, assessment, and feedstock of operating experience data from commercial nuclear power plants and has centralized these activities in the Office for Analysis and Evaluation of Operational Data (AEOD). Such data is essential for performing safety and reliability analyses, especially analyses of trends and patterns to identify undesirable changes in plant performance at the earliest opportunity to implement corrective measures to preclude the occurrences of a more serious event. One of NRC's principal tools for collecting and evaluating operating experience data is the Sequence Coding and Search System (SCSS). The SCSS consists of a methodology for structuring event sequences and the requisite computer system to store and search the data. The source information for SCSS is the Licensee Event Report (LER), which is a legally required document. This paper describes the objective SCSS, the information it contains, and the format and approach for constructuring SCSS event sequences. Examples are presented demonstrating the use SCSS to support the analysis of LER data. The SCSS contains over 30,000 LERs describing events from 1980 through the present. Insights gained from working with a complex data system from the initial developmental stage to the point of a mature operating system are highlighted.

  17. Nuclear Systems Modeling, Simulation & Validation | Nuclear Science...

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

    Research Areas Fuel Cycle Science & Technology Fusion Nuclear Science Isotope Development and Production Nuclear Security Science & Technology Nuclear Systems Modeling, Simulation...

  18. Nuclear information systems

    SciTech Connect (OSTI)

    Cowley, R.L. (Enercon Services, Inc., Broken Arrow, OK (US))

    1989-01-01

    This paper reviews options, challenges, and opportunities facing the nuclear industry as it strives to achieve the most effective use of the available resources in support of managing the nuclear power plant business.

  19. Nuclear power: key to man's extraterrestrial civilization

    SciTech Connect (OSTI)

    Angelo, J.A. Jr.; Buden, D.

    1982-01-01

    The start of the Third Millennium will be highlighted by the establishment of man's extraterrestrial civilization with three technical cornerstones leading to the off-planet expansion of the human resource base. These are (1) the availability of compact energy sources for power and propulsion, (2) the creation of permanent manned habitats in space, and (3) the ability to process materials anywhere in the Solar System. In the 1990s and beyond, nuclear reactors could represent the prime source of both space power and propulsion. The manned and unmanned space missions of tomorrow will demand first kilowatt and then megawatt levels of power. Various nuclear power plant technologies will be discussed, with emphasis on derivatives from the nuclear rocket technology.

  20. CONTROL OF POPULATION DENSITIES SURROUNDING NUCLEAR POWER PLANTS. VOLUME 5 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Nero, jA.V.

    2010-01-01

    the actual risk presented by nuclear power plants. Dependingyears): Average risk from a nuclear power plant during itssocietal risks from a system of 100 nuclear power plants due

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

    SciTech Connect (OSTI)

    Golay, Michael (MIT) [MIT

    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.

  2. Intelligent Component Monitoring for Nuclear Power Plants

    SciTech Connect (OSTI)

    Lefteri Tsoukalas

    2010-07-30

    Reliability and economy are two major concerns for a nuclear power generation system. Next generation nuclear power reactors are being developed to be more reliable and economic. An effective and efficient surveillance system can generously contribute toward this goal. Recent progress in computer systems and computational tools has made it necessary and possible to upgrade current surveillance/monitoring strategy for better performance. For example, intelligent computing techniques can be applied to develop algorithm that help people better understand the information collected from sensors and thus reduce human error to a new low level. Incidents incurred from human error in nuclear industry are not rare and have been proven costly. The goal of this project is to develop and test an intelligent prognostics methodology for predicting aging effects impacting long-term performance of nuclear components and systems. The approach is particularly suitable for predicting the performance of nuclear reactor systems which have low failure probabilities (e.g., less than 10-6 year-). Such components and systems are often perceived as peripheral to the reactor and are left somewhat unattended. That is, even when inspected, if they are not perceived to be causing some immediate problem, they may not be paid due attention. Attention to such systems normally involves long term monitoring and possibly reasoning with multiple features and evidence, requirements that are not best suited for humans.

  3. 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.

  4. Export Control Guide: Loose Parts Monitoring Systems for Nuclear Power Plants

    SciTech Connect (OSTI)

    Langenberg, Donald W.

    2012-12-01

    This report describes a typical LPMS, emphasizing its application to the RCS of a modern NPP. The report also examines the versatility of AE monitoring technology by describing several nuclear applications other than loose parts monitoring, as well as some non-nuclear applications. In addition, LPMS implementation requirements are outlined, and LPMS suppliers are identified. Finally, U.S. export controls applicable to LPMSs are discussed.

  5. Fusion & Materials for Nuclear Systems Division | ornl.gov

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

    Fusion & Materials for Nuclear Systems SHARE Fusion & Materials for Nuclear Systems Division Fusion holds the promise of significant power with no carbon emissions and minimal...

  6. 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.

  7. Safer nuclear power

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power AdministrationRobust, High-Throughput Analysis of Protein1-0845*RV6STATDecember 2,Requirements OSafer

  8. 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.

  9. QUARTERLY NUCLEAR POWER DEPLOYMENT SUMMARY JULY 2015

    Energy Savers [EERE]

    purposes. The Nuclear Regulatory Commission has voted to grant the Director of Nuclear Reactor Regulation authority to issue a full power operating license to Tennessee...

  10. New Jersey Nuclear Profile - Power Plants

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

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

  11. New York Nuclear Profile - Power Plants

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

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

  12. North Carolina Nuclear Profile - Power Plants

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

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

  13. New Hampshire Nuclear Profile - Power Plants

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

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

  14. 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.

  15. Organizational learning at nuclear power plants

    E-Print Network [OSTI]

    Carroll, John S.

    1991-01-01

    The Nuclear Power Plant Advisory Panel on Organizational Learning provides channels of communications between the management and organization research projects of the MIT International Program for Enhanced Nuclear Power ...

  16. 24. Nuclear? Nuclear power comes in two flavours

    E-Print Network [OSTI]

    Ernst, Damien

    24. Nuclear? Nuclear power comes in two flavours: 1. Nuclear fission. Split up heavy nuclei into medium-sized nu- clei, thereby releasing energy. 2. Nuclear fusion. Fuse light nuclei into medium-sized nuclei, thereby releasing energy. 1 #12;Nuclear energy available per atom is roughly one mil- lion times

  17. The Decline and Death of Nuclear Power

    E-Print Network [OSTI]

    Melville, Jonathan

    2013-01-01

    hints of a burgeoning “energy crisis” (Rosa & Dunlap, 1994).consciousness for years. ” energy crisis. Nuclear power is

  18. nuclear power Update of the mit 2003

    E-Print Network [OSTI]

    Reuter, Martin

    #12;Future of nuclear power Update of the mit 2003 PROFESSOR JOHN M.DEUTCH Institute Professor of Technology. All rights reserved. #12;Update of the MIT 2003 Future of Nuclear Power Study 3 In 2003 a group of MIT faculty issued a study on The Future of Nuclear Power.1 The study was motivated by growing concern

  19. NUCLEAR POWER IN CALIFORNIA: 2007 STATUS REPORT

    E-Print Network [OSTI]

    NUCLEAR POWER IN CALIFORNIA: 2007 STATUS REPORT Prepared For: California Energy Commission Prepared;Abstract This consultant report examines how nuclear power issues have evolved since publication of the consultant report, Nuclear Power in California: Status Report, which was prepared for the 2005 IEPR

  20. 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.

  1. Preventing power outages Power system contingency analysis on the GPU

    E-Print Network [OSTI]

    Vuik, Kees

    problem. Moreover, the power system has to keep functioning properly even when a transmission line failsPreventing power outages Power system contingency analysis on the GPU To provide electricity generators, nuclear power plants, wind turbines, etc.) and a network of lines and cables to transmit

  2. Materials challenges for nuclear systems

    SciTech Connect (OSTI)

    Allen, Todd; Busby, Jeremy; Meyer, Mitch; Petti, David

    2010-11-26

    The safe and economical operation of any nuclear power system relies to a great extent, on the success of the fuel and the materials of construction. During the lifetime of a nuclear power system which currently can be as long as 60 years, the materials are subject to high temperature, a corrosive environment, and damage from high-energy particles released during fission. The fuel which provides the power for the reactor has a much shorter life but is subject to the same types of harsh environments. This article reviews the environments in which fuels and materials from current and proposed nuclear systems operate and then describes how the creation of the Advanced Test Reactor National Scientific User Facility is allowing researchers from across the U.S. to test their ideas for improved fuels and materials.

  3. Development and testing of an integrated signal validation system for nuclear power plants

    SciTech Connect (OSTI)

    Upadhyaya, B.R.; Kerlin, T.W.; Gaudio, P.J. Jr.

    1989-09-01

    Since the incident at Three Mile Island unit 2, computerized plant status display, implementation of human factors in control room design, and plant monitoring based on expert system technology have seen a tremendous growth. One such proposed operator assist device is a plant signal validation system. This system is used to check the consistency of redundant measurements (sensors) of selected process variables, estimate their expect values from plant-wide data, and detect, isolate and characterize the type of anomaly in the instrument channel outputs. In large process control systems signals from several hundred instrument channels are routed via data highways to control systems, protection (safety) systems and plant monitoring systems. The need of automated signal validation is necessary because of the large amount of information available, and as a result the operator's inability to validate information from many diverse sources. This is also useful for improved plant control (minimize challenges on control systems), minimizing plant downtime, and for predictive maintenance advising. 107 refs., 56 figs., 6 tabs.

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

    DOE Patents [OSTI]

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

    1993-01-01

    A nuclear reactor steam generator includes a reactor vessel for heating water and a steam generator with a pump casing at the lowest point on the steam generator. A cold-leg pipe extends horizontally between the steam generator and the reactor vessel to return water from the steam generator to the reactor vessel. The bottom of the cold-leg pipe is at a first height above the bottom of the reactor vessel. A hot-leg pipe with one end connected to the steam generator and a second end connected to the reactor vessel has a first pipe region extending downwardly from the steam generator to a location between the steam generator and the reactor vessel at which a bottom of the hot-leg pipe is at a second height above the bottom of the reactor vessel. A second region extends from that location in a horizontal direction at the second height to the point at which the hot-leg pipe connects to the reactor vessel. A pump is attached to the casing at a location below the first and second heights and returns water from the steam generator to the reactor vessel over the cold-leg. The first height is greater than the second height and the bottom of the steam generator is at a height above the bottom of the reactor vessel that is greater than the first and second heights. A residual heat recovery pump is below the hot-leg and has an inlet line from the hot-leg that slopes down continuously to the pump inlet.

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

    DOE Patents [OSTI]

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

    1993-11-16

    A nuclear reactor steam generator includes a reactor vessel for heating water and a steam generator with a pump casing at the lowest point on the steam generator. A cold-leg pipe extends horizontally between the steam generator and the reactor vessel to return water from the steam generator to the reactor vessel. The bottom of the cold-leg pipe is at a first height above the bottom of the reactor vessel. A hot-leg pipe with one end connected to the steam generator and a second end connected to the reactor vessel has a first pipe region extending downwardly from the steam generator to a location between the steam generator and the reactor vessel at which a bottom of the hot-leg pipe is at a second height above the bottom of the reactor vessel. A second region extends from that location in a horizontal direction at the second height to the point at which the hot-leg pipe connects to the reactor vessel. A pump is attached to the casing at a location below the first and second heights and returns water from the steam generator to the reactor vessel over the cold-leg. The first height is greater than the second height and the bottom of the steam generator is at a height above the bottom of the reactor vessel that is greater than the first and second heights. A residual heat recovery pump is below the hot-leg and has an inlet line from the hot-leg that slopes down continuously to the pump inlet. 2 figures.

  6. Power management system

    DOE Patents [OSTI]

    Algrain, Marcelo C. (Peoria, IL); Johnson, Kris W. (Washington, IL); Akasam, Sivaprasad (Peoria, IL); Hoff, Brian D. (East Peoria, IL)

    2007-10-02

    A method of managing power resources for an electrical system of a vehicle may include identifying enabled power sources from among a plurality of power sources in electrical communication with the electrical system and calculating a threshold power value for the enabled power sources. A total power load placed on the electrical system by one or more power consumers may be measured. If the total power load exceeds the threshold power value, then a determination may be made as to whether one or more additional power sources is available from among the plurality of power sources. At least one of the one or more additional power sources may be enabled, if available.

  7. Moratorium on Construction of Nuclear Power Facilities (Connecticut...

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

    Moratorium on Construction of Nuclear Power Facilities (Connecticut) Moratorium on Construction of Nuclear Power Facilities (Connecticut) < Back Eligibility Agricultural Commercial...

  8. Implementation of the MPC and A Operations Monitoring (MOM) System at IRT-T FSRE Nuclear Power Institute (NPI)

    SciTech Connect (OSTI)

    Sitdikov,I.; Zenkov, A.; Tsibulnikov, Y.; Duncan, C.; Brownell, L.; Pratt, W.T.; Carbonaro, J.; White, R.M.; Coffing, J.A.

    2008-07-13

    The Material Protection, Control and Accounting (MPC&A) Program has been working since 1994 with nuclear sites in Russia to upgrade the physical protection (PP) and material control and accounting (MC&A) functions at facilities containing weapons usable nuclear material. In early 2001, the MPC&A program initiated the MPC&A Operations Monitoring (MOM) Project to monitor facilities where MPC&A upgrades have been installed to provide increased confidence that personnel are present and vigilant, provide confidence that security procedures are being properly performed and provide additional assurance that nuclear materials have not been stolen. The MOM project began as a pilot project at the Moscow State Engineering Physics Institute (MEPhI) and a MOM system was successfully installed in October 2001. Following the success of the MEPhI pilot project, the MPC&A Program expanded the installation of MOM systems to several other Russian facilities, including the Nuclear Physics Institute (NPI) in Tomsk. The MOM system was made operational at NPI in October 2004. This paper is focused on the experience gained from operation of this system and the objectives of the MOM system. The paper also describes how the MOM system is used at NPI and, in particular, how the data is analyzed. Finally, potential expansion of the MOM system at NPI is described.

  9. Use of fuel cells for improving on-site emergency power availability and reliability ad nuclear power plants

    E-Print Network [OSTI]

    Akkaynak, Derya

    2005-01-01

    To assure safe shutdown of a nuclear power plant, there must always be reliable means of decay heat removal provided, in last resort, by an Emergency Core Cooling System (ECCS). Currently the majority of nuclear power ...

  10. 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...

  11. 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...

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

    SciTech Connect (OSTI)

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

    2014-07-01

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

  13. Materials challenges for nuclear systems

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

    Allen, Todd; Busby, Jeremy; Meyer, Mitch; Petti, David

    2010-11-26

    The safe and economical operation of any nuclear power system relies to a great extent, on the success of the fuel and the materials of construction. During the lifetime of a nuclear power system which currently can be as long as 60 years, the materials are subject to high temperature, a corrosive environment, and damage from high-energy particles released during fission. The fuel which provides the power for the reactor has a much shorter life but is subject to the same types of harsh environments. This article reviews the environments in which fuels and materials from current and proposed nuclearmore »systems operate and then describes how the creation of the Advanced Test Reactor National Scientific User Facility is allowing researchers from across the U.S. to test their ideas for improved fuels and materials.« less

  14. 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.

  15. South Carolina Nuclear Profile - Power Plants

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

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

  16. The Decline and Death of Nuclear Power

    E-Print Network [OSTI]

    Melville, Jonathan

    2013-01-01

    1. The International Nuclear Safety Advisory Group (Safetystrict safety regulations regarding containment of nuclearnuclear power plant poses is greater than any other source of energy, and no safety

  17. Physical features of small disperse coal dust fraction transportation and structurization processes in iodine air filters of absorption type in ventilation systems at nuclear power plants

    E-Print Network [OSTI]

    Ledenyov, Oleg P; Poltinin, P Ya; Fedorova, L I

    2012-01-01

    The research on the physical features of transportation and structurization processes by the air-dust aerosol in the granular filtering medium with the cylindrical coal adsorbent granules in an air filter of the adsorption type in the heating ventilation and cooling (HVAC) system at the nuclear power plant is completed. The physical origins of the coal dust masses distribution along the absorber with the granular filtering medium with the cylindrical coal granules during the air-dust aerosol intake process in the near the surface layer of absorber are researched. The quantitative technical characteristics of air filtering elements, which have to be considered during the optimization of air filters designs for the application in the ventilation systems at the nuclear power plants, are obtained.

  18. Solar powered desalination system

    E-Print Network [OSTI]

    Mateo, Tiffany Alisa

    2011-01-01

    done using photovoltaic systems or by a photoelectrochemicalprocess. Of course, photovoltaic systems convert sunlightwill be powered by the photovoltaic system. Also, a typical

  19. International Atomic Energy Agency specialists meeting on experience in ageing, maintenance, and modernization of instrumentation and control systems for improving nuclear power plant availability

    SciTech Connect (OSTI)

    Not Available

    1993-10-01

    This report presents the proceedings of the Specialist`s Meeting on Experience in Aging, Maintenance and Modernization of Instrumentation and Control Systems for Improving Nuclear Power Plant Availability that was held at the Ramada Inn in Rockville, Maryland on May 5--7, 1993. The Meeting was presented in cooperation with the Electric Power Research Institute, Oak Ridge National Laboratory and the International Atomic Energy Agency. There were approximately 65 participants from 13 countries at the Meeting. Individual reports have been cataloged separately.

  20. 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.

  1. Nuclear power expansion: thinking about uncertainty

    SciTech Connect (OSTI)

    Holt, Lynne; Sotkiewicz, Paul; Berg, Sanford

    2010-06-15

    Nuclear power is one of many options available to achieve reduced carbon dioxide emissions. The real-option value model can help explain the uncertainties facing prospective nuclear plant developers in developing mitigation strategies for the development, construction, and operation of new nuclear plants. (author)

  2. Nuclear Power in France Beyond the Myth

    E-Print Network [OSTI]

    Laughlin, Robert B.

    Nuclear Power in France Beyond the Myth By Mycle Schneider International Consultant on Energy and Nuclear Policy Commissioned by the Greens-EFA Group in the European Parliament V5 #12;Note: The present international energy nuclear policy consultant. Between 1983 and April 2003 Mycle Schneider was executive

  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. Update on the Cost of Nuclear Power

    E-Print Network [OSTI]

    Parsons, John E.

    2009-01-01

    We update the cost of nuclear power as calculated in the MIT (2003) Future of Nuclear Power study. Our main focus is on the changing cost of construction of new plants. The MIT (2003) study provided useful data on the cost ...

  5. Nuclear Power PROS -`No' greenhouse gas emissions

    E-Print Network [OSTI]

    Toohey, Darin W.

    Nuclear Power PROS -`No' greenhouse gas emissions -Fuel is cheep -High energy density (1 ton U = 16 abundant elements found in natural crustal rocks) Nuclear Power CONS -High capital cost due to meeting,000 tons of coal to produce same amount of electricity) -Natural abundance of U (48th among the most

  6. Identification of good practices in the operation of nuclear power plants

    E-Print Network [OSTI]

    Chen, Haibo, 1975-

    2005-01-01

    This work developed an approach to diagnose problems and identify good practices in the operation of nuclear power plants using the system dynamics technique. The research began with construction of the ORSIM (Nuclear Power ...

  7. Nuclear reactor power for an electrically powered orbital transfer vehicle

    SciTech Connect (OSTI)

    Jaffe, L.; Beatty, R.; Bhandari, P.; Chow, E.; Deininger, W.; Ewell, R.; Fujita, T.; Grossman, M.; Kia, T.; Nesmith, B.

    1987-01-01

    To help determine the systems requirements for a 300-kWe space nuclear reactor power system, a mission and spacecraft have been examined which utilize electric propulsion and this nuclear reactor power for multiple transfers of cargo between low Earth orbit (LEO) and geosynchronous Earth orbit (GEO). A propulsion system employing ion thrusters and xenon propellant was selected. Propellant and thrusters are replaced after each sortie to GEO. The mass of the Orbital Transfer Vehicle (OTV), empty and dry, is 11,000 kg; nominal propellant load is 5000 kg. The OTV operates between a circular orbit at 925 km altitude, 28.5 deg inclination, and GEO. Cargo is brought to the OTV by Shuttle and an Orbital Maneuvering Vehicle (OMV); the OTV then takes it to GEO. The OTV can also bring cargo back from GEO, for transfer by OMV to the Shuttle. OTV propellant is resupplied and the ion thrusters are replaced by the OMV before each trip to GEO. At the end of mission life, the OTV's electric propulsion is used to place it in a heliocentric orbit so that the reactor will not return to Earth. The nominal cargo capability to GEO is 6000 kg with a transit time of 120 days; 1350 kg can be transferred in 90 days, and 14,300 kg in 240 days. These capabilities can be considerably increased by using separate Shuttle launches to bring up propellant and cargo, or by changing to mercury propellant.

  8. Nuclear medicine imaging system

    DOE Patents [OSTI]

    Bennett, G.W.; Brill, A.B.; Bizais, Y.J.C.; Rowe, R.W.; Zubal, I.G.

    1983-03-11

    It is an object of this invention to provide a nuclear imaging system having the versatility to do positron annihilation studies, rotating single or opposed camera gamma emission studies, and orthogonal gamma emission studies. It is a further object of this invention to provide an imaging system having the capability for orthogonal dual multipinhole tomography. It is another object of this invention to provide a nuclear imaging system in which all available energy data, as well as patient physiological data, are acquired simultaneously in list mode.

  9. Configuration management in nuclear power plants

    E-Print Network [OSTI]

    2003-01-01

    Configuration management (CM) is the process of identifying and documenting the characteristics of a facility's structures, systems and components of a facility, and of ensuring that changes to these characteristics are properly developed, assessed, approved, issued, implemented, verified, recorded and incorporated into the facility documentation. The need for a CM system is a result of the long term operation of any nuclear power plant. The main challenges are caused particularly by ageing plant technology, plant modifications, the application of new safety and operational requirements, and in general by human factors arising from migration of plant personnel and possible human failures. The IAEA Incident Reporting System (IRS) shows that on average 25% of recorded events could be caused by configuration errors or deficiencies. CM processes correctly applied ensure that the construction, operation, maintenance and testing of a physical facility are in accordance with design requirements as expressed in the d...

  10. Resummed QCD Power Corrections to Nuclear Shadowing

    E-Print Network [OSTI]

    Qiu, J; Qiu, Jianwei; Vitev, Ivan

    2004-01-01

    We calculate and resum a perturbative expansion of nuclear enhanced power corrections to the structure functions measured in deeply inelastic scattering of leptons on a nuclear target. Our results for the Bjorken $x$-, $Q^2$- and $A$-dependence of nuclear shadowing in $F_2^A(x,Q^2)$ and the nuclear modifications to $F_L^A(x,Q^2)$, obtained in terms of the QCD factorization approach, are consistent with the existing data. We demonstrate that the low-$Q^2$ behavior of these data and the measured large longitudinal structure function point to a critical role for the power corrections when compared to other theoretical approaches.

  11. Resummed QCD Power Corrections to Nuclear Shadowing

    E-Print Network [OSTI]

    Jianwei Qiu; Ivan Vitev

    2005-01-10

    We calculate and resum a perturbative expansion of nuclear enhanced power corrections to the structure functions measured in deeply inelastic scattering of leptons on a nuclear target. Our results for the Bjorken $x$-, $Q^2$- and $A$-dependence of nuclear shadowing in $F_2^A(x,Q^2)$ and the nuclear modifications to $F_L^A(x,Q^2)$, obtained in terms of the QCD factorization approach, are consistent with the existing data. We demonstrate that the low-$Q^2$ behavior of these data and the measured large longitudinal structure function point to a critical role for the power corrections when compared to other theoretical approaches.

  12. Relative Movements for Design of Commodities in Nuclear Power Plants

    Broader source: Energy.gov [DOE]

    Relative Movements for Design of Commodities in Nuclear Power Plants Javad Moslemian, Vice President, Nuclear Power Technologies, Sargent & Lundy LLC Nezar Abraham, Senior Associate II, Nuclear Power Technologies, Sargent & Lundy LLC

  13. Review: Nuclear Power Is Not the Answer by Helen Caldicott

    E-Print Network [OSTI]

    Mirza, Umar Karim

    2007-01-01

    Review: Nuclear Power Is Not the Answer By Helen CaldicottPakistan. Helen Caldicott. Nuclear Power Is Not the Answer.about the true costs of nuclear power, the health effects of

  14. SPACE-R Thermionic Space Nuclear Power System: Design and Technology Demonstration Program. Semiannual technical progress report for period ending March 1993

    SciTech Connect (OSTI)

    Not Available

    1993-05-01

    This Semiannual Technical Progress Report summarizes the technical progress and accomplishments for the Thermionic Space Nuclear Power System (TI-SNPS) Design and Technology Demonstration Program of the Prime Contractor, Space Power Incorporated (SPI), its subcontractors and supporting National Laboratories during the first half of the Government Fiscal Year (GFY) 1993. SPI`s subcontractors and supporting National Laboratories include: Babcock & Wilcox for the reactor core and externals; Space Systems/Loral for the spacecraft integration; Thermocore for the radiator heat pipes and the heat exchanger; INERTEK of CIS for the TFE, core elements and nuclear tests; Argonne National Laboratories for nuclear safety, physics and control verification; and Oak Ridge National laboratories for materials testing. Parametric trade studies are near completion. However, technical input from INERTEK has yet to be provided to determine some of the baseline design configurations. The INERTEK subcontract is expected to be initiated soon. The Point Design task has been initiated. The thermionic fuel element (TFE) is undergoing several design iterations. The reactor core vessel analysis and design has also been started.

  15. NUCLEAR POWER AND RESEARCH REACTORS 1939 1942 1943 1944

    E-Print Network [OSTI]

    #12;#12;11 #12;2 NUCLEAR POWER AND RESEARCH REACTORS 1939 1942 1943 1944 Nuclear fission discovered 430 nuclear power reactors are operating in the world, and 103 nuclear power plants produce 20, naval reactors, and nuclear power plants. Oak Ridge experiments byArt Snell in 1944 showed that 10 tons

  16. CEC-150-2006-001-F NUCLEAR POWER

    E-Print Network [OSTI]

    CALIFORNIA ENERGY COMMISSION MARCH 2006 CEC-150-2006-001-F NUCLEAR POWER IN CALIFORNIA: STATUS REPORT Prepared for the 2005 Integrated Energy Policy Report FINAL CONSULTANT REPORT #12;NUCLEAR POWER on California's nuclear power plants and key nuclear power issues such as nuclear waste storage, disposal

  17. Educational/trainingEducational/training needs of Nuclear Powerneeds of Nuclear Power

    E-Print Network [OSTI]

    Educational/trainingEducational/training needs of Nuclear Powerneeds of Nuclear Power Industry [NPI.Activities of the NPI. ·· Activities important for a GreekActivities important for a Greek Nuclear Power Industry.Nuclear and models discussed are based on the USdiscussed are based on the US Nuclear Power Industry andNuclear Power

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

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

    Quarterly Nuclear Power Deployment Scorecard - April 2013 Quarterly Nuclear Power Deployment Scorecard - April 2013 News Updates On November 20, 2012, the Department of Energy...

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

    Office of Environmental Management (EM)

    Delivers Remarks on Nuclear Power at Tokyo American Center in Japan Deputy Secretary Poneman Delivers Remarks on Nuclear Power at Tokyo American Center in Japan December 15, 2011 -...

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

    Open Energy Info (EERE)

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

  1. 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,...

  2. Neural networks and their application to nuclear power plant diagnosis

    SciTech Connect (OSTI)

    Reifman, J. [Argonne National Lab., IL (United States). Reactor Analysis Div.

    1997-10-01

    The authors present a survey of artificial neural network-based computer systems that have been proposed over the last decade for the detection and identification of component faults in thermal-hydraulic systems of nuclear power plants. The capabilities and advantages of applying neural networks as decision support systems for nuclear power plant operators and their inherent characteristics are discussed along with their limitations and drawbacks. The types of neural network structures used and their applications are described and the issues of process diagnosis and neural network-based diagnostic systems are identified. A total of thirty-four publications are reviewed.

  3. Japanese nuclear power and the Kyoto agreement

    E-Print Network [OSTI]

    Babiker, Mustafa H.M.; Reilly, John M.; Ellerman, A. Denny.

    We find that, on an economic basis, nuclear power could make a substantial contribution for meeting the emissions target Japan agreed to in the Kyoto Protocol. It is unlikely however that the contribution would be as large ...

  4. A Verification Framework for FBD based Software in Nuclear Power Plants Junbeom Yoo

    E-Print Network [OSTI]

    A Verification Framework for FBD based Software in Nuclear Power Plants Junbeom Yoo Div, conducted using a nuclear power plant shutdown system being developed in Korea, demonstrated (2001~2008) is to develop a suite of I&C software for use in the next generation Korean nuclear power

  5. Nuclear power plant construction activity, 1986

    SciTech Connect (OSTI)

    Not Available

    1987-07-24

    Cost estimates, chronological data on construction progress, and the physical characteristics of nuclear units in commercial operation and units in the construction pipeline as of December 31, 1986, are presented. This report, which is updated annually, was prepared to provide an overview of the nuclear power plant construction industry. The report contains information on the status of nuclear generating units, average construction costs and lead-times, and construction milestones for individual reactors.

  6. Power Systems Past Projects

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

    loop and its six associated substations. An upgrade of the INL loop, designed by Power Systems personnel, was completed in 1997. This project consists of transmission line...

  7. Ongoing Space Nuclear Systems Development in the United States

    SciTech Connect (OSTI)

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

    2011-10-01

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

  8. Crowd-powered systems

    E-Print Network [OSTI]

    Bernstein, Michael Scott

    2012-01-01

    Crowd-powered systems combine computation with human intelligence, drawn from large groups of people connecting and coordinating online. These hybrid systems enable applications and experiences that neither crowds nor ...

  9. Solar powered desalination system

    E-Print Network [OSTI]

    Mateo, Tiffany Alisa

    2011-01-01

    Solar Energy Center USA, Blythe, CA Solar electric power plant,Solar Wind Total Northwest Imports Southwest Imports Total Energy System Table 1.18: Largest PV Power PlantsPlants……………………………………………………32 Table 1.19: Solar Desalination Systems…………………………………………………34 Table 1.20: Energy

  10. 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.

  11. Nuclear Power Plant Construction Activity, 1985

    SciTech Connect (OSTI)

    Not Available

    1986-08-13

    Nuclear Power Plant Construction Activity 1985 presents cost estimates, chronological data on construction progress, and the physical characteristics of nuclear units in commercial operation and units in the construction pipeline as of December 31, 1985. This Report, which is updated annually, was prepared to respond to the numerous requests received by the Energy Information Administration for the data collected on Form EIA-254, ''Semiannual Report on Status of Reactor Construction.''

  12. 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)

  13. Power System Dispatcher

    Broader source: Energy.gov [DOE]

    As a Power System Dispatcher, you will be working in the Operations Center in Springfield, Missouri as part of the Division of Scheduling & Operations, Office of Corporate Operations. You will...

  14. Incremental costs and optimization of in-core fuel management of nuclear power plants

    E-Print Network [OSTI]

    Watt, Hing Yan

    1973-01-01

    This thesis is concerned with development of methods for optimizing the energy production and refuelling decision for nuclear power plants in an electric utility system containing both nuclear and fossil-fuelled stations. ...

  15. A Verification Framework for FBD based Software in Nuclear Power Plants Junbeom Yoo

    E-Print Network [OSTI]

    require safety demonstration. RPS software of APR-1400 advanced nuclear power reactor, in developmentA Verification Framework for FBD based Software in Nuclear Power Plants Junbeom Yoo Div-based software in nuclear reactor protection system (RPS). FBD programs are developed manually and revised

  16. The Potential for a Nuclear Renaissance: The Development of Nuclear Power Under Climate Change Mitigation Policies

    E-Print Network [OSTI]

    The Potential for a Nuclear Renaissance: The Development of Nuclear Power Under Climate Change and Policy Program #12;#12;The Potential for a Nuclear Renaissance: The Development of Nuclear Power Under the Earth's climate, and will continue to change it for centuries if no action is taken. Nuclear power

  17. Webinar on Environmental Radiation Protection Standards for Nuclear Power

    E-Print Network [OSTI]

    not directly oversee nuclear power plants. · The Nuclear Regulatory Commission (NRC) licenses and overseesWELCOME! Webinar on Environmental Radiation Protection Standards for Nuclear Power Operations #12 for Nuclear Power Operations­ 40 CFR Part 190 Brian Littleton, US EPA May 28, 2014 Public Webinar #12

  18. C Produced by Nuclear Power Reactors Generation and Characterization of

    E-Print Network [OSTI]

    Haviland, David

    14 C Produced by Nuclear Power Reactors ­ Generation and Characterization of Gaseous, Liquid in the terrestrial environment in the vicinity of two European nuclear power plants. Radiocarbon 46(2)863­868. III levels in the vicinity of the Lithuanian nuclear power plant Ignalina. Nuclear Instruments and Methods

  19. Global nuclear power supply chains and the rise of China's nuclear industry

    E-Print Network [OSTI]

    Metzler, Florian

    2012-01-01

    China has embarked on a massive expansion of nuclear power that may fundamentally change the global nuclear industry, for better or for worse. Some industry observers argue that the incumbent nuclear power companies are ...

  20. Sandia Energy - Sandia Nuclear Power Safety Expert Elected to...

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

    Nuclear Power Safety Expert Elected to National Academy of Engineering Home Infrastructure Security Energy Nuclear Energy Capabilities News News & Events Research & Capabilities...

  1. 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.

  2. Power Systems Development Facility

    SciTech Connect (OSTI)

    Southern Company Services

    2009-01-31

    In support of technology development to utilize coal for efficient, affordable, and environmentally clean power generation, the Power Systems Development Facility (PSDF), located in Wilsonville, Alabama, has routinely demonstrated gasification technologies using various types of coals. The PSDF is an engineering scale demonstration of key features of advanced coal-fired power systems, including a Transport Gasifier, a hot gas particulate control device, advanced syngas cleanup systems, and high-pressure solids handling systems. This final report summarizes the results of the technology development work conducted at the PSDF through January 31, 2009. Twenty-one major gasification test campaigns were completed, for a total of more than 11,000 hours of gasification operation. This operational experience has led to significant advancements in gasification technologies.

  3. A Verification Framework for FBD based Software in Nuclear Power Plants Junbeom Yoo

    E-Print Network [OSTI]

    Jee, Eunkyoung

    power reactor. Formal verification techniques such as model checking 1 Goal of KNICS consortium project in nuclear power plant's reactor protection systems. The software verification framework uses two differentA Verification Framework for FBD based Software in Nuclear Power Plants Junbeom Yoo Div

  4. 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).

  5. Nuclear Power - Operation, Safety and Environment 

    E-Print Network [OSTI]

    2011-01-01

    for Advanced Reactors 47 P. F. Frutuoso e Melo, I. M. S. Oliveira and P. L. Saldanha Chapter 4 Geodetic Terrestrial Observations for the Determination of the Stability in the Kr?ko Nuclear Power Plant Region 71 S. Sav?ek, T. Ambro?i? and D. Kogoj Chapter... Experience in Nuclear Steam Reheat 3 Eugene Saltanov and Igor Pioro Chapter 2 Integrated Approach for Actual Safety Analysis 29 Francesco D?Auria, Walter Giannotti and Marco Cherubini Chapter 3 LWR Safety Analysis and Licensing and Implications...

  6. 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.

  7. Carbon pricing, nuclear power and electricity markets

    SciTech Connect (OSTI)

    Cameron, R.; Keppler, J. H. [OECD Nuclear Energy Agency, 12, boulevard des Iles, 92130 Issy-les-Moulineaux (France)

    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)

  8. 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.

  9. Incentive Cost Recovery Rule for Nuclear Power Generation (Louisiana)

    Broader source: Energy.gov [DOE]

    The Incentive Cost Recovery Rule for Nuclear Power Generation establishes guidelines for any utility seeking to develop a nuclear power plant in Louisiana. The rule clarifies, as well as...

  10. 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 &...

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

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

    Secretary Chu Visits Vogtle Nuclear Power Plant Secretary Chu Visits Vogtle Nuclear Power Plant February 15, 2012 - 3:54pm Addthis Secretary Chu traveled to Waynesboro, Georgia, to...

  12. 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...

  13. 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...

  14. Subsynchronous resonance in power systems

    SciTech Connect (OSTI)

    Anderson, P.M. (Power Math Associates, Inc. (US)); Agrawal, B.L. (Arizona Public Service Co., Phoenix, AZ (United States)); Van Ness, J.E. (Northwestern Univ., Evanston, IL (United States). Dept. of Electrical Engineering and Computer Science)

    1990-01-01

    This book provides an introduction to subsynchronous resonance in power systems and includes material on system modeling, system parameters, and system analysis.

  15. Power line detection system

    DOE Patents [OSTI]

    Latorre, V.R.; Watwood, D.B.

    1994-09-27

    A short-range, radio frequency (RF) transmitting-receiving system that provides both visual and audio warnings to the pilot of a helicopter or light aircraft of an up-coming power transmission line complex. Small, milliwatt-level narrowband transmitters, powered by the transmission line itself, are installed on top of selected transmission line support towers or within existing warning balls, and provide a continuous RF signal to approaching aircraft. The on-board receiver can be either a separate unit or a portion of the existing avionics, and can also share an existing antenna with another airborne system. Upon receipt of a warning signal, the receiver will trigger a visual and an audio alarm to alert the pilot to the potential power line hazard. 4 figs.

  16. 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

  17. Nuclear medicine imaging system

    DOE Patents [OSTI]

    Bennett, Gerald W. (East Moriches, NY); Brill, A. Bertrand (Shoreham, NY); Bizais, Yves J. C. (Upton, NY); Rowe, R. Wanda (Upton, NY); Zubal, I. George (Upton, NY)

    1986-01-01

    A nuclear medicine imaging system having two large field of view scintillation cameras mounted on a rotatable gantry and being movable diametrically toward or away from each other is disclosed. In addition, each camera may be rotated about an axis perpendicular to the diameter of the gantry. The movement of the cameras allows the system to be used for a variety of studies, including positron annihilation, and conventional single photon emission, as well as static orthogonal dual multi-pinhole tomography. In orthogonal dual multi-pinhole tomography, each camera is fitted with a seven pinhole collimator to provide seven views from slightly different perspectives. By using two cameras at an angle to each other, improved sensitivity and depth resolution is achieved. The computer system and interface acquires and stores a broad range of information in list mode, including patient physiological data, energy data over the full range detected by the cameras, and the camera position. The list mode acquisition permits the study of attenuation as a result of Compton scatter, as well as studies involving the isolation and correlation of energy with a range of physiological conditions.

  18. PNNL's Community Science & Technology Seminar Series Nuclear Power in a

    E-Print Network [OSTI]

    PNNL's Community Science & Technology Seminar Series Nuclear Power in a Post-Fukushima World generated by nuclear power. What will the U.S. energy portfolio look like, and how will the energy demand is focused on longer- term operation of nuclear power plants, including measurements to detect

  19. 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.

  20. 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.

  1. Nuclear engine system simulation (NESS) program update

    SciTech Connect (OSTI)

    Scheil, C.M.; Pelaccio, D.G. (Science Applications International Corporation, 10717 Griffith Park Drive NE, Albuquerque, NM 87123 (United States)); Petrosky, L.J. (Westinghouse Electric Corporation, Advanced Energy Systems, Waltz Mill Site Madison, PA 15663 (United States))

    1993-01-20

    The second phase of development of a Nuclear Thermal Propulsion (NTP) engine system design analysis code has been completed. The standalone, versatile Nuclear Engine System Simulation (NESS) code provides an accurate, detailed assessment of engine system operating performance, weight, and sizes. The critical information is required to support ongoing and future engine system and stage design study efforts. This recent development effort included incorporation of an updated solid-core nuclear thermal reactor model that yields a reduced core weight and higher fuel power density when compared to a NERVA type reactor. NESS can now analyze expander, gas generator, and bleed cycles, along with multi-redundant propellant pump feed systems. Performance and weight of efficient multi-stage axial turbopump can now be determined, in addition to the traditional centrifugal pump.

  2. Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume IX. Reactor and fuel cycle description

    SciTech Connect (OSTI)

    Not Available

    1980-06-01

    The Nonproliferation Alterntive Systems Assessment Program (NASAP) has characterized and assessed various reactor/fuel-cycle systems. Volume IX provides, in summary form, the technical descriptions of the reactor/fuel-cycle systems studied. This includes the status of the system technology, as well as a discussion of the safety, environmental, and licensing needs from a technical perspective. This information was then used in developing the research, development, and demonstration (RD and D) program, including its cost and time frame, to advance the existing technology to the level needed for commercial use. Wherever possible, the cost data are given as ranges to reflect the uncertainties in the estimates.

  3. Remote hybrid power systems

    SciTech Connect (OSTI)

    Barley, C.D.; Winn, C.B. [Colorado State Univ., Fort Collins, CO (United States)

    1997-12-31

    This paper provides an overview of the emerging technology of remote, stand-alone electrical power systems featuring a renewable source (wind or photovoltaics [PV]) as well as a diesel generator, with or without an energy storage device. Other stand-alone power systems are discussed briefly, mainly to emphasize the domain of hybrid systems. The history of hybrid systems is reviewed, beginning with the first wind/diesel system in the late 1970s. Other topics include issues arising from the characteristics of diesel engine/generator sets; simple vs. complex systems; the various energy storage technologies that have been used or proposed; control strategies; modeling; optimization; and some {open_quotes}nuts & bolts{close_quotes} details. The bibliography includes over 130 references which are cited throughout the topical discussions. It is concluded that the technical feasibility of hybrid systems has been demonstrated through many prototype installations, and that areas for further improvements include higher reliability and more economical energy storage devices. 139 refs., 7 figs., 1 tab.

  4. High power connection system

    DOE Patents [OSTI]

    Schaefer, Christopher E. (Warren, OH); Beer, Robert C. (Noblesville, IN); McCall, Mark D. (Youngstown, OH)

    2000-01-01

    A high power connection system adapted for automotive environments which provides environmental and EMI shielding includes a female connector, a male connector, and a panel mount. The female connector includes a female connector base and a snap fitted female connector cover. The male connector includes a male connector base and a snap fitted male connector cover. The female connector base has at least one female power terminal cavity for seatably receiving a respective female power terminal. The male connector base has at least one male power terminal cavity for seatably receiving a respective male power terminal. The female connector is covered by a cover seal and a conductive shroud. A pair of lock arms protrude outward from the front end of the male connector base, pass through the panel mount and interface with a lever of a lever rotatably connected to the shroud to thereby mechanically assist mating of the male and female connectors. Safety terminals in the male and female connectors provide a last-to-connect-first-to-break connection with an HVIL circuit.

  5. Some aspects of nuclear power plant safety under war conditions

    SciTech Connect (OSTI)

    Stritar, A.; Mavko, B.; Susnik, J.; Sarler, B. (Jozef Stefan Inst., Ljubljana (Slovenia))

    1993-02-01

    In the summer of 1991, the Krsko nuclear power plant in Slovenia found itself in an area of military operations. This was probably the first commercial nuclear power plant to have been threatened by an attack by fighter jets. A number of never-before-asked questions had to be answered by the operating staff and supporting organizations. Some aspects of nuclear power plant safety under war conditions are described, such as the selection of the best plant operating state before the attack and the determination of plant system vulnerability and dose releases from the potentially damaged spent fuel in the spent-fuel pit. The best operating mode to which the plant should be brought before the attack is cold shutdown, and radiological consequences to the environment after the spent fuel is damaged and the water in the pit is lost are not very high. The problem of nuclear power plant safety under war conditions should be addressed in more detail in the future.

  6. Power System Dispatcher (Technical Writer)

    Broader source: Energy.gov [DOE]

    (See Frequently Asked Questions for more information). Where would I be working? Western Area Power Administration Rocky Mountain Region Power System Operations Operations Reliability and Balancing...

  7. The Decline and Death of Nuclear Power

    E-Print Network [OSTI]

    Melville, Jonathan

    2013-01-01

    Nuclear- Wastes/Appendices/Radioactive-Waste-Management-Nuclear Association (2010). Radioactive Waste Management:

  8. Review of nuclear power plant offsite power source reliability and related recommended changes to the NRC rules and regulations

    SciTech Connect (OSTI)

    Battle, R.E.; Clark, F.H.; Reddoch, T.W.

    1980-05-01

    The NRC has stated its concern about the reliability of the offsite power system as the preferred emergency source and about the possible damage to a pressurized water reactor (PWR) that could result from a rapid decay of power grid frequency. ORNL contracted with NRC to provide technical assistance to establish criteria that can be used to evaluate the offsite power system for the licensing of a nuclear power plant. The results of many of the studies for this contract are recommendations to assess and control the power grid during operation. This is because most of the NRC regulations pertaining to the offsite power system are related to the design of the power grid, and we believe that additional emphasis on monitoring the power grid operation will improve the reliability of the nuclear plant offsite power supply. 46 refs., 10 figs.

  9. Powering the Nuclear Navy | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefield Municipal Gas &SCE-SessionsSouthReport for the t-) S/,,5 'a C O09Our Mission / Powering the Nuclear

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would like submitKansas Nuclear ProfileMultiferroic Electric FieldAdministration

  11. 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.

  12. Solar powered desalination system

    E-Print Network [OSTI]

    Mateo, Tiffany Alisa

    2011-01-01

    2008, uses concentrated solar power to split water. Figurethe main reason the potential for solar power is boundless.a clean energy source, solar power is inexhaustible, fairly

  13. Review guidelines for software languages for use in nuclear power plant safety systems: Final report. Revision 1

    SciTech Connect (OSTI)

    Hecht, M.; Decker, D.; Graff, S.; Green, W.; Lin, D.; Dinsmore, G.; Koch, S.

    1997-10-01

    Guidelines for the programming and auditing of software written in high level languages for safety systems are presented. The guidelines are derived from a framework of issues significant to software safety which was gathered from relevant standards and research literature. Language-specific adaptations of these guidelines are provided for the following high level languages: Ada83 and Ada95; C and C++; International Electrochemical Commission (IEC) Standard 1131-3 Ladder Logic, Sequential Function Charts, Structured Text, and Function Block Diagrams; Pascal; and PL/M. Appendices to the report include a tabular summary of the guidelines and additional information on selected languages.

  14. Power control system and method

    DOE Patents [OSTI]

    Steigerwald, Robert Louis (Burnt Hills, NY) [Burnt Hills, NY; Anderson, Todd Alan (Niskayuna, NY) [Niskayuna, NY

    2008-02-19

    A power system includes an energy harvesting device, a battery coupled to the energy harvesting device, and a circuit coupled to the energy harvesting device and the battery. The circuit is adapted to deliver power to a load by providing power generated by the energy harvesting device to the load without delivering excess power to the battery and to supplement the power generated by the energy harvesting device with power from the battery if the power generated by the energy harvesting device is insufficient to fully power the load. A method of operating the power system is also provided.

  15. Power control system and method

    DOE Patents [OSTI]

    Steigerwald, Robert Louis; Anderson, Todd Alan

    2006-11-07

    A power system includes an energy harvesting device, a battery coupled to the energy harvesting device, and a circuit coupled to the energy harvesting device and the battery. The circuit is adapted to deliver power to a load by providing power generated by the energy harvesting device to the load without delivering excess power to the battery and to supplement the power generated by the energy harvesting device with power from the battery if the power generated by the energy harvesting device is insufficient to fully power the load. A method of operating the power system is also provided.

  16. Submerged Medium Voltage Cable Systems at Nuclear Power Plants. A Review of Research Efforts Relevant to Aging Mechanisms and Condition Monitoring

    SciTech Connect (OSTI)

    Brown, Jason; Bernstein, Robert; White, II, Gregory Von; Glover, Steven F.; Neely, Jason C.; Pena, Gary; Williamson, Kenneth Martin; Zutavern, Fred J.; Gelbard, Fred

    2015-03-01

    In a submerged environment, power cables may experience accelerated insulation degradation due to water - related aging mechanisms . Direct contact with water or moisture intrusion in the cable insulation s ystem has been identified in the literature as a significant aging stressor that can affect performance and lifetime of electric cables . Progressive reduction of the dielectric strength is commonly a result of water treeing which involves the development of permanent hydrophilic structures in the insulation coinciding with the absorption of water into the cable . Water treeing is a phenomenon in which dendritic microvoids are formed in electric cable insulation due to electrochemic al reactions , electromechanical forces , and diffusion of contaminants over time . These reactions are caused by the combined effect s of water presence and high electrical stress es in the material . Water tree growth follow s a tree - like branching pattern , i ncreasing in volume and length over time . Although these cables can be "dried out," water tree degradation , specifically the growth of hydrophilic regions, is believed to be permanent and typically worsens over time. Based on established research , water treeing or water induced damage can occur in a variety of electric cables including XLPE, TR - XLPE and other insulating materials, such as EPR and butyl rubber . Once water trees or water induced damage form, the dielectric strength of an insulation materia l will decrease gradually with time as the water trees grow in length, which could eventually result in failure of the insulating material . Under wet conditions or i n submerged environments , several environmental and operational parameters can influence w ater tree initiation and affect water tree growth . These parameters include voltage cycling, field frequency, temperature, ion concentration and chemistry, type of insula tion material , and the characteristics of its defects. In this effort, a review of academic and industrial literature was performed to identify : 1) findings regarding the degradation mechanisms of submerged cabling and 2) condition monitoring methods that may prove useful in predict ing the remaining lifetime of submerged medium voltage p ower cables . The re search was conducted by a multi - disciplinary team , and s ources includ ed official NRC reports, n ational l aboratory reports , IEEE standards, conference and journal proceedings , magazine articles , PhD dissertations , and discussions with experts . The purpose of this work was to establish the current state - of - the - art in material degradation modeling and cable condition monitoring techniques and to identify research gaps . Subsequently, future areas of focus are recommended to address these research gaps and thus strengthen the efficacy of the NRC's developing cable condition monitoring program . Results of this literature review and details of the test ing recommendations are presented in this report . FOREWORD To ensure the safe, re liable, and cost - effective long - term operation of nuclear power plants, many systems, structures, and components must be continuously evaluated. The Nuclear Regulatory Commission (NRC) has identified that cables in submerged environments are of concern, particularly as plants are seeking license renewal. To date, there is a lack of consensus on aging and degradation mechanisms even though the area of submerged cables has been extensively studied. Consequently, the ability to make lifetime predictions for submerged cable does not yet exist. The NRC has engaged Sandia National Laboratories (SNL) to lead a coordinated effort to help elucidate the aging and degradation of cables in submerged environments by collaborating with cable manufacturers, utilities, universities, and other government agencies. A team of SNL experts was assembled from the laboratories including electrical condition monitoring, mat erial science, polymer degradation, plasma physics, nuclear systems, and statistics. An objective of this research program is to perform a l iterature

  17. Department of Mechanical and Nuclear Engineering Spring 2012 East Campus Power Plant Deaerator Optimization

    E-Print Network [OSTI]

    Demirel, Melik C.

    PENNSTATE Department of Mechanical and Nuclear Engineering Spring 2012 East Campus Power Plant Deaerator Optimization Overview In the East Campus Power plant a new Deaerator system has been installed. Approach Understand the inner-workings and operations of the power plant and the Deaerator system. Visit

  18. The U.S. Department of Energy's Office of Nuclear Energy promotes nuclear power as

    E-Print Network [OSTI]

    Kemner, Ken

    nuclear power as a resource capable of meeting the Nation's energy, environmental and national security nuclear power plants. zz NuclearzEnergyzEnablingzTechnologiesz-- to explore transformative, "out our national and international supplies of fuel for nuclear power plants remain stable

  19. Nuclear Power and the World's Energy Requirements

    E-Print Network [OSTI]

    Castellano, V; Dunning-Davies, J

    2004-01-01

    The global requirements for energy are increasing rapidly as the global population increases and the under-developed nations become more advanced. The traditional fuels used in their traditional ways will become increasingly unable to meet the demand. The need for a review of the energy sources available is paramount, although the subsequent need to develop a realistic strategy to deal with all local and global energy requirements is almost as important. Here attention will be restricted to examining some of the claims and problems of using nuclear power to attempt to solve this major question.

  20. Nuclear Power and the World's Energy Requirements

    E-Print Network [OSTI]

    V. Castellano; R. F. Evans; J. Dunning-Davies

    2004-06-10

    The global requirements for energy are increasing rapidly as the global population increases and the under-developed nations become more advanced. The traditional fuels used in their traditional ways will become increasingly unable to meet the demand. The need for a review of the energy sources available is paramount, although the subsequent need to develop a realistic strategy to deal with all local and global energy requirements is almost as important. Here attention will be restricted to examining some of the claims and problems of using nuclear power to attempt to solve this major question.

  1. The Decline and Death of Nuclear Power

    E-Print Network [OSTI]

    Melville, Jonathan

    2013-01-01

    United States Nuclear Regulatory Commission (2012). NRC:United States Nuclear Regulatory Commission (2013). NRC: Newreasons that the Nuclear Regulatory Commission was founded

  2. Financial and ratepayer impacts of nuclear power plant regulatory reform

    SciTech Connect (OSTI)

    Turpin, A.G.

    1985-01-01

    Three reports - ''The Future Market for Electric Generating Capacity,'' ''Quantitative Analysis of Nuclear Power Plant Licensing Reform,'' and ''Nuclear Rate Increase Study'' are recent studies performed by the Los Alamos National Laboratory that deal with nuclear power. This presents a short summary of these three studies. More detail is given in the reports.

  3. Power Systems Development Facility

    SciTech Connect (OSTI)

    None

    2003-07-01

    This report discusses Test Campaign TC12 of the Kellogg Brown & Root, Inc. (KBR) Transport Gasifier train with a Siemens Westinghouse Power Corporation (SW) particle filter system at the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama. The Transport Gasifier is an advanced circulating fluidized-bed reactor designed to operate as either a combustor or a gasifier using a particulate control device (PCD). While operating as a gasifier, either air or oxygen can be used as the oxidant. Test run TC12 began on May 16, 2003, with the startup of the main air compressor and the lighting of the gasifier start-up burner. The Transport Gasifier operated until May 24, 2003, when a scheduled outage occurred to allow maintenance crews to install the fuel cell test unit and modify the gas clean-up system. On June 18, 2003, the test run resumed when operations relit the start-up burner, and testing continued until the scheduled end of the run on July 14, 2003. TC12 had a total of 733 hours using Powder River Basin (PRB) subbituminous coal. Over the course of the entire test run, gasifier temperatures varied between 1,675 and 1,850 F at pressures from 130 to 210 psig.

  4. Nuclear Power No Solution to the Climate Crisis

    E-Print Network [OSTI]

    Laughlin, Robert B.

    construction of new nuclear reactors as a means of addressing the climate crisis. Available renewable energy Reality Check, Part 4 · Costs raise serious questions about nuclear's competitiveness · 15 cents per kwNuclear Power No Solution to the Climate Crisis Michael Mariotte Nuclear Information and Resource

  5. Flex power perspectives of indirect power system control through...

    Open Energy Info (EERE)

    Flex power perspectives of indirect power system control through dynamic power price (Smart Grid Project) Jump to: navigation, search Project Name Flex power perspectives of...

  6. Analysis of nuclear power plant construction costs

    SciTech Connect (OSTI)

    Not Available

    1986-01-01

    The objective of this report is to present the results of a statistical analysis of nuclear power plant construction costs and lead-times (where lead-time is defined as the duration of the construction period), using a sample of units that entered construction during the 1966-1977 period. For more than a decade, analysts have been attempting to understand the reasons for the divergence between predicted and actual construction costs and lead-times. More importantly, it is rapidly being recognized that the future of the nuclear power industry rests precariously on an improvement in the cost and lead-time situation. Thus, it is important to study the historical information on completed plants, not only to understand what has occurred to also to improve the ability to evaluate the economics of future plants. This requires an examination of the factors that have affected both the realized costs and lead-times and the expectations about these factors that have been formed during the construction process. 5 figs., 22 tabs.

  7. Power Systems Group Home Page

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

    Systems Division Search APS ... Search Button About ASD General Information ASD Groups ESHQA Operations Argonne Home > Advanced Photon Source > Power Systems Group This page is...

  8. Solar powered desalination system

    E-Print Network [OSTI]

    Mateo, Tiffany Alisa

    2011-01-01

    are many solar photovoltaic power plants internationally andUSA, Blythe, CA Solar electric power plant, Blythe USA, SanTX Blue Wing solar electric power plant USA, Jacksonville,

  9. POWER SYSTEMS DEVELOPMENT FACILITY

    SciTech Connect (OSTI)

    Unknown

    2002-11-01

    This report discusses test campaign GCT4 of the Kellogg Brown & Root, Inc. (KBR) transport reactor train with a Siemens Westinghouse Power Corporation (Siemens Westinghouse) particle filter system at the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama. The transport reactor is an advanced circulating fluidized-bed reactor designed to operate as either a combustor or a gasifier using one of two possible particulate control devices (PCDs). The transport reactor was operated as a pressurized gasifier during GCT4. GCT4 was planned as a 250-hour test run to continue characterization of the transport reactor using a blend of several Powder River Basin (PRB) coals and Bucyrus limestone from Ohio. The primary test objectives were: Operational Stability--Characterize reactor loop and PCD operations with short-term tests by varying coal-feed rate, air/coal ratio, riser velocity, solids-circulation rate, system pressure, and air distribution. Secondary objectives included the following: Reactor Operations--Study the devolatilization and tar cracking effects from transient conditions during transition from start-up burner to coal. Evaluate the effect of process operations on heat release, heat transfer, and accelerated fuel particle heat-up rates. Study the effect of changes in reactor conditions on transient temperature profiles, pressure balance, and product gas composition. Effects of Reactor Conditions on Synthesis Gas Composition--Evaluate the effect of air distribution, steam/coal ratio, solids-circulation rate, and reactor temperature on CO/CO{sub 2} ratio, synthesis gas Lower Heating Value (LHV), carbon conversion, and cold and hot gas efficiencies. Research Triangle Institute (RTI) Direct Sulfur Recovery Process (DSRP) Testing--Provide syngas in support of the DSRP commissioning. Loop Seal Operations--Optimize loop seal operations and investigate increases to previously achieved maximum solids-circulation rate.

  10. Power Systems Engineer | Princeton Plasma Physics Lab

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

    technical support and assistance on complicated Power System electrical, electronic and control systems. Knowledge of AC Power, power conversion, DC circuits, motors, power...

  11. Solar thermal power system

    DOE Patents [OSTI]

    Bennett, Charles L.

    2010-06-15

    A solar thermal power generator includes an inclined elongated boiler tube positioned in the focus of a solar concentrator for generating steam from water. The boiler tube is connected at one end to receive water from a pressure vessel as well as connected at an opposite end to return steam back to the vessel in a fluidic circuit arrangement that stores energy in the form of heated water in the pressure vessel. An expander, condenser, and reservoir are also connected in series to respectively produce work using the steam passed either directly (above a water line in the vessel) or indirectly (below a water line in the vessel) through the pressure vessel, condense the expanded steam, and collect the condensed water. The reservoir also supplies the collected water back to the pressure vessel at the end of a diurnal cycle when the vessel is sufficiently depressurized, so that the system is reset to repeat the cycle the following day. The circuital arrangement of the boiler tube and the pressure vessel operates to dampen flow instabilities in the boiler tube, damp out the effects of solar transients, and provide thermal energy storage which enables time shifting of power generation to better align with the higher demand for energy during peak energy usage periods.

  12. A Domain-Specific Safety Analysis for Digital Nuclear Plant Protection Systems

    E-Print Network [OSTI]

    . INTRODUCTION Safety-critical systems (e.g. nuclear power plants and air- planes) require rigorous quality a domain-specific point of view. In the RPS (Reactor Protection System) in nuclear power plants, the mostA Domain-Specific Safety Analysis for Digital Nuclear Plant Protection Systems Sanghyun Yoon

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

    Office of Scientific and Technical Information (OSTI)

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

  14. 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...

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

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

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

  16. 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.

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

    DOE Patents [OSTI]

    Powell, James G. (Clifton Park, NY)

    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.

  18. West European nuclear power generation research and development

    SciTech Connect (OSTI)

    Turinsky, P.J.; Baron, S.; Burch, W.D.; Corradini, M.L.; Lucas, G.E.; Matthews, R.B.; Uhrig, R.E.

    1991-09-01

    This report assesses the status of West European research and development (R&D) in support of nuclear power generation. The focus is on light-water reactors (LWRs), as they will likely be the only concept commerically implemented within the next decade. To a laser degree, alternative concepts such as the high-temperature gas cooled reactor and the liquid-metal reactor (LMR) are also assessed. To bound the study, only the fuel cycle stages of fuel fabrication, power generation, and fuel reprocessing are considered. Under the topic of power generation, the subtopics of core reactor physics, materials, instrumentation and control systems, nuclear power safety, and power plant fabrication and construction are addressed. The front-end fuel cycle stages of mining and milling, conversion and enrichment, and the back-end fuel cycle stages of waste conditioning and disposal and not considered. Most assessments for light-water reactor R&D are completed on a country-by-country basis since there is limited cooperation among the West European countries due to the commercial relevance of R&D in this area.

  19. West European nuclear power generation research and development

    SciTech Connect (OSTI)

    Turinsky, P.J.; Baron, S.; Burch, W.D.; Corradini, M.L.; Lucas, G.E.; Matthews, R.B.; Uhrig, R.E.

    1991-09-01

    This report assesses the status of West European research and development (R D) in support of nuclear power generation. The focus is on light-water reactors (LWRs), as they will likely be the only concept commerically implemented within the next decade. To a laser degree, alternative concepts such as the high-temperature gas cooled reactor and the liquid-metal reactor (LMR) are also assessed. To bound the study, only the fuel cycle stages of fuel fabrication, power generation, and fuel reprocessing are considered. Under the topic of power generation, the subtopics of core reactor physics, materials, instrumentation and control systems, nuclear power safety, and power plant fabrication and construction are addressed. The front-end fuel cycle stages of mining and milling, conversion and enrichment, and the back-end fuel cycle stages of waste conditioning and disposal and not considered. Most assessments for light-water reactor R D are completed on a country-by-country basis since there is limited cooperation among the West European countries due to the commercial relevance of R D in this area.

  20. Seminar in Critical Inquiry Twenty-first Century Nuclear Systems

    SciTech Connect (OSTI)

    LeMone, D. V.

    2002-02-25

    Critical Inquiry, has not only been successful in increasing university student retention rate but also in improving student academic performance beyond the initial year of transition into the University. The seminar course herein reviewed is a balanced combination of student personal and academic skill development combined with a solid background in modern nuclear systems. It is a valid premise to assume that entering students as well as stakeholders of the general public demonstrate equal levels of capability. Nuclear systems is designed to give a broad and basic knowledge of nuclear power, medical, industrial, research, and military systems (nuclear systems) in 20-25 hours.

  1. Nuclear power plant status diagnostics using a neural network with dynamic node architecture

    SciTech Connect (OSTI)

    Basu, A.

    1992-12-31

    This thesis is part of an ongoing project at Iowa State University to develop ANN based fault diagnostic systems to detect and classify operational transients at nuclear power plants. The project envisages the deployment of such an advisor at Iowa Electric Light and Power Company`s Duane Arnold Energy Center nuclear power plant located at Palo, IA. This advisor is expected to make status diagnosis in real time, thus providing the operators with more time for corrective measures.

  2. Nuclear power plant status diagnostics using a neural network with dynamic node architecture

    SciTech Connect (OSTI)

    Basu, A.

    1992-01-01

    This thesis is part of an ongoing project at Iowa State University to develop ANN based fault diagnostic systems to detect and classify operational transients at nuclear power plants. The project envisages the deployment of such an advisor at Iowa Electric Light and Power Company's Duane Arnold Energy Center nuclear power plant located at Palo, IA. This advisor is expected to make status diagnosis in real time, thus providing the operators with more time for corrective measures.

  3. Design, analysis and optimization of the power conversion system for the Modular Pebble Bed Reactor System

    E-Print Network [OSTI]

    Wang, Chunyun, 1968-

    2003-01-01

    The Modular Pebble Bed Reactor system (MPBR) requires a gas turbine cycle (Brayton cycle) as the power conversion system for it to achieve economic competitiveness as a GenIV nuclear system. The availability of controllable ...

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

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

    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...

  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. Body powered thermoelectric systems

    E-Print Network [OSTI]

    Settaluri, Krishna Tej

    2012-01-01

    Great interest exists for and progress has be made in the effective utilization of the human body as a possible power supply in hopes of powering such applications as sensors and continuously monitoring medical devices ...

  7. 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.

  8. 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.

  9. 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)

  10. Reactor and Nuclear Systems Division (RNSD)

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

    RNSD Home Research Groups Advanced Reactor Systems & Safety Nuclear Data & Criticality Safety Nuclear Security Modeling Radiation Safety Information Computational Center Radiation...

  11. Multi Megawatt Power System Analysis Report

    SciTech Connect (OSTI)

    Longhurst, Glen Reed; Harvego, Edwin Allan; Schnitzler, Bruce Gordon; Seifert, Gary Dean; Sharpe, John Phillip; Verrill, Donald Alan; Watts, Kenneth Donald; Parks, Benjamin Travis

    2001-11-01

    Missions to the outer planets or to near-by planets requiring short times and/or increased payload carrying capability will benefit from nuclear power. A concept study was undertaken to evaluate options for a multi-megawatt power source for nuclear electric propulsion. The nominal electric power requirement was set at 15 MWe with an assumed mission profile of 120 days at full power, 60 days in hot standby, and another 120 days of full power, repeated several times for 7 years of service. Of the numerous options considered, two that appeared to have the greatest promise were a gas-cooled reactor based on the NERVA Derivative design, operating a closed cycle Brayton power conversion system; and a molten lithium-cooled reactor based on SP-100 technology, driving a boiling potassium Rankine power conversion system. This study examined the relative merits of these two systems, seeking to optimize the specific mass. Conclusions were that either concept appeared capable of approaching the specific mass goal of 3-5 kg/kWe estimated to be needed for this class of mission, though neither could be realized without substantial development in reactor fuels technology, thermal radiator mass efficiency, and power conversion and distribution electronics and systems capable of operating at high temperatures. Though the gas-Brayton systems showed an apparent advantage in specific mass, differences in the degree of conservatism inherent in the models used suggests expectations for the two approaches may be similar. Brayton systems eliminate the need to deal with two-phase flows in the microgravity environment of space.

  12. Power Systems Engineering

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

    systems; steam, water, fuel, and environmental monitoring systems; alternative energy systems; reliability, availability, and maintainability assessments; and associated...

  13. Nuclear facilities: criteria for the design and operation of ventilation systems for nuclear installations other than nuclear reactors

    E-Print Network [OSTI]

    International Organization for Standardization. Geneva

    2004-01-01

    Nuclear facilities: criteria for the design and operation of ventilation systems for nuclear installations other than nuclear reactors

  14. Switching power pulse system

    DOE Patents [OSTI]

    Aaland, K.

    1983-08-09

    A switching system for delivering pulses of power from a source to a load using a storage capacitor charged through a rectifier, and maintained charged to a reference voltage level by a transistor switch and voltage comparator. A thyristor is triggered to discharge the storage capacitor through a saturable reactor and fractional turn saturable transformer having a secondary to primary turn ratio N of n:l/n = n[sup 2]. The saturable reactor functions as a soaker'' while the thyristor reaches saturation, and then switches to a low impedance state. The saturable transformer functions as a switching transformer with high impedance while a load coupling capacitor charges, and then switches to a low impedance state to dump the charge of the storage capacitor into the load through the coupling capacitor. The transformer is comprised of a multilayer core having two secondary windings tightly wound and connected in parallel to add their output voltage and reduce output inductance, and a number of single turn windings connected in parallel at nodes for the primary winding, each single turn winding linking a different one of the layers of the multilayer core. The load may be comprised of a resistive beampipe for a linear particle accelerator and capacitance of a pulse forming network. To hold off discharge of the capacitance until it is fully charged, a saturable core is provided around the resistive beampipe to isolate the beampipe from the capacitance until it is fully charged. 5 figs.

  15. Nuclear enhanced power corrections to DIS structure functions

    E-Print Network [OSTI]

    Xiaofeng Guo; Jianwei Qiu; Wei Zhu

    2001-10-03

    We calculate nuclear enhanced power corrections to structure functions measured in deeply inelastic lepton-nucleus scattering in Quantum Chromodynamics (QCD). We find that the nuclear medium enhanced power corrections at order of $O(\\alpha_s/Q^2)$ enhance the longitudinal structure function $F_L$, and suppress the transverse structure function $F_1$. We demonstrate that strong nuclear effects in $\\sigma_A/\\sigma_D$ and $R_A/R_D$, recently observed by HERMES Collaboration, can be explained in terms of the nuclear enhanced power corrections.

  16. DC Power Distribution Systems 

    E-Print Network [OSTI]

    Savage, P.

    2012-01-01

    - A FLEXIBLE ALTERNATIVE ..OR ELECTRICAL POWER SUPPLY S. D. REYNOLDS Manager of Industrial Marketing & Services Tennessee Valley Authority Chattanooga, Tennessee ABSTRACT In an increasingly competitive operating environment, utilities must... place greater emphasis on developing programs that benefit the customer while at the same time benefiting the utility. Economy Surplus Power (ESP) is such a program. ESP offers industrial customers attractively priced power supply arrangements based...

  17. POWER SYSTEMS DEVELOPMENT FACILITY

    SciTech Connect (OSTI)

    Unknown

    2002-05-01

    This report discusses test campaign GCT3 of the Halliburton KBR transport reactor train with a Siemens Westinghouse Power Corporation (Siemens Westinghouse) particle filter system at the Power Systems Development Facility (PSDF) located in Wilsonville, Alabama. The transport reactor is an advanced circulating fluidized-bed reactor designed to operate as either a combustor or a gasifier using one of two possible particulate control devices (PCDs). The transport reactor was operated as a pressurized gasifier during GCT3. GCT3 was planned as a 250-hour test run to commission the loop seal and continue the characterization of the limits of operational parameter variations using a blend of several Powder River Basin coals and Bucyrus limestone from Ohio. The primary test objectives were: (1) Loop Seal Commissioning--Evaluate the operational stability of the loop seal with sand and limestone as a bed material at different solids circulation rates and establish a maximum solids circulation rate through the loop seal with the inert bed. (2) Loop Seal Operations--Evaluate the loop seal operational stability during coal feed operations and establish maximum solids circulation rate. Secondary objectives included the continuation of reactor characterization, including: (1) Operational Stability--Characterize the reactor loop and PCD operations with short-term tests by varying coal feed, air/coal ratio, riser velocity, solids circulation rate, system pressure, and air distribution. (2) Reactor Operations--Study the devolatilization and tar cracking effects from transient conditions during transition from start-up burner to coal. Evaluate the effect of process operations on heat release, heat transfer, and accelerated fuel particle heat-up rates. Study the effect of changes in reactor conditions on transient temperature profiles, pressure balance, and product gas composition. (3) Effects of Reactor Conditions on Syngas Composition--Evaluate the effect of air distribution, steam/coal ratio, solids circulation rate, and reactor temperature on CO/CO{sub 2} ratio, H{sub 2}/converted carbon ratio, gasification rates, carbon conversion, and cold and hot gas efficiencies. Test run GCT3 was started on December 1, 2000, with the startup of the thermal oxidizer fan, and was completed on February 1, 2001. This test was conducted in two parts; the loop seal was commissioned during the first part of this test run from December 1 through 15, which consisted of hot inert solids circulation testing. These initial tests provided preliminary data necessary to understand different parameters associated with the operation and performance of the loop seal. The loop seal was tested with coal feed during the second part of the test run and additional data was gathered to analyze reactor operations and to identify necessary modifications to improve equipment and process performance. In the second part of GCT3, the gasification portion of the test, from January 20 to February 1, 2001, the mixing zone and riser temperatures were varied between 1,675 and 1,825 F at pressures ranging from 200 to 240 psig. There were 306 hours of solid circulation and 184 hours of coal feed attained in GCT3.

  18. 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.

  19. Refractory alloy technology for space nuclear power applications

    SciTech Connect (OSTI)

    Cooper, R.H. Jr.; Hoffman, E.E. (eds.)

    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)

  20. Switching power pulse system

    DOE Patents [OSTI]

    Aaland, Kristian (Livermore, CA)

    1983-01-01

    A switching system for delivering pulses of power from a source (10) to a load (20) using a storage capacitor (C3) charged through a rectifier (D1, D2), and maintained charged to a reference voltage level by a transistor switch (Q1) and voltage comparator (12). A thyristor (22) is triggered to discharge the storage capacitor through a saturable reactor (18) and fractional turn saturable transformer (16) having a secondary to primary turn ratio N of n:l/n=n.sup.2. The saturable reactor (18) functions as a "soaker" while the thyristor reaches saturation, and then switches to a low impedance state. The saturable transformer functions as a switching transformer with high impedance while a load coupling capacitor (C4) charges, and then switches to a low impedance state to dump the charge of the storage capacitor (C3) into the load through the coupling capacitor (C4). The transformer is comprised of a multilayer core (26) having two secondary windings (28, 30) tightly wound and connected in parallel to add their output voltage and reduce output inductance, and a number of single turn windings connected in parallel at nodes (32, 34) for the primary winding, each single turn winding linking a different one of the layers of the multilayer core. The load may be comprised of a resistive beampipe (40) for a linear particle accelerator and capacitance of a pulse forming network (42). To hold off discharge of the capacitance until it is fully charged, a saturable core (44) is provided around the resistive beampipe (40) to isolate the beampipe from the capacitance (42) until it is fully charged.

  1. 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.

  2. Economic Conditions and Factors Affecting New Nuclear Power Deployment

    SciTech Connect (OSTI)

    Harrison, Thomas J.

    2014-10-01

    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 and those key factors that may impact the deployment of AdvSMRs or any other new nuclear power plants. Thus, this report serves as a reference document for DOE as it moves forward with its plans to develop advanced reactors, including AdvSMRs. For the purpose of this analysis, information on electricity markets and nuclear power plant operating costs will be combined to examine the current state of the nuclear industry and the process required to successfully move forward with new nuclear power in general and AdvSMRs in particular. The current electricity market is generally unfavorable to new nuclear construction, especially in deregulated markets with heavy competition from natural gas and subsidized renewables. The successful and profitable operation of a nuclear power plant (or any power plant) requires the rate at which the electricity is sold to be sufficiently greater than the cost to operate. The wholesale rates in most US markets have settled into values that provide profits for most operating nuclear power plants but are too low to support the added cost of capital recovery for new nuclear construction. There is a strong geographic dependence on the wholesale rate, with some markets currently able to support new nuclear construction. However, there is also a strong geographic dependence on pronuclear public opinion; the areas where power prices are high tend to have unfavorable views on the construction of new nuclear power plants. The use of government-backed incentives, such as subsidies, can help provide a margin to help justify construction projects that otherwise may not seem viable. Similarly, low interest rates for the project will also add a positive margin to the economic analysis. In both cases, the profitable price point is decreased, making more markets open to profitable entry. Overall, the economic attractiveness of a nuclear power construction project is not only a function of its own costs, but a function of the market into which it is deployed. Many of the market characteristics are out of the control of the potential nuclear power plant operators. The decision-making process for the power industry in general is complicated by the short-term market volatility in both the wholesale electricity market and the commodity (natural gas) market. Decisions based on market conditions today may be rendered null and void in six months. With a multiple-year lead time, nuclear power plants are acutely vulnerable to market corrections.

  3. Example G Cost of construction of nuclear power plants Description of data

    E-Print Network [OSTI]

    Reid, Nancy

    Example G Cost of construction of nuclear power plants Description of data Table G.1 gives data it is possible that some manufacturer's subsidies might be hidden in the quoted capital costs. Table G.1 Data) CT Use of cooling tower (=1) BW Nuclear steam supply system manufactured by Babcock-Wilcox (=1) N

  4. Example G Cost of construction of nuclear power plants Description of data

    E-Print Network [OSTI]

    Reid, Nancy

    1 Example G Cost of construction of nuclear power plants Description of data Table G.1 gives and for which it is possible that some manufacturer's subsidies might be hidden in the quoted capital costs-east region (=1) CT Use of cooling tower (=1) BW Nuclear steam supply system manufactured by Babcock

  5. RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Yen, W.W.S.

    2010-01-01

    EMERGENCY PLANNING FOR NUCLEAR POWER PLANTS: THE LICENSINGEmergency Planning for Nuclear Power Plants Determination ofproposed nuclear power plants . . . . . . . . . • . . . .

  6. Alarm system for a nuclear control complex

    DOE Patents [OSTI]

    Scarola, Kenneth (Windsor, CT); Jamison, David S. (Windsor, CT); Manazir, Richard M. (North Canton, CT); Rescorl, Robert L. (Vernon, CT); Harmon, Daryl L. (Enfield, CT)

    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.

  7. Solar powered desalination system

    E-Print Network [OSTI]

    Mateo, Tiffany Alisa

    2011-01-01

    USA, Jacksonville, FL Jacksonville Solar Energy Generation Facility Constructed Systems that produce electricity

  8. Technical and Political Assessment of Peaceful Nuclear Power Program Prospects in North Africa and the

    E-Print Network [OSTI]

    Summary.........................................................................5 Country Reports Egypt and application of resources towards developing nuclear-generated electricity and nuclear-powered desalination

  9. Predicting the severity of nuclear power plant transients by using genetic and nearest neighbor algorithms

    SciTech Connect (OSTI)

    Lin, J.; Bartal, Y.; Uhrig, R.E.

    1995-03-01

    Nuclear power plant status is monitored by a human operator. To enhance the operator`s capability to diagnose the nuclear power plant status in case of a transient, several systems were developed to identify the type of the transient. Few of them addressed the further question: how severe is the transient? In this paper, we explore the possibility of predicting the severity of a transient using genetic algorithms and nearest neighbor algorithms after its type has been identified.

  10. Nuclear power plant status diagnostics using artificial neural networks

    SciTech Connect (OSTI)

    Bartlett, E.B. [Iowa State Univ. of Science and Technology, Ames, IA (United States). Dept. of Mechanical Engineering] [Iowa State Univ. of Science and Technology, Ames, IA (United States). Dept. of Mechanical Engineering; Uhrig, R.E. [Tennessee Univ., Knoxville, TN (United States). Dept. of Nuclear Engineering] [Tennessee Univ., Knoxville, TN (United States). Dept. of Nuclear Engineering

    1991-12-31

    In this work, the nuclear power plant operating status recognition issue is investigated using artificial neural networks (ANNs). The objective is to train an ANN to classify nuclear power plant accident conditions and to assess the potential of future work in the area of plant diagnostics with ANNS. To this end, an ANN was trained to recognize normal operating conditions as well as potentially unsafe conditions based on nuclear power plant training simulator generated accident scenarios. These scenarios include; hot and cold leg loss of coolant, control rod ejection, loss of offsite power, main steam line break, main feedwater line break and steam generator tube leak accidents. Findings show that ANNs can be used to diagnose and classify nuclear power plant conditions with good results.

  11. Nuclear power plant status diagnostics using artificial neural networks

    SciTech Connect (OSTI)

    Bartlett, E.B. (Iowa State Univ. of Science and Technology, Ames, IA (United States). Dept. of Mechanical Engineering); Uhrig, R.E. (Tennessee Univ., Knoxville, TN (United States). Dept. of Nuclear Engineering)

    1991-01-01

    In this work, the nuclear power plant operating status recognition issue is investigated using artificial neural networks (ANNs). The objective is to train an ANN to classify nuclear power plant accident conditions and to assess the potential of future work in the area of plant diagnostics with ANNS. To this end, an ANN was trained to recognize normal operating conditions as well as potentially unsafe conditions based on nuclear power plant training simulator generated accident scenarios. These scenarios include; hot and cold leg loss of coolant, control rod ejection, loss of offsite power, main steam line break, main feedwater line break and steam generator tube leak accidents. Findings show that ANNs can be used to diagnose and classify nuclear power plant conditions with good results.

  12. LIMITED POWER BURSTS IN DISTRIBUTED MODELS OF NUCLEAR REACTORS

    E-Print Network [OSTI]

    Bazhenov, Maxim

    LIMITED POWER BURSTS IN DISTRIBUTED MODELS OF NUCLEAR REACTORS M. V. Bazhenov and E. F. Sabaev UDC employed for analyzing reactor dynamics. Equations of this type are used for analyzing the stability of the reactor power, etc. Among these problems the question of the boundedness of reactor power bursts

  13. System Study: Emergency Power System 1998–2012

    SciTech Connect (OSTI)

    T. E. Wierman

    2013-10-01

    This report presents an unreliability evaluation of the emergency power system (EPS) at 104 U.S. commercial nuclear power plants. Demand, run hours, and failure data from fiscal year 1998 through 2012 for selected components were obtained from the Equipment Performance and Information Exchange (EPIX). The unreliability results are trended for the most recent 10 year period while yearly estimates for system unreliability are provided for the entire active period. A statistically significant increasing trend was identified for unreliability (8 hour model) as a function of fiscal year. No statistically significant decreasing trend was identified in the EPS results.

  14. Reactive Power Compensating System.

    DOE Patents [OSTI]

    Williams, Timothy J.; El-Sharkawi, Mohamed A.; Venkata, Subrahmanyam S.

    1985-01-04

    The circuit was designed for the specific application of wind-driven induction generators. It has great potential for application in any situation where a varying reactive power load is present, such as with induction motors or generators, or for transmission network compensation.

  15. Reactive power compensating system

    DOE Patents [OSTI]

    Williams, Timothy J. (Redondo Beach, CA); El-Sharkawi, Mohamed A. (Renton, WA); Venkata, Subrahmanyam S. (Seattle, WA)

    1987-01-01

    The reactive power of an induction machine is compensated by providing fixed capacitors on each phase line for the minimum compensation required, sensing the current on one line at the time its voltage crosses zero to determine the actual compensation required for each phase, and selecting switched capacitors on each line to provide the balance of the compensation required.

  16. Electric Power System Asset Optimization

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantityBonneville Power Administration would like submitKansas Nuclear ProfileMultiferroic Electric

  17. Solar powered desalination system

    E-Print Network [OSTI]

    Mateo, Tiffany Alisa

    2011-01-01

    Support System for Seawater Desalination Plants. TheRizzuti, Lucio. Seawater Desalination, Conventional andcosts of thermal seawater desalination plants…………………19

  18. ICENES '91:Sixth international conference on emerging nuclear energy systems

    SciTech Connect (OSTI)

    Not Available

    1991-01-01

    This document contains the program and abstracts of the sessions at the Sixth International Conference on Emerging Nuclear Energy Systems held June 16--21, 1991 at Monterey, California. These sessions included: The plenary session, fission session, fission and nonelectric session, poster session 1P; (space propulsion, space nuclear power, electrostatic confined fusion, fusion miscellaneous, inertial confinement fusion, [mu]-catalyzed fusion, and cold fusion); Advanced fusion session, space nuclear session, poster session 2P, (nuclear reactions/data, isotope separation, direct energy conversion and exotic concepts, fusion-fission hybrids, nuclear desalting, accelerator waste-transmutation, and fusion-based chemical recycling); energy policy session, poster session 3P (energy policy, magnetic fusion reactors, fission reactors, magnetically insulated inertial fusion, and nuclear explosives for power generation); exotic energy storage and conversion session; and exotic energy storage and conversion; review and closing session.

  19. Nuclear plant-aging research on reactor protection systems

    SciTech Connect (OSTI)

    Meyer, L.C.

    1988-01-01

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

  20. QUARTERLY NUCLEAR POWER DEPLOYMENT SUMMARY JULY 2014

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

    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...

  1. Configuration and technology implications of potential nuclear hydrogen system applications.

    SciTech Connect (OSTI)

    Conzelmann, G.; Petri, M.; Forsberg, C.; Yildiz, B.; ORNL

    2005-11-05

    Nuclear technologies have important distinctions and potential advantages for large-scale generation of hydrogen for U.S. energy services. Nuclear hydrogen requires no imported fossil fuels, results in lower greenhouse-gas emissions and other pollutants, lends itself to large-scale production, and is sustainable. The technical uncertainties in nuclear hydrogen processes and the reactor technologies needed to enable these processes, as well waste, proliferation, and economic issues must be successfully addressed before nuclear energy can be a major contributor to the nation's energy future. In order to address technical issues in the time frame needed to provide optimized hydrogen production choices, the Nuclear Hydrogen Initiative (NHI) must examine a wide range of new technologies, make the best use of research funding, and make early decisions on which technology options to pursue. For these reasons, it is important that system integration studies be performed to help guide the decisions made in the NHI. In framing the scope of system integration analyses, there is a hierarchy of questions that should be addressed: What hydrogen markets will exist and what are their characteristics? Which markets are most consistent with nuclear hydrogen? What nuclear power and production process configurations are optimal? What requirements are placed on the nuclear hydrogen system? The intent of the NHI system studies is to gain a better understanding of nuclear power's potential role in a hydrogen economy and what hydrogen production technologies show the most promise. This work couples with system studies sponsored by DOE-EE and other agencies that provide a basis for evaluating and selecting future hydrogen production technologies. This assessment includes identifying commercial hydrogen applications and their requirements, comparing the characteristics of nuclear hydrogen systems to those market requirements, evaluating nuclear hydrogen configuration options within a given market, and identifying the key drivers and thresholds for market viability of nuclear hydrogen options.

  2. Solar powered desalination system

    E-Print Network [OSTI]

    Mateo, Tiffany Alisa

    2011-01-01

    river, and be used to filter the water. The water producedppm. This system can filter natural sources of water such asstandard filter housing with the inlet concentrated water

  3. Solar powered desalination system

    E-Print Network [OSTI]

    Mateo, Tiffany Alisa

    2011-01-01

    Fundamentals of Salt Water Desalination. New York: Elsevier,7. Lightbucket. Large scale desalination: is there enoughSystem for Seawater Desalination Plants. The Netherlands:

  4. Power Systems Awards

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

    energy across nation at Department of Defense facilities, installed many assessment systems, and recommended energy procurement and installation guidelines. The product of the...

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

    Office of Energy Efficiency and Renewable Energy (EERE)

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

  6. TRANSMISSION SYSTEM ADEQUACY EVALUATION CONSIDERING WIND POWER

    E-Print Network [OSTI]

    Saskatchewan, University of

    TRANSMISSION SYSTEM ADEQUACY EVALUATION CONSIDERING WIND POWER Rajesh Karki Jaimin Patel Power to significantly increase renewable power penetration in electrical power systems. Wind power is the most important systems and large grid connected systems. Power generated by wind depends on the availability of the wind

  7. Nuclear Systems Technology | Nuclear Science | ORNL

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

    Cycle Systems Criticality Safety Irradiation Experiment Development and Execution Robotics & Remote Systems Engineering and Applications Thermal & Hydraulic Experiments &...

  8. 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)

  9. Risk Framework for the Next Generation Nuclear Power Plant Construction 

    E-Print Network [OSTI]

    Yeon, Jaeheum 1981-

    2012-12-11

    sector projects, and recently elevated to Best Practice status. However, its current format is inadequate to address the unique challenges of constructing the next generation of nuclear power plants (NPP). To understand and determine the risks...

  10. 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...

  11. Risk-informed incident management for nuclear power plants

    E-Print Network [OSTI]

    Smith, Curtis Lee, 1966-

    2002-01-01

    Decision making as a part of nuclear power plant operations is a critical, but common, task. Plant management is forced to make decisions that may have safety and economic consequences. Formal decision theory offers the ...

  12. Extra-terrestrial nuclear power stations : transportation and operation

    E-Print Network [OSTI]

    Kane, Susan Christine

    2005-01-01

    Many challenges exist when considering nuclear power to provide electricity for bases on the Moon or Mars, including launch safety, landing safety, deployment, control, and protecting the astronauts from radiation. Examples ...

  13. 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.

  14. The Handbook of Applied Bayesian Analysis, Eds: Tony O'Hagan & Mike West, Oxford University Bayesian analysis and decisions in nuclear power plant

    E-Print Network [OSTI]

    Popova, Elmira

    Bayesian analysis and decisions in nuclear power plant maintenance Elmira Popova, David Morton, Paul Damien are then applied to solving an important problem in a nuclear power plant system at the South Texas Project (STP) Electric Generation Station. STP is one of the newest and largest nuclear power plants in the US

  15. A Preliminary Report on Static Analysis of C Code for Nuclear Reactor Protection System

    E-Print Network [OSTI]

    A Preliminary Report on Static Analysis of C Code for Nuclear Reactor Protection System Jong: Cybersecurity regulations require new I&C (Instrumentation & Control) systems in nuclear power plants to develop if the C code is produced mechanically. Keywords: Nuclear Plant Protection System , I&C , PLC software

  16. Cognitive skill training for nuclear power plant operational decision making

    SciTech Connect (OSTI)

    Mumaw, R.J.; Swatzler, D.; Roth, E.M. [Westinghouse Electric Corp., Pittsburgh, PA (United States); Thomas, W.A. [Quantum Technologies, Inc., Oak Brook, IL (United States)

    1994-06-01

    Training for operator and other technical positions in the commercial nuclear power industry traditionally has focused on mastery of the formal procedures used to control plant systems and processes. However, decisionmaking tasks required of nuclear power plant operators involve cognitive skills (e.g., situation assessment, planning). Cognitive skills are needed in situations where formal procedures may not exist or may not be as prescriptive, as is the case in severe accident management (SAM). The Westinghouse research team investigated the potential cognitive demands of SAM on the control room operators and Technical Support Center staff who would be most involved in the selection and execution of severe accident control actions. A model of decision making, organized around six general cognitive processes, was developed to identify the types of cognitive skills that may be needed for effective performance. Also, twelve SAM scenarios were developed to reveal specific decision-making difficulties. Following the identification of relevant cognitive skills, 19 approaches for training individual and team cognitive skills were identified. A review of these approaches resulted in the identification of general characteristics that are important in effective training of cognitive skills.

  17. 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

  18. Nuclear power and climate change | The Bulletin Online http://www.thebulletin.org/roundtable/nuclear-power-climate-change/ 1 of 11 9/25/07 2:14 PM

    E-Print Network [OSTI]

    Berry, R. Stephen

    Nuclear power and climate change | The Bulletin Online http://www.thebulletin.org/roundtable/nuclear-power-climate-change/ 1 of 11 9/25/07 2:14 PM ROUNDTABLE Roundtable > Nuclear power and climate change Nuclear power, experts argue that all options should be considered--including nuclear power. But with nuclear power comes

  19. Pantex Occupational Health System (OHS), National Nuclear Security...

    Energy Savers [EERE]

    Pantex Occupational Health System (OHS), National Nuclear Security Administration Pantex Site Office Pantex Occupational Health System (OHS), National Nuclear Security...

  20. Prognostics and Health Management in Nuclear Power Plants: A Review of Technologies and Applications

    SciTech Connect (OSTI)

    Coble, Jamie B.; Ramuhalli, Pradeep; Bond, Leonard J.; Hines, Wes; Upadhyaya, Belle

    2012-07-17

    This report reviews the current state of the art of prognostics and health management (PHM) for nuclear power systems and related technology currently applied in field or under development in other technological application areas, as well as key research needs and technical gaps for increased use of PHM in nuclear power systems. The historical approach to monitoring and maintenance in nuclear power plants (NPPs), including the Maintenance Rule for active components and Aging Management Plans for passive components, are reviewed. An outline is given for the technical and economic challenges that make PHM attractive for both legacy plants through Light Water Reactor Sustainability (LWRS) and new plant designs. There is a general introduction to PHM systems for monitoring, fault detection and diagnostics, and prognostics in other, non-nuclear fields. The state of the art for health monitoring in nuclear power systems is reviewed. A discussion of related technologies that support the application of PHM systems in NPPs, including digital instrumentation and control systems, wired and wireless sensor technology, and PHM software architectures is provided. Appropriate codes and standards for PHM are discussed, along with a description of the ongoing work in developing additional necessary standards. Finally, an outline of key research needs and opportunities that must be addressed in order to support the application of PHM in legacy and new NPPs is presented.

  1. Solar-powered cooling system

    DOE Patents [OSTI]

    Farmer, Joseph C

    2013-12-24

    A solar-powered adsorption-desorption refrigeration and air conditioning system uses nanostructural materials made of high specific surface area adsorption aerogel as the adsorptive media. Refrigerant molecules are adsorbed on the high surface area of the nanostructural material. A circulation system circulates refrigerant from the nanostructural material to a cooling unit.

  2. 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"...

  3. 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.

  4. Nuclear power plant control room operator control and monitoring tasks

    SciTech Connect (OSTI)

    Bovell, C.R.; Beck, M.G. [Concord Associates, Inc., Knoxville, TN (United States); Carter, R.J. [Oak Ridge National Labs., TN (United States)

    1998-07-01

    Oak Ridge National Laboratory is conducting a research project the purpose of which is to develop the technical bases for regulatory review criteria for use in evaluating the safety implications of human factors associated with the use of artificial intelligence and expert systems, and with advanced instrumentation and control (I and C) systems in nuclear power plants (NPP). This report documents the results from Task 8 of that project. The primary objectives of the task was to identify the scope and type of control and monitoring tasks now performed by control-room operators. Another purpose was to address the types of controls and safety systems needed to operate the nuclear plant. The final objective of Task 8 was to identify and categorize the type of information and displays/indicators required to monitor the performance of the control and safety systems. This report also discusses state-of-the-art controls and advanced display devices which will be available for use in control-room retrofits and in control room of future plants. The fundamental types of control and monitoring tasks currently conducted by operators can be divided into four classifications: function monitoring tasks, control manipulation tasks, fault diagnostic tasks, and administrative tasks. There are three general types of controls used in today`s NPPs, switches, pushbuttons, and analog controllers. Plant I and C systems include components to achieve a number of safety-related functions: measuring critical plant parameters, controlling critical plant parameters within safety limits, and automatically actuating protective devices if safe limits are exceeded. The types of information monitored by the control-room operators consist of the following parameters: pressure, fluid flow and level, neutron flux, temperature, component status, water chemistry, electrical, and process and area radiation. The basic types of monitoring devices common to nearly all NPP control rooms include: analog meters, graphic recorders, digital displays and counters, light indicators, visual and audio alarms, and cathode-ray tubes.

  5. Sandia Energy - Nuclear Power & Engineering

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Homesum_a_epg0_fpd_mmcf_m.xls" ,"Available from WebQuantity of NaturalDukeWakefieldSulfateSciTechtail.Theory ofDid youOxygenLaboratory Fellows Jerry Simmons IsNationalNuclearNuclear

  6. Developing Secure Power Systems Professional Competence: Alignment...

    Energy Savers [EERE]

    Developing Secure Power Systems Professional Competence: Alignment and Gaps in Workforce Development Programs - Phase 2 (JulyAugust 2013) Developing Secure Power Systems...

  7. Standard practice for evaluation of surveillance capsules from light-water moderated nuclear power reactor vessels

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2010-01-01

    Standard practice for evaluation of surveillance capsules from light-water moderated nuclear power reactor vessels

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

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

    Top 6 Things You Didn't Know About Nuclear Power Top 6 Things You Didn't Know About Nuclear Power December 12, 2014 - 10:39am Addthis These are the first lightbulbs lit by nuclear...

  9. The CMS Detector Power System

    E-Print Network [OSTI]

    Lusin, S

    2008-01-01

    The power system for the on-detector electronics of the CMS Experiment comprises approximately 12000 low voltage channels, with a total power requirement of 1.1 MVA. The radiation environment inside the CMS experimental cavern combined with an ambient magnetic field (reaching up to 1.3 kGauss at the detector periphery) severely limit the available choices of low voltage supplies, effectively ruling out the use of commercial off-the-shelf DC power supplies. Typical current requirements at the CMS detector front end range from 1A-30A per channel at voltages ranging between 1.25V and 8V. This requires in turn that the final stage of the low voltage power supply be located on the detector periphery. Power to the CMS front-end electronics is stabilized by a 2 MVA uninterruptible power supply (UPS) located in a CMS surface building. This UPS isolates the CMS detector from disturbances on the local power grid and provides for 2 minutes of autonomy following a power failure, allowing for an orderly shutdown of detect...

  10. Space nuclear-power reactor design based on combined neutronic and thermal-fluid analyses

    SciTech Connect (OSTI)

    Koenig, D.R.; Gido, R.G.; Brandon, D.I.

    1985-01-01

    The design and performance analysis of a space nuclear-power system requires sophisticated analytical capabilities such as those developed during the nuclear rocket propulsion (Rover) program. In particular, optimizing the size of a space nuclear reactor for a given power level requires satisfying the conflicting requirements of nuclear criticality and heat removal. The optimization involves the determination of the coolant void (volume) fraction for which the reactor diameter is a minimum and temperature and structural limits are satisfied. A minimum exists because the critical diameter increases with increasing void fraction, whereas the reactor diameter needed to remove a specified power decreases with void fraction. The purpose of this presentation is to describe and demonstrate our analytical capability for the determination of minimum reactor size. The analysis is based on combining neutronic criticality calculations with OPTION-code thermal-fluid calculations.

  11. Electromagnetic pulse (EMP) interaction with electric power systems. Power Systems Technology Program. Final report

    SciTech Connect (OSTI)

    Zaininger, H.W.

    1984-08-01

    A high altitude nuclear burst, detonated at a height of 50 km or more, causes two types of electromagnetic pulses (EMP) - high altitude EMP (HEMP) and magnetohydrodynamic EMP (MHD-EMP). This high altitude EMP scenario is of principal concern when assessing the effects of EMP on electric power systems, because the total United States can be simultaneously illuminated by HEMP and MHD-EMP can cover a large area of up to several hundred kilometers in diameter. The purpose of this project was first to define typical electrical power system characteristics for EMP analysis, and second, to determine reasonable worst case EMP induced surges on overhead electric power system transmission and distribution lines for reasonable assumptions, using unclassified HEMP and MHD-EMP electric field waveforms.

  12. The potential for a nuclear renaissance : the development of nuclear power under climate change mitigation policies

    E-Print Network [OSTI]

    Osouf, Nicolas

    2007-01-01

    Anthropogenic emissions of greenhouse gases are very likely to have already changed the Earth's climate, and will continue to change it for centuries if no action is taken. Nuclear power, a nearly carbon-free source of ...

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

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

    October 22, 2012, Dominion Resources Inc. announced that it would close and decommission its Kewaunee Power Station located in Carlton, Wis. after failing to find a buyer for the...

  14. The Decline and Death of Nuclear Power

    E-Print Network [OSTI]

    Melville, Jonathan

    2013-01-01

    power as an energy source, as compared to Germany, France,and solar energy. While in some countries, like Germany andto meet rising energy demands. In Germany, 88% of the

  15. Nuclear Norm Regularization for Overparametrized Hammerstein Systems

    E-Print Network [OSTI]

    Nuclear Norm Regularization for Overparametrized Hammerstein Systems Tillmann Falck, Johan A relaxation we propose the use of nuclear norms [2], instead of using ridge regression. On several simple a generalization performance close to the one obtained by nuclear norms. I. INTRODUCTION The identification

  16. Nuclear Technology & Canadian Oil Sands: Integration of Nuclear Power with In-Situ Oil Extraction

    E-Print Network [OSTI]

    Nuclear Technology & Canadian Oil Sands: Integration of Nuclear Power with In-Situ Oil Extraction A for a Canadian oil sands extraction facility using Steam-Assisted Gravity Drainage (SAGD) technology. The energy to produce steam as well as electricity for the oil sands facility; and (3) using the reactor to produce

  17. Nuclear Power - Deployment, Operation and Sustainability 

    E-Print Network [OSTI]

    2011-01-01

    a f t and surfa c e vesse l s . Even though speci a l snorke l devic e s were used to suck and exhaus t air to the subm a r i n e shallowl y submerge d below the water's surfac e, a nuclear reactor provides it with a theor e t i c a l l y infin i... t e su bmersion time. In addition, the high specific energy, or energy per unit weight of nuclear fuel, eliminat e s the need for consta n t refuel i n g by fleets of vulner a b l e tanke r s follo w i n g a fleet of surfa c e or subsur f a c e...

  18. Power Spectrum Analyses of Nuclear Decay Rates

    E-Print Network [OSTI]

    Javorsek, D; Lasenby, R N; Lasenby, A N; Buncher, J B; Fischbach, E; Gruenwald, J T; Hoft, A W; Horan, T J; Jenkins, J H; Kerford, J L; Lee, R H; Longman, A; Mattes, J J; Morreale, B L; Morris, D B; Mudry, R N; Newport, J R; O'Keefe, D; Petrelli, M A; Silver, M A; Stewart, C A; Terry, B; 10.1016/j.astropartphys.2010.06.011

    2010-01-01

    We provide the results from a spectral analysis of nuclear decay data displaying annually varying periodic fluctuations. The analyzed data were obtained from three distinct data sets: 32Si and 36Cl decays reported by an experiment performed at the Brookhaven National Laboratory (BNL), 56Mn decay reported by the Children's Nutrition Research Center (CNRC), but also performed at BNL, and 226Ra decay reported by an experiment performed at the Physikalisch-Technische Bundesanstalt (PTB) in Germany. All three data sets exhibit the same primary frequency mode consisting of an annual period. Additional spectral comparisons of the data to local ambient temperature, atmospheric pressure, relative humidity, Earth-Sun distance, and their reciprocals were performed. No common phases were found between the factors investigated and those exhibited by the nuclear decay data. This suggests that either a combination of factors was responsible, or that, if it was a single factor, its effects on the decay rate experiments are n...

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

    SciTech Connect (OSTI)

    Leishear, R

    2010-05-02

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

  20. Reliability Engineering and System Safety 92 (2007) 609618 The nuclear industry's transition to risk-informed regulation and

    E-Print Network [OSTI]

    2007-01-01

    , USA b Nuclear Power Engineering, Quality and Safety Management Department, Tokyo Electric Power improvement in safety based on Institute of Nuclear Power Operations (INPO) performance indicatorsReliability Engineering and System Safety 92 (2007) 609­618 The nuclear industry's transition

  1. Design, Analysis and Optimization of the Power Conversion System for the Modular Pebble Bed Reactor System

    E-Print Network [OSTI]

    Design, Analysis and Optimization of the Power Conversion System for the Modular Pebble Bed Reactor August 31, 2003 Certified by Ronald G. Ballinger Professor of Nuclear Engineering and Materials Science;2 #12;Design, Analysis, and Optimization of the Power Conversion System for the Modular Pebble Bed

  2. UNCLASSIFIED Nuclear Materials Management & Safeguards System

    National Nuclear Security Administration (NNSA)

    Nuclear Materials Management & Safeguards System CHANGE OF PROJECT NUMBER UPDATE PROJECT Project Number: Title: Date Valid: Date Deactivated: Classification Codes: Project Number:...

  3. Mapping Complexity Sources in Nuclear Power Plant Domains Understanding the sources of complexity in advanced Nuclear Power Plant (NPP) control rooms and their

    E-Print Network [OSTI]

    Cummings, Mary "Missy"

    Mapping Complexity Sources in Nuclear Power Plant Domains Understanding the sources of complexity in advanced Nuclear Power Plant (NPP) control rooms and their effects on human reliability is critical of complexity leveraging network theory. INTRODUCTION The nuclear power industry in United States has declined

  4. Design tool needs for space nuclear propulsion systems

    SciTech Connect (OSTI)

    Klein, A.C. (Oregon State Univ., Corvallis (United States)); Lewis, B.R. (Atom Analysis, Inc., Portland, OR (United States))

    1992-01-01

    The interest in a return trip for humans to the moon and a pioneering voyage to Mars has rekindled interest in the use of nuclear reactors to provide propulsion for both piloted and robotic space vehicles. Two types of nuclear reactor-based propulsion systems are currently envisioned: nuclear thermal propulsion (NTP) and nuclear electric propulsion (NEP). The former relies on the direct heating and exhaust of a propellant within the core of the reactor, while the latter utilizes ion thruster engines for propulsion, and the nuclear reactor supplies the large amount of electrical power required to drive the engines. Another direct contrast between the NTP and NEP concepts is the length of reactor operation. The NTP nuclear rocket core is required to produce large amounts of thermal power for relatively short bursts (on the order of minutes to hours), and the NEP reactor core operates for a much longer period of time (on the order of days to months) with a steady-state electrical power output. The design of these types of nuclear reactor systems requires the use of specific analysis tools, some of which already exist and others that need considerable development. The general areas in which design tools are needed in the development of systems for space nuclear propulsion include the following: (1) neutronics design - both steady-state and transient applications including thermal feedback effects; (2) thermal-hydraulics design - again, both steady-state and transient applications with coupling to and from the neutronics design codes; (3) materials analysis tools - due to the high temperatures and high stresses required for efficient propulsion operation, increased importance will be placed on understanding the material responses; and (4) systems analysis - these codes allow optimizaiton of the entire propulsion system.

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

    DOE Patents [OSTI]

    Prelas, Mark A. (Columbia, MO)

    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.

  6. Scoping calculations of power sources for nuclear electric propulsion

    SciTech Connect (OSTI)

    Difilippo, F.C. [Oak Ridge National Lab., TN (United States)] [Oak Ridge National Lab., TN (United States)

    1994-05-01

    This technical memorandum describes models and calculational procedures to fully characterize the nuclear island of power sources for nuclear electric propulsion. Two computer codes were written: one for the gas-cooled NERVA derivative reactor and the other for liquid metal-cooled fuel pin reactors. These codes are going to be interfaced by NASA with the balance of plant in order to making scoping calculations for mission analysis.

  7. 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.

  8. Nuclear power for energy and for scientific progress

    E-Print Network [OSTI]

    Giacomelli, G

    2012-01-01

    The Introduction in this paper underlines the present general situation for energy and the environment using the words of the US Secretary of Energy. A short presentation is made of some major nuclear power plants used to study one fundamental parameter for neutrino oscillations. The nuclear power status in some Far East Nations is summarized. The 4th generation of nuclear power stations, with emphasis on Fast Neutron Reactors, is recollected. The world consumptions of all forms of energies is recalled, fuel reserves are considered and the opportunities for a sustainable energy future is discussed. These considerations are applied to the italian situation, which is rather peculiar, also due to the many consequencies of the strong Nimby effects in Italy.

  9. OE Power Systems Engineering Research & Development Program Partnershi...

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

    Mission Power Systems Engineering Research and Development OE Power Systems Engineering Research & Development Program Partnerships OE Power Systems Engineering Research &...

  10. Catalog of DC Appliances and Power Systems

    SciTech Connect (OSTI)

    Garbesi, Karina; Vossos, Vagelis; Shen, Hongxia

    2010-10-13

    This document catalogs the characteristics of current and potential future DC products and power systems.

  11. 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.

  12. Addressing employee concerns about welding in a nuclear power plant

    SciTech Connect (OSTI)

    Danko, J.C.; Hansen, D.D.; O'Leary, P.D.

    1988-03-01

    A leading utility contracted with EG and G Idaho to perform a comprehensive, independent evaluation of the utility's welding program with respect to the safety-related welds made at one of its nuclear power plants. The purpose of this paper is to review a number of the employee concerns and the technical basis for the disposition of these concerns. In addition, recommendations are presented that may help to prevent the recurrence of employee concerns in future nuclear power plant construction, and thereby costly delays may be avoided and welding productivity and quality improved.

  13. Future Power Systems 21 - The Smart Customer | Department of...

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

    Future Power Systems 21 - The Smart Customer Future Power Systems 21 - The Smart Customer Future Power Systems 21 - The Smart Customer: From Future Power Systems (FPS) articles 18...

  14. Power Spectrum Analyses of Nuclear Decay Rates

    E-Print Network [OSTI]

    D. Javorsek II; P. A. Sturrock; R. N. Lasenby; A. N. Lasenby; J. B. Buncher; E. Fischbach; J. T. Gruenwald; A. W. Hoft; T. J. Horan; J. H. Jenkins; J. L. Kerford; R. H. Lee; A. Longman; J. J. Mattes; B. L. Morreale; D. B. Morris; R. N. Mudry; J. R. Newport; D. O'Keefe; M. A. Petrelli; M. A. Silver; C. A. Stewart; B. Terry

    2010-07-06

    We provide the results from a spectral analysis of nuclear decay data displaying annually varying periodic fluctuations. The analyzed data were obtained from three distinct data sets: 32Si and 36Cl decays reported by an experiment performed at the Brookhaven National Laboratory (BNL), 56Mn decay reported by the Children's Nutrition Research Center (CNRC), but also performed at BNL, and 226Ra decay reported by an experiment performed at the Physikalisch-Technische Bundesanstalt (PTB) in Germany. All three data sets exhibit the same primary frequency mode consisting of an annual period. Additional spectral comparisons of the data to local ambient temperature, atmospheric pressure, relative humidity, Earth-Sun distance, and their reciprocals were performed. No common phases were found between the factors investigated and those exhibited by the nuclear decay data. This suggests that either a combination of factors was responsible, or that, if it was a single factor, its effects on the decay rate experiments are not a direct synchronous modulation. We conclude that the annual periodicity in these data sets is a real effect, but that further study involving additional carefully controlled experiments will be needed to establish its origin.

  15. Power transaction issues in deregulated power systems 

    E-Print Network [OSTI]

    Roycourt, Henrik

    2000-01-01

    is to review the power flow problem and the newly emerging concept of Available Transfer Capability (ATC) / Total Transfer Capability (TTC). Secondly, it aims at reviewing and implementing in the Matlab environment a technique for tracing the contributions...

  16. Artificial Neural Network for Optimized Power System Management

    E-Print Network [OSTI]

    OLeary, Daniel Albert

    2015-01-01

    nineteen percent), and hydroelectric power (seven percent) [rich countries. • Hydroelectric power is ideal in many ways,like hydroelectric dams, the construction of nuclear power

  17. Power system applications for PASC converter systems

    SciTech Connect (OSTI)

    Donnelly, M.K.; Johnson, R.M.

    1994-04-01

    This paper shows, using computer EMTP simulations, some preliminary results of applying pulse amplitude synthesis and control (PASC) technology to single-source level voltage converter system. The method can be applied to any single terminal pair source with appropriate modifications in power extraction interface and computer control program to match source and load impedance characteristics. The PASC realization as discussed here employs banks of transformers, one bank per phase, in which the primaries are connected in parallel through a switch matrix to the dc source. Two opposite polarity primaries per transformer are pulsed alternatively in time to produce an oscillatory sinusoidal output waveform. PASC conversion system capabilities to produce both leading and lagging power factor power output in single-phase and three-phase {Delta} or Y configurations are illustrated. EMTP simulations are used to demonstrate the converter capabilities. Also included are discussions regarding harmonics and potential control strategies to adapt the converter to an application or to minimize harmonics.

  18. An Integrated Scheme for Anomaly Identification and Automatic Control of Nuclear Power Plants Xin Jin, Robert M. Edwards and Asok Ray

    E-Print Network [OSTI]

    Ray, Asok

    An Integrated Scheme for Anomaly Identification and Automatic Control of Nuclear Power Plants Xin.edu INTRODUCTION Nuclear Power Plants (NPPs) are complex systems with many variables that require adjustment to the NPP. METHODOLOGY This proposed integrated scheme consists of three inter-related subsystems: Nuclear

  19. 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.

  20. 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.

  1. Comparative analysis of United States and French nuclear power plant siting and construction regulatory policies and their economic consequences

    E-Print Network [OSTI]

    Golay, Michael Warren.

    1977-01-01

    Despite the substantial commitments of time and money which are devoted to the nuclear power plant siting process, the effectiveness of the system in providing a balanced evaluation of the technical, environmental and ...

  2. TheHighCostofNuclearPower Why America Should Choose a Clean Energy Future

    E-Print Network [OSTI]

    Laughlin, Robert B.

    . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 Nuclear Power Companies are Counting on Consumers and Taxpayers to Bear the Risks of ReactorTheHighCostofNuclearPower Why America Should Choose a Clean Energy Future Over New Nuclear Reactors, CalPIRG Education Fund March 2009 The High Cost of Nuclear Power Why America Should Choose a Clean

  3. Nuclear Power: A Price Worth Paying For A Stable Climate? Will Cavendish & Robert Gross

    E-Print Network [OSTI]

    Nuclear Power: A Price Worth Paying For A Stable Climate? Will Cavendish & Robert Gross Thanks to the recent troubles at Sellafield, nuclear power has been in the news again. But focussing on BNFL alone." The case for nuclear is simple: nuclear power is CO2 free and its waste can be reprocessed. It already

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

    SciTech Connect (OSTI)

    Myers, Carl W [Los Alamos National Laboratory; Elkins, Ned Z [Los Alamos National Laboratory

    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.

  5. Distributed Power Delivery for Energy Efficient and Low Power Systems

    E-Print Network [OSTI]

    Friedman, Eby G.

    Distributed Power Delivery for Energy Efficient and Low Power Systems Selc¸uk K¨ose Department are needed to determine the location of these on-chip power supplies and decoupling capacitors. In this paper, the optimal location of the power supplies and decoupling capacitors is determined for different size

  6. 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.

  7. Electromagnetic pulse research on electric power systems: Program summary and recommendations. Power Systems Technology Program

    SciTech Connect (OSTI)

    Barnes, P.R.; McConnell, B.W.; Van Dyke, J.W. [Oak Ridge National Lab., TN (United States); Tesche, F.M. [Tesche (F.M.), Dallas, TX (United States); Vance, E.F. [Vance (E.F.), Fort Worth, TX (United States)

    1993-01-01

    A single nuclear detonation several hundred kilometers above the central United States will subject much of the nation to a high-altitude electromagnetic pulse (BENT). This pulse consists of an intense steep-front, short-duration transient electromagnetic field, followed by a geomagnetic disturbance with tens of seconds duration. This latter environment is referred to as the magnetohydrodynamic electromagnetic pulse (NMENT). Both the early-time transient and the geomagnetic disturbance could impact the operation of the nation`s power systems. Since 1983, the US Department of Energy has been actively pursuing a research program to assess the potential impacts of one or more BENT events on the nation`s electric energy supply. This report summarizes the results of that program and provides recommendations for enhancing power system reliability under HENT conditions. A nominal HENP environment suitable for assessing geographically large systems was developed during the program and is briefly described in this report. This environment was used to provide a realistic indication of BEMP impacts on electric power systems. It was found that a single high-altitude burst, which could significantly disturb the geomagnetic field, may cause the interconnected power network to break up into utility islands with massive power failures in some areas. However, permanent damage would be isolated, and restoration should be possible within a few hours. Multiple bursts would likely increase the blackout areas, component failures, and restoration time. However, a long-term blackout of many months is unlikely because major power system components, such as transformers, are not likely to be damaged by the nominal HEND environment. Moreover, power system reliability, under both HENT and normal operating conditions, can be enhanced by simple, and often low cost, modifications to current utility practices.

  8. US nuclear power plant operating cost and experience summaries

    SciTech Connect (OSTI)

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

    1998-02-01

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

  9. POWER SYSTEMS STABILITY WITH LARGE-SCALE WIND POWER PENETRATION

    E-Print Network [OSTI]

    Bak-Jensen, Birgitte

    of offshore wind farms, wind power fluctuations may introduce several challenges to reliable power system behaviour due to natural wind fluctuations. The rapid power fluctuations from the large scale wind farms Generation Control (AGC) system which includes large- scale wind farms for long-term stability simulation

  10. 2002CALIFORNIAPOWERMIX 2002 NET SYSTEM POWER CALCULATION

    E-Print Network [OSTI]

    the generation back to specific generators, and thereby claim that the electricity offered for sale to retail of their power as net system power. What is Net System Power? Net system power is "the mix of electricity fuel the previous calendar year in each of the statute's fuel type categories. Imports of out-of-state generation

  11. RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Nero, A.V.

    2010-01-01

    the possible risk from nuclear power . it . is sufficient tothe Cancer Risk Due to Nuclear-Electric Power Generation",of Accident Risks in U.S. Commercial Nuclear Power Plants",

  12. RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Nero, A.V.

    2010-01-01

    in U. S. Conunercial Nuclear Power Plants", Report WASH-Related Standards for Nuclear Power Plants," by A.V. NeroResponse Planning for Nuclear Power Plants in California,"

  13. Power Electronic Thermal System Performance and Integration ...

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

    May 18-22, 2009 -- Washington D.C. ape13bennion.pdf More Documents & Publications Power Electronic Thermal System Performance and Integration Integrated Power Module...

  14. Aerial Radiation Measurements from the Fukushima Dai-ichi Nuclear Power Plant Accident

    SciTech Connect (OSTI)

    Guss, P. P.

    2012-07-16

    This document is a slide show type presentation concerning DOE and Aerial Measuring System (AMS) activities and results with respect to assessing the consequences of the releases from the Fukushima Dai-ichi Nuclear Power Plant. These include ground monitoring and aerial monitoring.

  15. 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.

  16. 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.

  17. Neural network recognition of nuclear power plant transients

    SciTech Connect (OSTI)

    Bartlett, E.B.; Danofsky, R.; Adams, J.; AlJundi, T.; Basu, A.; Dhanwada, C.; Kerr, J.; Kim, K.; Lanc, T.

    1993-02-23

    The objective of this report is to describe results obtained during the first year of funding that will lead to the development of an artificial neural network (ANN) fault - diagnostic system for the real - time classification of operational transients at nuclear power plants. The ultimate goal of this three-year project is to design, build, and test a prototype diagnostic adviser for use in the control room or technical support center at Duane Arnold Energy Center (DAEC); such a prototype could be integrated into the plant process computer or safety - parameter display system. The adviser could then warn and inform plant operators and engineers of plant component failures in a timely manner. This report describes the work accomplished in the first of three scheduled years for the project. Included herein is a summary of the first year's results as, well as individual descriptions of each of the major topics undertaken by the researchers. Also included are reprints of the articles written under this funding as well as those that were published during the funded period.

  18. 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.

  19. Modeling Power Systems as Complex Adaptive Systems

    SciTech Connect (OSTI)

    Chassin, David P.; Malard, Joel M.; Posse, Christian; Gangopadhyaya, Asim; Lu, Ning; Katipamula, Srinivas; Mallow, J V.

    2004-12-30

    Physical analogs have shown considerable promise for understanding the behavior of complex adaptive systems, including macroeconomics, biological systems, social networks, and electric power markets. Many of today's most challenging technical and policy questions can be reduced to a distributed economic control problem. Indeed, economically based control of large-scale systems is founded on the conjecture that the price-based regulation (e.g., auctions, markets) results in an optimal allocation of resources and emergent optimal system control. This report explores the state-of-the-art physical analogs for understanding the behavior of some econophysical systems and deriving stable and robust control strategies for using them. We review and discuss applications of some analytic methods based on a thermodynamic metaphor, according to which the interplay between system entropy and conservation laws gives rise to intuitive and governing global properties of complex systems that cannot be otherwise understood. We apply these methods to the question of how power markets can be expected to behave under a variety of conditions.

  20. NUCLEAR ENERGY SYSTEM COST MODELING

    SciTech Connect (OSTI)

    Francesco Ganda; Brent Dixon

    2012-09-01

    The U.S. Department of Energy’s Fuel Cycle Technologies (FCT) Program is preparing to perform an evaluation of the full range of possible Nuclear Energy Systems (NES) in 2013. These include all practical combinations of fuels and transmuters (reactors and sub-critical systems) in single and multi-tier combinations of burners and breeders with no, partial, and full recycle. As part of this evaluation, Levelized Cost of Electricity at Equilibrium (LCAE) ranges for each representative system will be calculated. To facilitate the cost analyses, the 2009 Advanced Fuel Cycle Cost Basis Report is being amended to provide up-to-date cost data for each step in the fuel cycle, and a new analysis tool, NE-COST, has been developed. This paper explains the innovative “Island” approach used by NE-COST to streamline and simplify the economic analysis effort and provides examples of LCAE costs generated. The Island approach treats each transmuter (or target burner) and the associated fuel cycle facilities as a separate analysis module, allowing reuse of modules that appear frequently in the NES options list. For example, a number of options to be screened will include a once-through uranium oxide (UOX) fueled light water reactor (LWR). The UOX LWR may be standalone, or may be the first stage in a multi-stage system. Using the Island approach, the UOX LWR only needs to be modeled once and the module can then be reused on subsequent fuel cycles. NE-COST models the unit operations and life cycle costs associated with each step of the fuel cycle on each island. This includes three front-end options for supplying feedstock to fuel fabrication (mining/enrichment, reprocessing of used fuel from another island, and/or reprocessing of this island’s used fuel), along with the transmuter and back-end storage/disposal. Results of each island are combined based on the fractional energy generated by each islands in an equilibrium system. The cost analyses use the probability distributions of key parameters and employs Monte Carlo sampling to arrive at an island’s cost probability density function (PDF). When comparing two NES to determine delta cost, strongly correlated parameters can be cancelled out so that only the differences in the systems contribute to the relative cost PDFs. For example, one comparative analysis presented in the paper is a single stage LWR-UOX system versus a two-stage LWR-UOX to LWR-MOX system. In this case, the first stage of both systems is the same (but with different fractional energy generation), while the second stage of the UOX to MOX system uses the same type transmuter but the fuel type and feedstock sources are different. In this case, the cost difference between systems is driven by only the fuel cycle differences of the MOX stage.

  1. Long-Term Planning for Nuclear Energy Systems Under Deep Uncertainty

    E-Print Network [OSTI]

    Kim, Lance Kyungwoo

    2011-01-01

    efficiency given the expected high demand for nuclear energyefficiency. In Chapter 2, an overview of nuclear energyNUCLEAR ENERGY SYSTEM MODEL Table 5.2: Baseline Reactor Parameters Parameter UOX CFR BFR Reactor Power (GW th ) Capacity Factor Thermal Efficiency

  2. Nuclear Power - Control, Reliability and Human Factors 

    E-Print Network [OSTI]

    2011-01-01

    Reliability K s e n i i a Sapoz h n i k o v a and Roald Tayma n o v D.I.Mendeleyev Institute for Metrology, Russia 1. Introduction At present, a great number of embedded sens o r devi c es provi d e monito r i n g of operat i n g condi t io n... s and state of equi p me n t , includ i n g nucle a r react o r s of power plant s . The metrol o gi c a l reliab i li t y of meas uri n g instrum e n t s built in equi p me n t deter mi n e s the valid i t y of measure me nt infor ma t i o n . The qualit y...

  3. Use of artificial intelligence to enhance the safety of nuclear power plants

    SciTech Connect (OSTI)

    Uhrig, R.E.

    1988-01-01

    In the operation of a nuclear power plant, the sheer magnitude of the number of process parameters and systems interactions poses difficulties for the operators, particularly during abnormal or emergency situations. Recovery from an upset situation depends upon the facility with which the available raw data can be converted into and assimilated as meaningful knowledge. Plant personnel are sometimes affected by stress and emotion, which may have varying degrees of influence on their performance. Expert systems can take some of the uncertainty and guesswork out of their decisions by providing expert advice and rapid access to a large information base. Application of artificial intelligence technologies, particularly expert systems, to control room activities in a nuclear power plant has the potential to reduce operator error and improve power plant safety and reliability. 12 refs.

  4. Peach Bottom and Vermont Yankee Nuclear Power Plants

    SciTech Connect (OSTI)

    NONE

    1992-12-31

    A dramatic and extraordinary instance of state and local government control of nuclear power, the purchase by New York of the Shoreham plant is nonetheless indicative of the political demands that some states confront for additional involvement in the regulation of the radiological hazards associated with commercial nuclear power plants. Although the Supreme Court has appeared to expand, in the eight years since PG&E and Silkwood, the acceptable extent of state regulation, some states, in addition to New York, have acquired, with the acquiescence of the NRC, a degree of involvement that exceeds the role for state and local governments provided by the Court. For example, the Commonwealth of Pennsylvania concluded with the Philadelphia Electric Company (PECO) in June 1989 an agreement that commits PECO to various initiatives, not otherwise required under NRC regulations, for the safe operation of the Peach Bottom nuclear power plant in Pennsylvania. In July 1991 the State of Vermont and Vermont Yankee Nuclear Power Corporation (Vermont Yankee) concluded an agreement similar to that concluded between Pennsylvania and PECO. The agreement also commits Vermont Yankee to certain initiatives, not otherwise required under NRC regulations, related to its operation of the Vermont Yankee nuclear power plant in Vermont. The agreement was precipitated by a challenge to an application, submitted to the NRC by Vermont Yankee in April 1989, to amend the Vermont Yankee plant license to extend its expiration date from December 11, 2007 to March 21, 2012. The amendment would allow the Vermont Yankee plant to operate for forty full years.

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

    SciTech Connect (OSTI)

    NONE

    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.

  6. Nuclear PowerNuclear PowerNuclear PowerNuclear PowerNuclear PowerNuclear PowerNuclear PowerNuclear Power''''''''s Dirty Littles Dirty Littles Dirty Littles Dirty Littles Dirty Littles Dirty Littles Dirty Littles Dirty Little Secret: Uranium MiningSecret:

    E-Print Network [OSTI]

    Sheridan, Jennifer

    ,000,000 2,500,000 3,000,000 3,500,000 4,000,000 4,500,000 1 2 3 4 5 6 7 8 9 10 11 12 Coal[1] Petroleum Liquids[2] Petroleum Coke Natural Gas Other Gases[3] Nuclear Hydroelectric Conventional Other Renewables[4 Consumption Petroleum Coal Natural Gas Non-biogenic MSW and Geothermal Energy Subtotal http

  7. 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.

  8. System and method for advanced power management

    DOE Patents [OSTI]

    Atcitty, Stanley (Albuquerque, NM); Symons, Philip C. (Surprise, AZ); Butler, Paul C. (Albuquerque, NM); Corey, Garth P. (Albuquerque, NM)

    2009-07-28

    A power management system is provided that includes a power supply means comprising a plurality of power supply strings, a testing means operably connected to said plurality of power supply strings for evaluating performance characteristics of said plurality of power supply strings, and a control means for monitoring power requirements and comprising a switching means for controlling switching of said plurality of power supply strings to said testing means.

  9. 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.

  10. Use of neurals networks in nuclear power plant diagnostics

    SciTech Connect (OSTI)

    Uhrig, R.E. (Tennessee Univ., Knoxville, TN (USA). Dept. of Nuclear Engineering Oak Ridge National Lab., TN (USA))

    1989-01-01

    A technique using neural networks as a means of diagnosing transients or abnormal conditions in nuclear power plants is investigated and found to be feasible. The technique is based on the fact that each physical state of the plant can be represented by a unique pattern of sensor outputs or instrument readings that can be related to the condition of the plant. Neural networks are used to relate this pattern to the fault, problem, or transient condition of the plant. A demonstration of the ability of this technique to identify causes of perturbations in the steam generator of a nuclear plant is presented. 3 refs., 4 figs.

  11. Space reactor/Stirling cycle systems for high power Lunar applications

    SciTech Connect (OSTI)

    Schmitz, P.D.; Mason, L.S.

    1994-09-01

    NASA`s Space Exploration Initiative (SEI) has proposed the use of high power nuclear power systems on the lunar surface as a necessary alternative to solar power. Because of the long lunar night ({approximately} 14 earth days) solar powered systems with the requisite energy storage in the form of regenerative fuel cells or batteries becomes prohibitively heavy at high power levels ({approximately} 100 kWe). At these high power levels nuclear power systems become an enabling technology for variety of missions. One way of producing power on the lunar surface is with an SP-100 class reactor coupled with Stirling power converters. In this study, analysis and characterization of the SP-100 class reactor coupled with Free Piston Stirling Power Conversion (FPSPC) system will be performed. Comparison of results with previous studies of other systems, particularly Brayton and Thermionic, are made.

  12. Fuel cell powered irrigation system

    SciTech Connect (OSTI)

    Jacobi, E.F.; Madden, M.R.

    1982-01-12

    Set out herein is a fuel cell power plant for use with irrigation systems wherein the fuel cell is utilized to generate electric current to drive a pump motor. This pump motor drives a first water pump which receives water for distribution through a traveling irrigation system, the output of the first pump first conveyed into a condenser heat exchanger connected to a steam engine or turbine cycle. The fuel cell itself is contained within a boiler assembly and the heat of production of the electric power is used to generate steam which is sent to the steam engine. In the course of cooling the condenser gases of the steam engine the irrigating water is passed through a second pump driven by the steam engine and it is through this second pump that the pressure is raised sufficiently to allow for the necessary spraying fans. To improve the condenser efficiency part of the condensate or the ullage thereof is connected to one of the spray heads on the irrigation system in a venturi nozzle which thereby lowers the back pressure thereof. The lower portion of the condenser or the liquid part thereof is fed back through yet another condenser pump to the boiler to be regenerated into steam.

  13. 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)

  14. RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Yen, W.W.S.

    2010-01-01

    DENSITIES AROUND CALIFORNIA NUCLEAR POWER PLANT. le Iil _. .AROUND CALIFORNIA NUCLEAR POWER PLANTS Miles San OnofreIN CALIFORNIA The California Nuclear Power Plant Emergency

  15. RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Yen, W.W.S.

    2010-01-01

    of radiological risk from nuclear power plants, One suchreservation in risk assessment for nuclear power plants isrisks to populations surrounding a nuclear power plant by

  16. Power Systems Integration Laboratory (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2011-10-01

    This fact sheet describes the purpose, lab specifications, applications scenarios, and information on how to partner with NREL's Power Systems Integration Laboratory at the Energy Systems Integration Facility. At NREL's Power Systems Integration Laboratory in the Energy Systems Integration Facility (ESIF), research focuses on developing and testing large-scale distributed energy systems for grid-connected, stand-alone, and microgrid applications. The laboratory can accommodate large power system components such as inverters for photovoltaic (PV) and wind systems, diesel and natural gas generators, battery packs, microgrid interconnection switchgear, and vehicles. Closely coupled with the research electrical distribution bus at the ESIF, the Power Systems Integration Laboratory will offer power testing capability of megawatt-scale DC and AC power systems, as well as advanced hardware-in-the-loop and model-in-the-loop simulation capabilities. Thermal heating and cooling loops and fuel also allow testing of combined heating/cooling and power systems (CHP).

  17. Wind Speed Forecasting for Power System Operation 

    E-Print Network [OSTI]

    Zhu, Xinxin

    2013-07-22

    In order to support large-scale integration of wind power into current electric energy system, accurate wind speed forecasting is essential, because the high variation and limited predictability of wind pose profound challenges to the power system...

  18. Viability of an expanded United States nuclear power program and its effects on energy markets

    E-Print Network [OSTI]

    Khan, Tanzeer S

    2006-01-01

    The four biggest energy sources in the United States are coal, crude oil, natural gas, and nuclear power. While coal and nuclear power are produced domestically, more than 70% of crude oil and 20% of natural gas is imported. ...

  19. An examination of the pursuit of nuclear power plant construction projects in the United States

    E-Print Network [OSTI]

    Guyer, Brittany (Brittany Leigh)

    2011-01-01

    The recent serious reconsideration of nuclear power as a means for U.S. electric utilities to increase their generation capacity provokes many questions regarding the achievable success of future nuclear power plant ...

  20. Nuclear power plant performance assessment pertaining to plant aging in France and the United States

    E-Print Network [OSTI]

    Guyer, Brittany (Brittany Leigh)

    2013-01-01

    The effect of aging on nuclear power plant performance has come under increased scrutiny in recent years. The approaches used to make an assessment of this effect strongly influence the economics of nuclear power plant ...

  1. Enhancing nuclear power plant performance through the use of artifical intelligence

    SciTech Connect (OSTI)

    Johnson, M.; Maren, A.; Miller, L.; Uhrig, R.; Upadhyaya, B.

    1989-06-15

    In the summer of 1988, the Department of Nuclear Engineering (NE) at the University of Tennessee (UT) in Knoxville was selected to carry out a research program in Enhancing the Operation of Nuclear Power plants through the use of Artificial Intelligence, This program is sponsored by the Department of Energy's Office of Energy Research under 10CFR605 for Nuclear Engineering Research. The objective of the research is to advance the state-of-the-art of nuclear power plant control, safety, management, and instrumentation systems through the use of artificial intelligence (AI) techniques, including both expert systems and neural networks. The emphasis will be placed on methods that can be implemented on a rapid or real-time basis. A second, but equally important, objective is to build a broadly based critical mass of expertise in the artificial intelligence, field that can be brought to bear on the technology of nuclear power plants. Both of these goals are being met. This overview and the attached technical reports describe the work that is being carried out. Although in some cases, the scope of the work differs somewhat from the specific tasks described in the original proposal, all activities are clearly within the overall scope of the contract.

  2. Enhancing nuclear power plant performance through the use of artifical intelligence. First annual report

    SciTech Connect (OSTI)

    Johnson, M.; Maren, A.; Miller, L.; Uhrig, R.; Upadhyaya, B.

    1989-06-15

    In the summer of 1988, the Department of Nuclear Engineering (NE) at the University of Tennessee (UT) in Knoxville was selected to carry out a research program in ``Enhancing the Operation of Nuclear Power plants through the use of Artificial Intelligence, This program is sponsored by the Department of Energy`s Office of Energy Research under 10CFR605 for Nuclear Engineering Research. The objective of the research is to advance the state-of-the-art of nuclear power plant control, safety, management, and instrumentation systems through the use of artificial intelligence (AI) techniques, including both expert systems and neural networks. The emphasis will be placed on methods that can be implemented on a rapid or real-time basis. A second, but equally important, objective is to build a broadly based critical mass of expertise in the artificial intelligence, field that can be brought to bear on the technology of nuclear power plants. Both of these goals are being met. This overview and the attached technical reports describe the work that is being carried out. Although in some cases, the scope of the work differs somewhat from the specific tasks described in the original proposal, all activities are clearly within the overall scope of the contract.

  3. 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...

  4. Switched Control of Electron Nuclear Spin Systems

    E-Print Network [OSTI]

    Navin Khaneja

    2007-07-11

    In this article, we study control of electron-nuclear spin dynamics at magnetic field strengths where the Larmor frequency of the nucleus is comparable to the hyperfine coupling strength. The quantization axis for the nuclear spin differs from the static B_0 field direction and depends on the state of the electron spin. The quantization axis can be switched by flipping the state of electron spin, allowing for universal control on nuclear spin states. We show that by performing a sequence of flips (each followed by a suitable delay), we can perform any desired rotation on the nuclear spins, which can also be conditioned on the state of the electron spin. These operations, combined with electron spin rotations can be used to synthesize any unitary transformation on the coupled electron-nuclear spin system. We discuss how these methods can be used for design of experiments for transfer of polarization from the electron to the nuclear spins.

  5. ELECTRICAL POWER SYSTEM DESCRIPTION DOCUMENT

    SciTech Connect (OSTI)

    M. Maniyar

    2004-06-22

    The purpose of this revision of the System Description Document (SDD) is to establish requirements that drive the design of the electrical power system and their bases to allow the design effort to proceed to License Application. This SDD is a living document that will be revised at strategic points as the design matures over time. This SDD identifies the requirements and describes the system design as they exist at this time, with emphasis on those attributes of the design provided to meet the requirements. This SDD has been developed to be an engineering tool for design control. Accordingly, the primary audience are design engineers. This type of SDD leads and follows the design process. It leads the design process with regard to the flow down of upper tier requirements onto the system. Knowledge of these requirements is essential to performing the design process. This SDD follows the design with regard to the description of the system. The description provided in the SDD is a reflection of the results of the design process to date. Functional and operational requirements applicable to this system are obtained from ''Project Functional and Operational Requirements'' (F&OR) (Siddoway, 2003). Other requirements to support the design process have been taken from higher level requirements documents such as ''Project Design Criteria Document'' (PDC) (Doraswamy 2004), the fire hazards analyses, and the preclosure safety analysis. The above mentioned low-level documents address ''Project Requirements Document'' (PRD) (Canori and Leitner 2003) requirements. This SDD includes several appendices with supporting information. Appendix B lists key system charts, diagrams, drawings, and lists; and Appendix C is a list of system procedures.

  6. Solar-powered cooling system

    DOE Patents [OSTI]

    Farmer, Joseph C.

    2015-07-28

    A solar-powered adsorption-desorption refrigeration and air conditioning system that uses nanostructural materials such as aerogels, zeolites, and sol gels as the adsorptive media. Refrigerant molecules are adsorbed on the high surface area of the nanostructural material while the material is at a relatively low temperature, perhaps at night. During daylight hours, when the nanostructural materials is heated by the sun, the refrigerant are thermally desorbed from the surface of the aerogel, thereby creating a pressurized gas phase in the vessel that contains the aerogel. This solar-driven pressurization forces the heated gaseous refrigerant through a condenser, followed by an expansion valve. In the condenser, heat is removed from the refrigerant, first by circulating air or water. Eventually, the cooled gaseous refrigerant expands isenthalpically through a throttle valve into an evaporator, in a fashion similar to that in more conventional vapor recompression systems.

  7. Integrated Retail & Wholesale Power System Operation

    E-Print Network [OSTI]

    Tesfatsion, Leigh

    Integrated Retail & Wholesale Power System Operation with Smart-Grid Functionality PIs: Dionysios Retail/Wholesale Power System Operation with Smart-Grid Functionality Project PIs: Dionysios Aliprantis Tesfatsion, "Project Overview: Integrated Retail and Wholesale Power System Operation with Smart-Grid

  8. Nuclear envelope transmembrane proteins in differentiation systems 

    E-Print Network [OSTI]

    Batrakou, Dzmitry G.

    2012-11-30

    Historically, our perception of the nuclear envelope has evolved from a simple barrier isolating the genome from the rest of a cell to a complex system that regulates functions including transcription, splicing, DNA ...

  9. Nuclear power plant fault-diagnosis using artificial neural networks

    SciTech Connect (OSTI)

    Kim, Keehoon; Aljundi, T.L.; Bartlett, E.B.

    1992-01-01

    Artificial neural networks (ANNs) have been applied to various fields due to their fault and noise tolerance and generalization characteristics. As an application to nuclear engineering, we apply neural networks to the early recognition of nuclear power plant operational transients. If a transient or accident occurs, the network will advise the plant operators in a timely manner. More importantly, we investigate the ability of the network to provide a measure of the confidence level in its diagnosis. In this research an ANN is trained to diagnose the status of the San Onofre Nuclear Generation Station using data obtained from the plant's training simulator. Stacked generalization is then applied to predict the error in the ANN diagnosis. The data used consisted of 10 scenarios that include typical design basis accidents as well as less severe transients. The results show that the trained network is capable of diagnosing all 10 instabilities as well as providing a measure of the level of confidence in its diagnoses.

  10. Thermoelectric Power Generation System with Loop Thermosyphon...

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

    Generation System with Loop Thermosyphon in Future High Efficiency Hybrid Vehicles Thermoelectric Power Generation System with Loop Thermosyphon in Future High Efficiency Hybrid...

  11. Vulnerability Analysis of a Nuclear Power Plant Considering Detonations of Explosive Devices

    E-Print Network [OSTI]

    Cizelj, Leon

    strength and injuries of human beings with nuclear power plant models used in probabilistic safetyVulnerability Analysis of a Nuclear Power Plant Considering Detonations of Explosive Devices Marko threats to a nuclear power plant in the year 1991 and after the 9/11 events in 2001. The methodology which

  12. Potential Threats from a Likely Nuclear Power Plant Accident: a Climatological Trajectory Analysis

    E-Print Network [OSTI]

    Chen, Shu-Hua

    in the near future as insecure nuclear power plants with a high risk of accidents remain in the regionPotential Threats from a Likely Nuclear Power Plant Accident: a Climatological Trajectory Analysis at the Metsamor Nuclear Power Plant would influence all of Turkey. Furthermore, vulnerable regions in Turkey after

  13. PLC-Based Safety Critical Software Development for Nuclear Power Plants

    E-Print Network [OSTI]

    PLC-Based Safety Critical Software Development for Nuclear Power Plants Junbeom Yoo1 , Sungdeok Cha development technique for nuclear power plants'I&C soft- ware controllers. To improve software safety, we in developing safety-critical control software for a Korean nuclear power plant, and experience to date has been

  14. Empirical relations for nuclear stopping power F. S. Garnir-Monjoie

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    31 Empirical relations for nuclear stopping power F. S. Garnir-Monjoie Institut de Mathématiques, D, due to inelastic interaction with the target electrons, and the nuclear stopping power induced. The Lindhard, Scharff and Schiott theory (LSS theory) [1] shows that the nuclear stopping power is the same

  15. Four convictions motivate this paper.1 First, nuclear power could make a signi-

    E-Print Network [OSTI]

    Four convictions motivate this paper.1 First, nuclear power could make a signi˝- cant contribution to climate change mitiga- tion. To do so, however, nuclear power would have to be deployed extensive- ly of rules to govern nuclear power that are the same in all countries. Second, the world is not now safe

  16. Condition monitoring of motor-operated valves in nuclear power plants Pierre Granjon

    E-Print Network [OSTI]

    Boyer, Edmond

    Condition monitoring of motor-operated valves in nuclear power plants Pierre Granjon Gipsa of nuclear power plants. Unfortunately, today's policies present a major drawback. Indeed, these monitoring is illustrated through experimental data. 1. Introduction Nuclear power provides about 14% of the world

  17. Childhood leukaemia incidence below the age of 5 years near French nuclear power plants

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Childhood leukaemia incidence below the age of 5 years near French nuclear power plants D Laurier 1 living in the vicinity of nuclear power plants in Germany. We present herein results about the incidence of childhood leukaemia in the vicinity of nuclear power plants in France for the same age range. These results

  18. Nuclear reactor cooling system decontamination reagent regeneration

    DOE Patents [OSTI]

    Anstine, Larry D. (San Jose, CA); James, Dean B. (Saratoga, CA); Melaika, Edward A. (Berkeley, CA); Peterson, Jr., John P. (Livermore, CA)

    1985-01-01

    An improved method for decontaminating the coolant system of water-cooled nuclear power reactors and for regenerating the decontamination solution. A small amount of one or more weak-acid organic complexing agents is added to the reactor coolant, and the pH is adjusted to form a decontamination solution which is circulated throughout the coolant system to dissolve metal oxides from the interior surfaces and complex the resulting metal ions and radionuclide ions. The coolant containing the complexed metal ions and radionuclide ions is passed through a strong-base anion exchange resin bed which has been presaturated with a solution containing the complexing agents in the same ratio and having the same pH as the decontamination solution. As the decontamination solution passes through the resin bed, metal-complexed anions are exchanged for the metal-ion-free anions on the bed, while metal-ion-free anions in the solution pass through the bed, thus removing the metal ions and regenerating the decontamination solution.

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

    SciTech Connect (OSTI)

    Mashin, V. A.

    2012-09-15

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

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

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE: Alternative FuelsofProgram: Report15 MeetingDevelopmentDepartment ofTestimony5Nuclear Power in

  1. ASSESSMENT OF COMBINED HEAT AND POWER SYSTEM "PREMIUM POWER" APPLICATIONS IN CALIFORNIA

    E-Print Network [OSTI]

    Norwood, Zack

    2010-01-01

    Modeling with Combined Heat and Power Applications. LawrenceASSESSMENT OF COMBINED HEAT AND POWER SYSTEM “PREMIUM POWER”2010 ASSESSMENT OF COMBINED HEAT AND POWER SYSTEM “PREMIUM

  2. India's nuclear power program : a study of India's unique approach to nuclear energy

    E-Print Network [OSTI]

    Murray, Caitlin Lenore

    2006-01-01

    India is in the middle of the biggest expansion of nuclear power in its history, adding 20 GWe in the next 14 years in the form of pressure water reactors and fast breeder reactors. At the same time, the United States is ...

  3. Conceivable new recycling of nuclear waste by nuclear power companies in their plants

    E-Print Network [OSTI]

    Ruggero Maria Santilli

    1997-04-09

    We outline the basic principles and the needed experiments for a conceivable new recycling of nuclear waste by the power plants themselves to avoid its transportation and storage to a (yet unknown) dumping area. Details are provided in an adjoining paper and in patents pending.

  4. Power Systems Life Cycle Analysis Tool (Power L-CAT).

    SciTech Connect (OSTI)

    Andruski, Joel; Drennen, Thomas E.

    2011-01-01

    The Power Systems L-CAT is a high-level dynamic model that calculates levelized production costs and tracks environmental performance for a range of electricity generation technologies: natural gas combined cycle (using either imported (LNGCC) or domestic natural gas (NGCC)), integrated gasification combined cycle (IGCC), supercritical pulverized coal (SCPC), existing pulverized coal (EXPC), nuclear, and wind. All of the fossil fuel technologies also include an option for including carbon capture and sequestration technologies (CCS). The model allows for quick sensitivity analysis on key technical and financial assumptions, such as: capital, O&M, and fuel costs; interest rates; construction time; heat rates; taxes; depreciation; and capacity factors. The fossil fuel options are based on detailed life cycle analysis reports conducted by the National Energy Technology Laboratory (NETL). For each of these technologies, NETL's detailed LCAs include consideration of five stages associated with energy production: raw material acquisition (RMA), raw material transport (RMT), energy conversion facility (ECF), product transportation and distribution (PT&D), and end user electricity consumption. The goal of the NETL studies is to compare existing and future fossil fuel technology options using a cradle-to-grave analysis. The NETL reports consider constant dollar levelized cost of delivered electricity, total plant costs, greenhouse gas emissions, criteria air pollutants, mercury (Hg) and ammonia (NH3) emissions, water withdrawal and consumption, and land use (acreage).

  5. The nuclear electromagnetic pulse and the electric power grid: A different perspective: Special report

    SciTech Connect (OSTI)

    Rabinowitz, M.

    1987-10-01

    This report primarily considers the potential effects of a single high-altitude nuclear burst on the US power grid. It describes various types of electromagnetic pulses (EMP) from a nuclear explosion and provides a brief historical overview of EMP. A comparison is made between EMP and natural phenomena such as lightning and solar storms. This report concludes that EMP effects are exaggerated because of an unrealistic assumption of the pulse that can be seen by the power system. An upper limit of the electric field of the very fast, high-amplitude EMP is derived from first principles. The resulting values indicate that although electric fields approaching 50 kV/m might be obtained locally, the energy content is significantly lower than the commonly presented values, and the electric field decreases rapidly with distance. Additional calculations show that the ionization produced by a nuclear burst severely attenuates the EMP. These findings all indicate that EMP damage to the US power grid in equipment flashovers and line flashovers from a high-altitude nuclear bomb will be negligible, except for localized damage to some unshielded electronic control systems. Since it is difficult to make accurate calculations of the coupling of EMP into complex electronic systems, this report relies on the results of other studies which indicate the possibility of minimal damage. 42 refs., 23 figs., 6 tabs.

  6. RADIOISOTOPE POWER SYSTEM CAPABILITIES AT THE IDAHO NATIONAL LABORATORY (INL)

    SciTech Connect (OSTI)

    Kelly Lively; Stephen Johnson; Eric Clarke

    2014-07-01

    --Idaho National Laboratory’s, Space Nuclear Systems and Technology Division established the resources, equipment and facilities required to provide nuclear-fueled, Radioisotope Power Systems (RPS) to Department of Energy (DOE) Customers. RPSs are designed to convert the heat generated by decay of iridium clad, 238PuO2 fuel pellets into electricity that is used to power missions in remote, harsh environments. Utilization of nuclear fuel requires adherence to governing regulations and the INL provides unique capabilities to safely fuel, test, store, transport and integrate RPSs to supply power—supporting mission needs. Nuclear capabilities encompass RPS fueling, testing, handling, storing, transporting RPS nationally, and space vehicle integration. Activities are performed at the INL and in remote locations such as John F. Kennedy Space Center and Cape Canaveral Air Station to support space missions. This paper will focus on the facility and equipment capabilities primarily offered at the INL, Material and Fuel Complex located in a security-protected, federally owned, industrial area on the remote desert site west of Idaho Falls, ID. Nuclear and non-nuclear facilities house equipment needed to perform required activities such as general purpose heat source (GPHS) module pre-assembly and module assembly using nuclear fuel; RPS receipt and baseline electrical testing, fueling, vibration testing to simulate the launch environment, mass properties testing to measure the mass and compute the moment of inertia, electro-magnetic characterizing to determine potential consequences to the operation of vehicle or scientific instrumentation, and thermal vacuum testing to verify RPS power performance in the vacuum and cold temperatures of space.

  7. Electric Power Generation Systems | netl.doe.gov

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

    Electric Power Generation Systems Coal gasification-based power plants Coal combustion-based power plants Natural gas-fueled power plants Turbines Fuel cells Existing power plants...

  8. POWER GRID DYNAMICS: ENHANCING POWER SYSTEM OPERATION THROUGH PRONY ANALYSIS

    SciTech Connect (OSTI)

    Ray, C.; Huang, Z.

    2007-01-01

    Prony Analysis is a technique used to decompose a signal into a series consisting of weighted complex exponentials and promises to be an effi cient way of recognizing sensitive lines during faults in power systems such as the U.S. Power grid. Positive Sequence Load Flow (PSLF) was used to simulate the performance of a simple two-area-four-generator system and the reaction of the system during a line fault. The Dynamic System Identifi cation (DSI) Toolbox was used to perform Prony analysis and use modal information to identify key transmission lines for power fl ow adjustment to improve system damping. The success of the application of Prony analysis methods to the data obtained from PSLF is reported, and the key transmission line for adjustment is identifi ed. Future work will focus on larger systems and improving the current algorithms to deal with networks such as large portions of the Western Electricity Coordinating Council (WECC) power grid.

  9. Electronic power conditioning for dynamic power conversion in high-power space systems 

    E-Print Network [OSTI]

    Hansen, James Michael

    1991-01-01

    power conversion allows for improved methods of power conditioning. A block diagram of one such system that uses dynamic power conversion is shown in Fig. 4. The blocks labeled Energy Source, Primary Heat Rejection, snd User's Load are the same...ELECTRONIC POWER CONDITIONING FOR DYNAMIC POWER CONVERSION IN HIGH ? POWER SPACE SYSTEMS A Thesis by JAMES MICHAEL HANSEN Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements...

  10. Use of probabilistic risk assessment (PRA) in expert systems to advise nuclear plant operators and managers

    SciTech Connect (OSTI)

    Uhrig, R.E.

    1988-01-01

    The use of expert systems in nuclear power plants to provide advice to managers, supervisors and/or operators is a concept that is rapidly gaining acceptance. Generally, expert systems rely on the expertise of human experts or knowledge that has been modified in publications, books, or regulations to provide advice under a wide variety of conditions. In this work, a probabilistic risk assessment (PRA)/sup 3/ of a nuclear power plant performed previously is used to assess the safety status of nuclear power plants and to make recommendations to the plant personnel. 5 refs., 1 fig., 2 tabs.

  11. State of the art review of radioactive waste volume reduction techniques for commercial nuclear power plants

    SciTech Connect (OSTI)

    Not Available

    1980-04-01

    A review is made of the state of the art of volume reduction techniques for low level liquid and solid radioactive wastes produced as a result of: (1) operation of commercial nuclear power plants, (2) storage of spent fuel in away-from-reactor facilities, and (3) decontamination/decommissioning of commercial nuclear power plants. The types of wastes and their chemical, physical, and radiological characteristics are identified. Methods used by industry for processing radioactive wastes are reviewed and compared to the new techniques for processing and reducing the volume of radioactive wastes. A detailed system description and report on operating experiences follow for each of the new volume reduction techniques. In addition, descriptions of volume reduction methods presently under development are provided. The Appendix records data collected during site surveys of vendor facilities and operating power plants. A Bibliography is provided for each of the various volume reduction techniques discussed in the report.

  12. Energy management system functions in deregulated power systems 

    E-Print Network [OSTI]

    Magnago, Fernando Hugo

    1997-01-01

    The market structures for electric energy and power are changing. In the past interconnected electric utility systems dealt only with each other to buy and sell power and energy. In recent times, the electric power industry is facing...

  13. Agent Modeling for Integrated Power Systems

    E-Print Network [OSTI]

    effective market power mitigation rules, how to incorporate ancillary service markets, and how to properly implement a retail electricity market to encourage customer participation. Although valuable experience hasAgent Modeling for Integrated Power Systems Final Project Report Power Systems Engineering Research

  14. A study of stopping power in nuclear reactions at intermediate energies

    E-Print Network [OSTI]

    Lehaut, G; Lopez, O

    2010-01-01

    We show a systematic experimental study based on INDRA data of the stopping power in central symmetric nuclear reactions. Total mass of the systems goes from 80 to 400 nucleons while the incident energy range is from 12 AMeV to 100 AMeV. The role of isospin diffusion at 32 and 45 MeV/nucleon with 124,136Xe projectiles on 112,124Sn targets performed at GANIL is also discussed. Results suggest a strong memory of the entrance channel above 20 AMeV/A (nuclear transparency) and, as such, constitute valuable tests of the microscopic transport models.

  15. A study of stopping power in nuclear reactions at intermediate energies

    E-Print Network [OSTI]

    G. Lehaut; D. Durand; O. Lopez

    2010-01-25

    We show a systematic experimental study based on INDRA data of the stopping power in central symmetric nuclear reactions. Total mass of the systems goes from 80 to 400 nucleons while the incident energy range is from 12 AMeV to 100 AMeV. The role of isospin diffusion at 32 and 45 MeV/nucleon with 124,136Xe projectiles on 112,124Sn targets performed at GANIL is also discussed. Results suggest a strong memory of the entrance channel above 20 AMeV/A (nuclear transparency) and, as such, constitute valuable tests of the microscopic transport models.

  16. HIGH EFFICIENCY GENERATION OF HYDROGEN FUELS USING NUCLEAR POWER

    SciTech Connect (OSTI)

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

    2003-06-01

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

  17. Power production from renewable resources in a gasification power system

    SciTech Connect (OSTI)

    Paisley, M.A.; Farris, G.; Bain, R.

    1996-12-31

    The US Department of Energy (DOE) has been a leader in the promotion and development of alternative fuel supplies based on renewable energy crops. One promising power generation technology is biomass gasification coupled with either a gas turbine in a combined cycle system or a fuel cell. The gasification of biomass can efficiently and economically produce a renewable source of a clean gaseous fuel suitable for use in these high efficiency power systems or as a substitute fuel in other combustion devices such as boilers, kilns, or other natural gas fired equipment. This paper discusses the development and commercialization of the Battelle high-throughput gasification process for gas turbine based power generation systems. Projected process economics for a gas turbine combined cycle plant are presented along with a description of integrated system operation coupling a 200kW gas turbine power generation system to a 10 ton per day gasifier, and current commercialization activities. 6 refs., 3 figs., 1 tab.

  18. Reuse of hybrid car power systems

    E-Print Network [OSTI]

    Kirkby, Nicholas (Nicholas J.)

    2015-01-01

    Used hybrid car power systems are inexpensive and capable of tens of kilowatts of power throughput. This paper documents a process for using the second generation Toyota Prius inverter module to drive a three phase permanent ...

  19. An Energy-Based Approach to Power System Analysis

    E-Print Network [OSTI]

    Caliskan, Sina Yamac

    2015-01-01

    loads, Electrical Power and Energy Systems, Vol. 8, Issue 1,equation, Electrical Power & Energy Systems, Vol. 3, No. 3,In contemporary power systems, energy flows from the

  20. Low Cost High Concentration PV Systems for Utility Power Generation...

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

    Residential and Utility Solar Power Generating Systems SunPower,Low Cost Thin Film Building-Integrated PV Systems Low Cost High Concentration PV Systems for Utility Power...

  1. The NUCLARR databank: Human reliability and hardware failure data for the nuclear power industry

    SciTech Connect (OSTI)

    Reece, W.J.

    1993-05-01

    Under the sponsorship of the US Nuclear Regulatory Commission (NRC), the Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR) was developed to provide human reliability and hardware failure data to analysts in the nuclear power industry. This IBM-compatible databank is contained on a set of floppy diskettes which include data files and a menu-driven system for locating, reviewing, sorting, and retrieving the data. NUCLARR contains over 2500 individual data records, drawn from more, than 60 sources. The system is upgraded annually, to include additional human error and hardware component failure data and programming enhancements (i.e., increased user-friendliness). NUCLARR is available from the NRC through project staff at the INEL.

  2. Modernizing computerized nuclear material accounting systems

    SciTech Connect (OSTI)

    Erkkila, B.H.; Claborn, J. [Los Alamos National Lab., NM (United States). Safeguards Systems Group

    1995-09-01

    DOE Orders and draft orders for nuclear material control and accountability address a complete material control and accountability (MC and A) program for all DOE contractors processing, using, or storing nuclear materials. A critical element of an MC and A program is the accounting system used to track and record all inventories of nuclear material and movements of materials in those inventories. Most DOE facilities use computerized accounting systems to facilitate the task of accounting for all their inventory of nuclear materials. Many facilities still use a mixture of a manual paper system with a computerized system. Also, facilities may use multiple systems to support information needed for MC and A. For real-time accounting it is desirable to implement a single integrated data base management system for a variety of users. In addition to accountability needs, waste management, material management, and production operations must be supported. Information in these systems can also support criticality safety and other safety issues. Modern networked microcomputers provide extensive processing and reporting capabilities that single mainframe computer systems struggle with. This paper describes an approach being developed at Los Alamos to address these problems.

  3. 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.

  4. 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.

  5. SUBMITTED TO IEEE TRANSACTIONS ON POWER SYSTEMS, FEBRUARY 2002 1 Human Factors Aspects of Power System

    E-Print Network [OSTI]

    SUBMITTED TO IEEE TRANSACTIONS ON POWER SYSTEMS, FEBRUARY 2002 1 Human Factors Aspects of Power with human factors aspects of utilizing color contours to visualize electric power system bus voltage in the quickest solution times. Testing was done using a modified version of the IEEE 118 bus system. Index Terms--Power

  6. RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Nero, A.V.

    2010-01-01

    Report LBL-5287. "Power Plant Reliability-Availability andConunercial Nuclear Power Plants", Report WASH-1400 (NUREG-Standards for Nuclear Power Plants," by A.V. Nero and Y.C.

  7. Guidelines for inservice testing at nuclear power plants

    SciTech Connect (OSTI)

    Campbell, P.

    1995-04-01

    The staff of the U.S. Nuclear Regulatory Commission (NRC) gives licensees guidelines and recommendations for developing and implementing programs for the inservice testing of pumps and valves at commercial nuclear power plants. The staff discusses the regulations; the components to be included in an inservice testing program; and the preparation and content of cold shutdown justifications, refueling outage justifications, and requests for relief from the American Society of Mechanical Engineers Code requirements. The staff also gives specific guidance on relief acceptable to the NRC and advises licensees in the use of this information at their facilities. The staff discusses the revised standard technical specifications for the inservice testing program requirements and gives guidance on the process a licensee may follow upon finding an instance of noncompliance with the Code.

  8. 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.

  9. Power management circuits for ultra-low power systems

    E-Print Network [OSTI]

    El-Damak, Dina Reda

    2015-01-01

    Power management circuits perform a wide range of vital tasks for electronic systems including DC-DC conversion, energy harvesting, battery charging and protection as well as dynamic voltage scaling. The impact of the ...

  10. 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.

  11. Abstract--A novel methodology for economic evaluation of hydrogen storage for a mixed wind-nuclear power plant is

    E-Print Network [OSTI]

    Cańizares, Claudio A.

    .e. transmission congestion. Index Terms--wind power, nuclear power, hydrogen storage, Hydrogen Economy, power power plant production (MW) NP : nuclear power plant production (MW) CP : electrolyzer consumption (MW with the market (kg) WIND ipwP ,, : wind-nuclear power consumed for wind scenario w and price scenario p in hour i

  12. Distributed vs. Centralized Power Systems Frequency Control

    E-Print Network [OSTI]

    Dimarogonas, Dimos

    Distributed vs. Centralized Power Systems Frequency Control Martin Andreasson12 , Dimos V control of electrical power systems. We propose a distributed controller which retains the reference, where their performance is compared. I. INTRODUCTION Distributed control is in many large-scale systems

  13. Integration of Storage Devices into Power Systems

    E-Print Network [OSTI]

    and renewable source of energy with zero fuel costs. However, wind generation outputs are highly variableIntegration of Storage Devices into Power Systems with Renewable Energy Sources Final Project System #12;Integration of Storage Devices into Power Systems with Renewable Energy Sources Final Project

  14. Los Alamos Nuclear Plant Analyzer: an interactive power-plant simulation program

    SciTech Connect (OSTI)

    Steinke, R.; Booker, C.; Giguere, P.; Liles, D.R.; Mahaffy, J.H.; Turner, M.R.

    1984-01-01

    The Nuclear Plant Analyzer (NPA) is a computer-software interface for executing the TRAC or RELAP5 power-plant systems codes. The NPA is designed to use advanced supercomputers, long-distance data communications, and a remote workstation terminal with interactive computer graphics to analyze power-plant thermal-hydraulic behavior. The NPA interface simplifies the running of these codes through automated procedures and dialog interaction. User understanding of simulated-plant behavior is enhanced through graphics displays of calculational results. These results are displayed concurrently with the calculation. The user has the capability to override the plant's modeled control system with hardware-adjustment commands. This gives the NPA the utility of a simulator, and at the same time, the accuracy of an advanced, best-estimate, power-plant systems code for plant operation and safety analysis.

  15. Flexibility in 21st Century Power Systems

    SciTech Connect (OSTI)

    Cochran, J.; Miller, M.; Zinaman, O.; Milligan, M.; Arent, D.; Palmintier, B.; O'Malley, M.; Mueller, S.; Lannoye, E.; Tuohy, A.; Kujala, B.; Sommer, M.; Holttinen, H.; Kiviluoma, J.; Soonee, S. K.

    2014-05-01

    Flexibility of operation--the ability of a power system to respond to change in demand and supply--is a characteristic of all power systems. Flexibility is especially prized in twenty-first century power systems, with higher levels of grid-connected variable renewable energy (primarily, wind and solar). This paper summarizes the analytic frameworks that have emerged to measure this characteristic and distills key principles of flexibility for policy makers.

  16. 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.

  17. 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.

  18. Antineutrino flux from the Laguna Verde Nuclear Power Plant

    E-Print Network [OSTI]

    Marisol Chavez-Estrada; Alexis A. Aguilar-Arevalo

    2015-09-09

    We present a calculation of the antineutrino flux produced by the reactors at the Laguna Verde Nuclear Power Plant in M\\'exico, based on the antineutrino spectra produced in the decay chains of the fission fragments of the main isotopes in the reactor core, and their fission rates, that have been calculated using the DRAGON simulation code. We also present an estimate of the number of expected events in a detector made of plastic scintillator with a mass of 1 ton, at 100 m from the reactor cores.

  19. Antineutrino flux from the Laguna Verde Nuclear Power Plant

    E-Print Network [OSTI]

    Chavez-Estrada, Marisol

    2015-01-01

    We present a a calculation of the antineutrino flux produced by the reactors at the Laguna Verde Nuclear Power Plant in M\\'exico, based on the antineutrino spectra produced in the decay chains of the fission fragments of the main isotopes in the reactor core, and their fission rates, that have been calculated using the DRAGON simulation code. We also present an estimate of the number of expected events in a detector made of plastic scintillator with a mass of 1 ton, at 100 m from the reactor cores.

  20. Antineutrino flux from the Laguna Verde Nuclear Power Plant

    E-Print Network [OSTI]

    Marisol Chavez-Estrada; Alexis A. Aguilar-Arevalo

    2015-08-20

    We present a a calculation of the antineutrino flux produced by the reactors at the Laguna Verde Nuclear Power Plant in M\\'exico, based on the antineutrino spectra produced in the decay chains of the fission fragments of the main isotopes in the reactor core, and their fission rates, that have been calculated using the DRAGON simulation code. We also present an estimate of the number of expected events in a detector made of plastic scintillator with a mass of 1 ton, at 100 m from the reactor cores.

  1. Long-Term Planning for Nuclear Energy Systems Under Deep Uncertainty

    E-Print Network [OSTI]

    Kim, Lance Kyungwoo

    2011-01-01

    5.3.2 Nuclear Energy System Model . . . . . . . . . . .Brief History of Nuclear Energy . . . . . . . . Nuclear FuelModeling . . . . . . . . . . . . . 5.3 Nuclear Energy System

  2. Transmutation of nuclear waste in accelerator-driven systems

    E-Print Network [OSTI]

    Herrera-Martínez, A

    2004-01-01

    Today more than ever energy is not only a cornerstone of human development, but also a key to the environmental sustainability of economic activity. In this context, the role of nuclear power may be emphasized in the years to come. Nevertheless, the problems of nuclear waste, safety and proliferation still remain to be solved. It is believed that the use of accelerator-driven systems (ADSs) for nuclear waste transmutation and energy production would address these problems in a simple, clean and economically viable, and therefore sustainable, manner. This thesis covers the major nuclear physics aspects of ADSs, in particular the spallation process and the core neutronics specific to this type of systems. The need for accurate nuclear data is described, together with a detailed analysis of the specific isotopes and energy ranges in which this data needs to be improved and the impact of their uncertainty. Preliminary experimental results for some of these isotopes, produced by the Neutron Time-of-Flight (n_TOF) ...

  3. Review: Nuclear Power Is Not the Answer by Helen Caldicott

    E-Print Network [OSTI]

    Mirza, Umar Karim

    2007-01-01

    and the possibility of nuclear weapons proliferation make itto a discussion of nuclear weapons proliferation. In the

  4. Review: Nuclear Power Is Not the Answer by Helen Caldicott

    E-Print Network [OSTI]

    Mirza, Umar Karim

    2007-01-01

    the possibility of nuclear weapons proliferation make it ato a discussion of nuclear weapons proliferation. In the

  5. Water reactive hydrogen fuel cell power system

    DOE Patents [OSTI]

    Wallace, Andrew P; Melack, John M; Lefenfeld, Michael

    2014-11-25

    A water reactive hydrogen fueled power system includes devices and methods to combine reactant fuel materials and aqueous solutions to generate hydrogen. The generated hydrogen is converted in a fuel cell to provide electricity. The water reactive hydrogen fueled power system includes a fuel cell, a water feed tray, and a fuel cartridge to generate power for portable power electronics. The removable fuel cartridge is encompassed by the water feed tray and fuel cell. The water feed tray is refillable with water by a user. The water is then transferred from the water feed tray into the fuel cartridge to generate hydrogen for the fuel cell which then produces power for the user.

  6. Water reactive hydrogen fuel cell power system

    DOE Patents [OSTI]

    Wallace, Andrew P; Melack, John M; Lefenfeld, Michael

    2014-01-21

    A water reactive hydrogen fueled power system includes devices and methods to combine reactant fuel materials and aqueous solutions to generate hydrogen. The generated hydrogen is converted in a fuel cell to provide electricity. The water reactive hydrogen fueled power system includes a fuel cell, a water feed tray, and a fuel cartridge to generate power for portable power electronics. The removable fuel cartridge is encompassed by the water feed tray and fuel cell. The water feed tray is refillable with water by a user. The water is then transferred from the water feed tray into a fuel cartridge to generate hydrogen for the fuel cell which then produces power for the user.

  7. Data base on dose reduction research projects for nuclear power plants. Volume 5

    SciTech Connect (OSTI)

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

    1994-05-01

    This is the fifth volume in a series of reports that provide information on dose reduction research and health physics technology or nuclear power plants. The information is taken from two of several databases maintained by Brookhaven National Laboratory`s ALARA Center for the Nuclear Regulatory Commission. The research section of the report covers dose reduction projects that are in the experimental or developmental phase. It includes topics such as steam generator degradation, decontamination, robotics, improvements in reactor materials, and inspection techniques. The section on health physics technology discusses dose reduction efforts that are in place or in the process of being implemented at nuclear power plants. A total of 105 new or updated projects are described. All project abstracts from this report are available to nuclear industry professionals with access to a fax machine through the ACEFAX system or a computer with a modem and the proper communications software through the ACE system. Detailed descriptions of how to access all the databases electronically are in the appendices of the report.

  8. 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.

  9. Nuclear power plant fault-diagnosis using artificial neural networks

    SciTech Connect (OSTI)

    Kim, Keehoon; Aljundi, T.L.; Bartlett, E.B.

    1992-12-31

    Artificial neural networks (ANNs) have been applied to various fields due to their fault and noise tolerance and generalization characteristics. As an application to nuclear engineering, we apply neural networks to the early recognition of nuclear power plant operational transients. If a transient or accident occurs, the network will advise the plant operators in a timely manner. More importantly, we investigate the ability of the network to provide a measure of the confidence level in its diagnosis. In this research an ANN is trained to diagnose the status of the San Onofre Nuclear Generation Station using data obtained from the plant`s training simulator. Stacked generalization is then applied to predict the error in the ANN diagnosis. The data used consisted of 10 scenarios that include typical design basis accidents as well as less severe transients. The results show that the trained network is capable of diagnosing all 10 instabilities as well as providing a measure of the level of confidence in its diagnoses.

  10. The potential role of nuclear power in controlling CO sub 2 emissions

    SciTech Connect (OSTI)

    Fulkerson, W.; Jones, J.E.; Delene, J.G.; Perry, A.M.; Cantor, R.A.

    1990-01-01

    Nuclear power currently reduces CO{sub 2} emissions from fossil fuel burning worldwide by about 8% (0.4 Gt(C)/yr). It can continue to play an important role only if it can grow substantially in the next 50 years. For such growth to occur public confidence will need to improve throughout the world. That might happen if (a) other non-fossil alternatives are inadequate to meet electricity demand growth, (b) the risks to society from global warming are perceived to be very high, (c) nuclear technology improves substantially, and (d) an international institutional setting is devised to manage the nuclear enterprise so that the technology is available to all nations while catastrophic accidents and proliferation of nuclear weapon capabilities are avoided. It seems feasible that the necessary technological and institutional advances can be devised and tested over the next 20 years. It is also plausible that the direct costs of electricity produced by the system would be in the range of 50-100 mills/kWhr (1990 dollars) delivered to the grid. In other words, the direct costs of nuclear power should not be greater than they are today. Achieving such an outcome will require aggressive technical and institutional RD D performed in a cooperative international setting. If rapid growth of nuclear power can begin again in 15-20 years it could supply 30-50% of world electricity in 50 years and cut CO{sub 2} emission rates by up to 2.5 Gt(C)/yr. This would be a substantial contribution to controlling greenhouse gases, but it is not sufficient. Improved efficiency and various renewable energy sources must also grow rapidly if CO{sub 2} emission rates from electricity generation are to be reduced from the current value of about 2 Gt(C)/yr. 41 refs., 4 figs., 3 tabs.

  11. Dominant Nuclear Outflow Driving Mechanisms in Powerful Radio Galaxies

    E-Print Network [OSTI]

    Dan Batcheldor; Clive Tadhunter; Joanna Holt; Raffaella Morganti; Christopher P. O'Dea; David J. Axon; Anton Koekemoer

    2007-02-20

    In order to identify the dominant nuclear outflow mechanisms in Active Galactic Nuclei, we have undertaken deep, high resolution observations of two compact radio sources (PKS 1549-79 and PKS 1345+12) with the Advanced Camera for Surveys (ACS) aboard the Hubble Space Telescope. Not only are these targets known to have powerful emission line outflows, but they also contain all the potential drivers for the outflows: relativistic jets, quasar nuclei and starbursts. ACS allows the compact nature (<0.15") of these radio sources to be optically resolved for the first time. Through comparison with existing radio maps we have seen consistency in the nuclear position angles of both the optical emission line and radio data. There is no evidence for bi-conical emission line features on the large-scale and there is a divergance in the relative position angles of the optical and radio structure. This enables us to exclude starburst driven outflows. However, we are unable to clearly distinguish between radiative AGN wind driven outflows and outflows powered by relativistic radio jets. The small scale bi-conical features, indicative of such mechanisms could be below the resolution limit of ACS, especially if aligned close to the line of sight. In addition, there may be offsets between the radio and optical nuclei induced by heavy dust obscuration, nebular continuum or scattered light from the AGN.

  12. Power to the People or Regulatory Ratcheting? Explaining the Success (or Failure) of Attempts to Site Commercial U.S. Nuclear Power Plants: 1954 -19961

    E-Print Network [OSTI]

    to Site Commercial U.S. Nuclear Power Plants: 1954 - 19961 7 April 2014 Eric Berndt2 and Daniel P. Aldrich3 Abstract: Between 1954 and 1996, more than 200 nuclear power projects were publically announced to revitalize the nuclear industry in the US and abroad. Keywords: nuclear power, siting decisions, regulatory

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

    SciTech Connect (OSTI)

    Miller, Keith [The UK's National Nuclear Laboratory, Chadwick House, Birchwood Park, Warrington WA3 6AE (United Kingdom)] [The UK's National Nuclear Laboratory, Chadwick House, Birchwood Park, Warrington WA3 6AE (United Kingdom)

    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)

  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. The future of nuclear power in the United States : economic and regulatory challenges

    E-Print Network [OSTI]

    Joskow, Paul L.

    2006-01-01

    This paper examines the economic and regulatory challenges that must be faced by potential investors in new nuclear power plants in the United States. The historical development of the existing fleet of over 100 nuclear ...

  16. U.S. nuclear power plants as terrorist targets : threat perception and the media

    E-Print Network [OSTI]

    Laughter, Mark, 1980-

    2005-01-01

    In recent history, nuclear engineers and the nuclear power industry have been primarily concerned with two things: safety and waste. In the past few years, a third concern has risen to join these two at the top: terrorism. ...

  17. Formation of the intermediate baryon systems in hadron-nuclear and nuclear-nuclear interactions

    E-Print Network [OSTI]

    M. K. Suleymanov; E. U. Khan; A Kravchakova; Mahnaz Q. Haseeb; S. M. Saleem; Y. H. Huseynaliyev; S Vokal; A. S. Vodopianov; O. B. Abdinov

    2007-12-17

    The centrality experiments indicate regime change and saturation in the behavior of some characteristics of the secondary particles emitted in hadron-nuclear and nuclear-nuclear interactions at high energies. The phenomenon has a critical character. The simple models do not explain the effect. We suppose that the responsible mechanism to explain the phenomenon could be the formation and decay of the intermediate baryon systems. Such systems could be formed as a result of nucleon percolation in compressed baryonic matter. Formation of big percolation cluster may change the properties of the medium, e.g., it could lead to the changing its transparency. This could be used to get a signal of the intermediate baryonic system formation. We consider two signals to identify the formation of the intermediate baryon systems: the critical changing of transparency of the strongly interacting matter and the enhancement of light nuclei production with increase in centrality.

  18. 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.

  19. 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.

  20. Dynamic Simulation of Nuclear Hydrogen Production Systems

    E-Print Network [OSTI]

    in a hydrogen plant. The resulting system is tightly interconnected and operates at very high temperature connecting a nuclear reactor and a hydrogen production plant. This heat transfer loop uses helium as the heat scenarios. The first contribution of this thesis is a novel equation-based model for the heat transfer loop

  1. High power laser perforating tools and systems

    DOE Patents [OSTI]

    Zediker, Mark S; Rinzler, Charles C; Faircloth, Brian O; Koblick, Yeshaya; Moxley, Joel F

    2014-04-22

    ystems devices and methods for the transmission of 1 kW or more of laser energy deep into the earth and for the suppression of associated nonlinear phenomena. Systems, devices and methods for the laser perforation of a borehole in the earth. These systems can deliver high power laser energy down a deep borehole, while maintaining the high power to perforate such boreholes.

  2. Accelerating the transformation of power systems

    E-Print Network [OSTI]

    requirements are unique to each power system, but across many settings the quantity and performance ancillary services provision and preventing gaming Next Steps · CERC and POSOCO are evaluating how to apply consultative support Accelerating the transformation of power systems NREL/FS-6A20-61811 · May 2014 15013

  3. Ocean Renewable Power Co (ORPC) (TRL 7 8 System)- TidGen (TM) Power System Commercialization Project

    Broader source: Energy.gov [DOE]

    Ocean Renewable Power Co (ORPC) (TRL 7 8 System) - TidGen (TM) Power System Commercialization Project

  4. Princeton Power Systems (TRL 5 6 Component)- Marine High-Voltage Power Conditioning and Transmission System with Integrated Energy Storage

    Broader source: Energy.gov [DOE]

    Princeton Power Systems (TRL 5 6 Component) - Marine High-Voltage Power Conditioning and Transmission System with Integrated Energy Storage

  5. 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)

  6. Liquid metal cooled nuclear reactor plant system

    DOE Patents [OSTI]

    Hunsbedt, Anstein (Los Gatos, CA); Boardman, Charles E. (Saratoga, CA)

    1993-01-01

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

  7. General approach to assure compliance with ALARA guidelines on direct radiation from a nuclear power plant, January 1979-January 1982

    SciTech Connect (OSTI)

    Harding, W; Silver, C

    1983-06-01

    Nuclear Regulatory Commission guide lines specify 10 mrad per reactor as the total yearly direct (gamma) radiation dose at any point external to a nuclear power facility site boundary. Typically a nuclear utility submits only thermoluminescence dosimetry (TLD) data unaccompanied by corresponding core sample, ion chamber or other data or analyses to demonstrate compliance. This study considers a standard approach for analyzing the TLD data in terms of semiempirical physical constructs which allow the use of correlations among certain preoperational TLD data to predict or model operational period TLD measures (expected values) in the absence of the source (nuclear facility). These apriori models depend only upon their fit to the observed nonimpacted data for their verification. They are not veridical. The models are used to analyze a CaSO/sub 4/ (TM) thermoluminescence dosimetry system set up in a matrix about the nuclear plant and which records the terrestrial and cosmic radiation background as well as the nuclear plant contribution.

  8. Rethinking the Future Grid: Integrated Nuclear Renewable Energy Systems: Preprint

    SciTech Connect (OSTI)

    Bragg-Sitton, S. M.; Boardman, R.; Ruth, M.; Zinaman, O.; Forsberg, C.

    2015-01-01

    The U.S. DOE is supporting research and development that could lead to more efficient utilization of clean energy generation sources, including renewable and nuclear options, to meet both grid demand and thermal energy needs in the industrial sector. One concept under consideration by the DOE-NE and DOE-EERE is tighter coupling of nuclear and renewable energy sources in a manner that better optimizes energy use for the combined electricity, industrial manufacturing, and transportation sectors. This integration concept has been referred to as a 'hybrid system' that is capable of apportioning thermal and electrical energy to first meet the grid demand (with appropriate power conversion systems), then utilizing excess thermal and, in some cases, electrical energy to drive a process that results in an additional product.

  9. Nuclear electric propulsion: A better, safer, cheaper transportation system for human exploration of Mars

    SciTech Connect (OSTI)

    Clark, J.S.; George, J.A.; Gefert, L.P.; Doherty, M.P.; Sefcik, R.J.

    1994-03-01

    NASA has completed a preliminary mission and systems study of nuclear electric propulsion (NEP) systems for split-sprint' human exploration and related robotic cargo missions to Mars. This paper describes the study, the mission architecture selected, the NEP system and technology development needs, proposed development schedules, and estimated development costs. Since current administration policy makers have delayed funding for key technology development activities that could make Mars exploration missions a reality in the near future, NASA will have time to evaluate various alternate mission options, and it appears prudent to ensure that Mars mission plans focus on astronaut and mission safety, while reducing costs to acceptable levels. The split-sprint nuclear electric propulsion system offers trip times comparable to nuclear thermal propulsion (NTP) systems, while providing mission abort opportunities that are not possible with reference' mission architectures. Thus, NEP systems offer short transit times for the astronauts, reducing the exposure of the crew to intergalactic cosmic radiation. The high specific impulse of the NEP system, which leads to very low propellant requirements, results in significantly lower initial mass in low earth orbit' (IMLEO). Launch vehicle packaging studies show that the NEP system can be launched, assembled, and deployed, with about one less 240-metric-ton heavy lift launch vehicle (HLLV) per mission opportunity - a very Technology development cost of the nuclear reactor for an NEP system would be shared with the proposed nuclear surface power systems, since nuclear systems will be required to provide substantial electrical power on the surface of Mars. The NEP development project plan proposed includes evolutionary technology development for nuclear electric propulsion systems that expands upon SP-100 (Space Power - 100 kw(e)) technology that has been developed for lunar and Mars surface nuclear power.

  10. Indicator system for advanced nuclear plant control complex

    DOE Patents [OSTI]

    Scarola, Kenneth (Windsor, CT); Jamison, David S. (Windsor, CT); Manazir, Richard M. (North Canton, CT); Rescorl, Robert L. (Vernon, CT); Harmon, Daryl L. (Enfield, CT)

    1993-01-01

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

  11. 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.

  12. RADIOLOGICAL EMERGENCY RESPONSE PLANNING FOR NUCLEAR POWER PLANTS IN CALIFORNIA. VOLUME 4 OF THE FINAL REPORT ON HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA

    E-Print Network [OSTI]

    Yen, W.W.S.

    2010-01-01

    PLANNING FOR NUCLEAR POWER PLANTS: THE LICENSING PROCESSPlanning for Nuclear Power Plants Determination of Accidentnuclear power plants . . . . . . . . . • . . . . .2.2.4.3.

  13. Nuclear Hybrid Energy Systems: Challenges and Opportunities

    SciTech Connect (OSTI)

    P. Sabharwall; S.B. Sitton; S.J. Yoon; C. Stoots

    2014-07-01

    With growing demand of energy and costs of the fossil fuels, coupled with the environmental concerns have resulted in an increased interest in alternative energy sources. Nuclear hybrid energy systems (NHES) are being considered which incorporates renewable energy sources such as solar and wind energy combined with nuclear reactor and energy storage to meet the peak hours demand imposed on the grid, along with providing process heat for other potential industrial applications. This concept could potentially satisfy various energy demands and improve reliability, robustness and resilience for the entire system as a whole, along with economic and net efficiency gains. This paper provides a brief understanding of potential NHES system and architecture along with the challenges

  14. Doublet III neutral beam power system

    SciTech Connect (OSTI)

    Nerem, A.; Beal, J.W.; Colleraine, A.P.; LeVine, F.H.; Pipkins, J.F.; Remsen, D.B. Jr.; Tooker, J.F.; Varga, H.J.; Franck, J.V.

    1981-01-01

    The Doublet III neutral beam power system supplies pulsed power to the neutral beam injectors for plasma heating experiments on the Doublet III tokamak. The power supply system is connected to an ion source where the power is converted to an 80 kV, 80A, 0.5 sec beam of hydrogen ions at maximum power output. These energetic ions undergo partial neutralization via charge exchange in the beamline. The energetic neutral hydrogen atoms pass through the Doublet III toroidal and poloidal magnet fields and deposit their energy in the confined plasma. The unneutralized ions are deflected into a water-cooled dump. The entire system is interfaced through the neutral beam computer instrumentation and control system.

  15. Multi-Megawatt Power System Trade Study

    SciTech Connect (OSTI)

    Longhurst, Glen Reed; Schnitzler, Bruce Gordon; Parks, Benjamin Travis

    2001-11-01

    As part of a larger task, the Idaho National Engineering and Environmental Laboratory (INEEL) was tasked to perform a trade study comparing liquid-metal cooled reactors having Rankine power conversion systems with gas-cooled reactors having Brayton power conversion systems. This report summarizes the approach, the methodology, and the results of that trade study. Findings suggest that either approach has the possibility to approach the target specific mass of 3-5 kg/kWe for the power system, though it appears either will require improvements to achieve that. Higher reactor temperatures have the most potential for reducing the specific mass of gas-cooled reactors but do not necessarily have a similar effect for liquid-cooled Rankine systems. Fuels development will be the key to higher reactor operating temperatures. Higher temperature turbines will be important for Brayton systems. Both replacing lithium coolant in the primary circuit with gallium and replacing potassium with sodium in the power loop for liquid systems increase system specific mass. Changing the feed pump turbine to an electric motor in Rankine systems has little effect. Key technologies in reducing specific mass are high reactor and radiator operating temperatures, low radiator areal density, and low turbine/generator system masses. Turbine/generator mass tends to dominate overall power system mass for Rankine systems. Radiator mass was dominant for Brayton systems.

  16. INTEGRATED CONTROL OF NEXT GENERATION POWER SYSTEM

    SciTech Connect (OSTI)

    2010-02-28

    Control methodologies provide the necessary data acquisition, analysis and corrective actions needed to maintain the state of an electric power system within acceptable operating limits. These methods are primarily software-based algorithms that are nonfunctional unless properly integrated with system data and the appropriate control devices. Components of the control of power systems today include protective relays, supervisory control and data acquisition (SCADA), distribution automation (DA), feeder automation, software agents, sensors, control devices and communications. Necessary corrective actions are still accomplished using large electromechanical devices such as vacuum, oil and gas-insulated breakers, capacitor banks, regulators, transformer tap changers, reclosers, generators, and more recently FACTS (flexible AC transmission system) devices. The recent evolution of multi-agent system (MAS) technologies has been reviewed and effort made to integrate MAS into next generation power systems. A MAS can be defined as ��a loosely-coupled network of problem solvers that work together to solve problems that are beyond their individual capabilities��. These problem solvers, often called agents, are autonomous and may be heterogeneous in nature. This project has shown that a MAS has significant advantages over a single, monolithic, centralized problem solver for next generation power systems. Various communication media are being used in the electric power system today, including copper, optical fiber and power line carrier (PLC) as well as wireless technologies. These technologies have enabled the deployment of substation automation (SA) at many facilities. Recently, carrier and wireless technologies have been developed and demonstrated on a pilot basis. Hence, efforts have been made by this project to penetrate these communication technologies as an infrastructure for next generation power systems. This project has thus pursued efforts to use specific MAS methods as well as pertinent communications protocols to imbed and assess such technologies in a real electric power distribution system, specifically the Circuit of the Future (CoF) developed by Southern California Edison (SCE). By modeling the behavior and communication for the components of a MAS, the operation and control of the power distribution circuit have been enhanced. The use of MAS to model and integrate a power distribution circuit offers a significantly different approach to the design of next generation power systems. For example, ways to control a power distribution circuit that includes a micro-grid while considering the impacts of thermal constraints, and integrating voltage control and renewable energy sources on the main power system have been pursued. Both computer simulations and laboratory testbeds have been used to demonstrate such technologies in electric power distribution systems. An economic assessment of MAS in electric power systems was also performed during this project. A report on the economic feasibility of MAS for electric power systems was prepared, and particularly discusses the feasibility of incorporating MAS in transmission and distribution (T&D) systems. Also, the commercial viability of deploying MAS in T&D systems has been assessed by developing an initial case study using utility input to estimate the benefits of deploying MAS. In summary, the MAS approach, which had previously been investigated with good success by APERC for naval shipboard applications, has now been applied with promising results for enhancing an electric power distribution circuit, such as the Circuit of the Future developed by Southern California Edison. The results for next generation power systems include better ability to reconfigure circuits, improve protection and enhance reliability.

  17. 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.

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

    SciTech Connect (OSTI)

    Booker, S.; Katz, D.; Daavettila, N.; Lehnert, D. [MDC-Ogden Environmental and Energy Services, Southfield, MI (United States)

    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.

  19. Developing and assessing accident management plans for nuclear power plants

    SciTech Connect (OSTI)

    Hanson, D.J.; Johnson, S.P.; Blackman, H.S.; Stewart, M.A. (EG and G Idaho, Inc., Idaho Falls, ID (United States))

    1992-07-01

    This document is the second of a two-volume NUREG/CR that discusses development of accident management plans for nuclear power plants. The first volume (a) describes a four-phase approach for developing criteria that could be used for assessing the adequacy of accident management plans, (b) identifies the general attributes of accident management plans (Phase 1), (c) presents a prototype process for developing and implementing severe accident management plans (Phase 2), and (d) presents criteria that can be used to assess the adequacy of accident management plans. This volume (a) describes results from an evaluation of the capabilities of the prototype process to produce an accident management plan (Phase 3) and (b), based on these results and preliminary criteria included in NUREG/CR-5543, presents modifications to the criteria where appropriate.

  20. 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.